No. NG-T-6 - IAEA · missioning of fast reactors. In France, the programme on fast reactors has been considerably reduced. Many specialists who were involved in the studies and development

6.06mm

IAEA Nuclear Energy Series No. NP-T-6.3Fast Reactor Know

ledge Preservation System: Taxonom

y and Basic Requirements

INTERNATIONAL ATOMIC ENERGY AGENCYVIENNA

ISBN 978–92–0–100708–7ISSN 1995–7807

Basic Principles

Objectives

IAEA Nuclear Energy Series

Technical Reports

Fast Reactor Knowledge Preservation System: Taxonomy and Basic Requirements

No. NG-T-6.3

Guides

08-04321_P1320_covI-IV.indd 1 2008-11-19 14:24:04

FAST REACTOR KNOWLEDGE PRESERVATION SYSTEM:

TAXONOMY ANDBASIC REQUIREMENTS

The following States are Members of the International Atomic Energy Agency:

AFGHANISTANALBANIAALGERIAANGOLAARGENTINAARMENIAAUSTRALIAAUSTRIAAZERBAIJANBANGLADESHBELARUSBELGIUMBELIZEBENINBOLIVIABOSNIA AND HERZEGOVINABOTSWANABRAZILBULGARIABURKINA FASOCAMEROONCANADACENTRAL AFRICAN REPUBLICCHADCHILECHINACOLOMBIACOSTA RICACÔTE D’IVOIRECROATIACUBACYPRUSCZECH REPUBLICDEMOCRATIC REPUBLIC OF THE CONGODENMARKDOMINICAN REPUBLICECUADOREGYPTEL SALVADORERITREAESTONIAETHIOPIAFINLANDFRANCEGABONGEORGIAGERMANYGHANAGREECE

GUATEMALAHAITIHOLY SEEHONDURASHUNGARYICELANDINDIAINDONESIAIRAN, ISLAMIC REPUBLIC OF IRAQIRELANDISRAELITALYJAMAICAJAPANJORDANKAZAKHSTANKENYAKOREA, REPUBLIC OFKUWAITKYRGYZSTANLATVIALEBANONLIBERIALIBYAN ARAB JAMAHIRIYALIECHTENSTEINLITHUANIALUXEMBOURGMADAGASCARMALAWIMALAYSIAMALIMALTAMARSHALL ISLANDSMAURITANIAMAURITIUSMEXICOMONACOMONGOLIAMONTENEGROMOROCCOMOZAMBIQUEMYANMARNAMIBIANEPALNETHERLANDSNEW ZEALANDNICARAGUANIGERNIGERIANORWAY

PAKISTANPALAUPANAMAPARAGUAYPERUPHILIPPINESPOLANDPORTUGALQATARREPUBLIC OF MOLDOVAROMANIARUSSIAN FEDERATIONSAUDI ARABIASENEGALSERBIASEYCHELLESSIERRA LEONESINGAPORESLOVAKIASLOVENIASOUTH AFRICASPAINSRI LANKASUDANSWEDENSWITZERLANDSYRIAN ARAB REPUBLICTAJIKISTANTHAILANDTHE FORMER YUGOSLAV REPUBLIC OF MACEDONIATUNISIATURKEYUGANDAUKRAINEUNITED ARAB EMIRATESUNITED KINGDOM OF GREAT BRITAIN AND NORTHERN IRELANDUNITED REPUBLIC OF TANZANIAUNITED STATES OF AMERICAURUGUAYUZBEKISTANVENEZUELAVIETNAMYEMENZAMBIAZIMBABWE

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FAST REACTOR KNOWLEDGE PRESERVATION SYSTEM:

TAXONOMY ANDBASIC REQUIREMENTS

IAEA NUCLEAR ENERGY SERIES No. NG-T-6.3

INTERNATIONAL ATOMIC ENERGY AGENCYVIENNA, 2008

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IAEA Library Cataloguing in Publication Data

Fast reactor knowledge preservation system : taxonomy and basic requirements. — Vienna : International Atomic Energy Agency, 2008.

p. ; 29 cm. — (IAEA nuclear energy series, ISSN 1995–7807 ; no. NG-T-6.3)STI/PUB/1320ISBN 978–92–0–100708–7Includes bibliographical references.

1. Fast reactors — Databases. 2. Fast reactors — Data processing. I. International Atomic Energy Agency. II. Series.

IAEAL 08-00548

FOREWORD

The IAEA has taken the initiative to coordinate efforts of Member States in the preservation of knowledge in the area of fast reactors. In the framework of this initiative, the IAEA intends to create an international database compiling information from different Member States on fast reactors through a web portal. Other activities related to this initiative are being designed to accumulate and exchange information on the fast reactor area, to facilitate access to this information by users in different countries and to assist Member States in preserving the experience gained in their countries.

The purpose of this publication is to develop a taxonomy of the Fast Reactor Knowledge Preservation System (FRKPS) that will facilitate the preservation of the world’s fast reactor knowledge base, to identify basic requirements of this taxonomy on the basis of the experience gained in the fast reactor area, as well as results of previous IAEA activities on fast reactor knowledge preservation.

The need for such taxonomy arises from the fact that during the past 15 years there has been stagnation in the development of fast reactors in the industrialized countries that were involved, earlier, in intensive development of this area. All studies on fast reactors have been stopped in countries such as Germany, Italy, the United Kingdom and the United States of America and the only work being carried out is related to the decommissioning of fast reactors. Many specialists who were involved in the studies and development work in this area in these countries have already retired or are close to retirement. In countries such as France, Japan and the Russian Federation that are still actively pursuing the evolution of fast reactor technology, the situation is aggravated by the lack of young scientists and engineers moving into this branch of nuclear power.

Appreciation is expressed to all the participants who contributed to this publication. Particular thanks are due to Mahadeva Rao Koorapaty†, India; Yu.M. Ashurko, Russian Federation, and A. Badulescu, Romania for their assistance in the compilation of this report. The IAEA officers responsible for this report were A. Stanculescu and A. Kosilov of the Department of Nuclear Energy.

† Deceased.

EDITORIAL NOTE

The use of particular designations of countries or territories does not imply any judgement by the publisher, the IAEA, as to the legal status of such countries or territories, of their authorities and institutions or of the delimitation of their boundaries.

The mention of names of specific companies or products (whether or not indicated as registered) does not imply any intention to infringe proprietary rights, nor should it be construed as an endorsement or recommendation on the part of the IAEA.

CONTENTS

1. INTRODUCTION . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1

1.1. Objectives . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 11.2. Background . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 11.3. Scope . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 21.4. Structure . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2

2. MAIN PRINCIPLES OF THE FRKPS AND ITS TAXONOMY. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3

2.1. FRKPS concept. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 32.2. Main requirements for the FRKPS taxonomy . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4

3. FRKPS TAXONOMY . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4

4. FORMAT OF DOCUMENT PRESENTATION IN FRKPS. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 11

5. APPROACHES TO FORMATION OF TOPICAL LISTS OF KEY WORDS . . . . . . . . . . . . . . . . . . 12

6. BASIC REQUIREMENTS FOR THE FRKPS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 13

7. FUTURE ACTIONS ON FRKPS DEVELOPMENT. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 13

8. CONCLUSIONS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 14

APPENDIX: STRUCTURE OF BRANCHES OF STAGE-TOPICAL FRKPS MATRIX . . . . . . . . . . . . 15

REFERENCES . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 75ABBREVIATIONS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 77CONTRIBUTORS TO DRAFTING AND REVIEW . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 79

1. INTRODUCTION

1.1. OBJECTIVES

The purpose of this publication is to develop a taxonomy of the Fast Reactor Knowledge Preservation System (FRKPS) that will facilitate the preservation of the world’s fast reactor knowledge base, to identify basic requirements of this taxonomy on the basis of the experience gained in the fast reactor area, as well as results of the previous IAEA activities on fast reactor knowledge preservation. Throughout this publication the meaning of the term ‘taxonomy’ is in accordance with its definition given in Ref. [1]: Taxonomy — a hierarchical structure in which a body of information or knowledge is categorized, allowing an understanding of how that body of knowledge can be broken down into parts, and how its various parts relate to one another. Taxonomies are used to organize information in systems, thereby helping users to find it”.

1.2. BACKGROUND

The need for such a taxonomy arises from the fact that during the past 15 years there has been stagnation in the development of fast reactors in the industrialized countries that were involved, earlier, in intensive development in this area. All studies on fast reactors have been stopped in countries such as Germany, Italy the United Kingdom and the United States of America, and the only work being carried out related to the decom-missioning of fast reactors. In France, the programme on fast reactors has been considerably reduced. Many specialists who were involved in the studies and development work in this area in the above countries have already retired or are close to retirement. Besides, in countries such as France, Japan and the Russian Federation that are still actively pursuing the evolution of fast reactor technology, the situation is aggravated by the lack of young scientists and engineers moving into this branch of nuclear power.

However, the global scientific community acknowledges that fast reactors are promising and are essential for tapping the huge potential of nuclear power for contributing to the economic development of the world. A confirmation of this thesis may be seen from the development of fast reactors in Asia (China, India, Japan, Republic of Korea) as well as the revival of interest in fast reactors in the developed countries within the framework of the INPRO and Generation-IV programmes. This is the evidence that fast reactor technology will undoubtedly play an important role in the future.

In this connection, preservation of knowledge and experience gained in the fast reactor area assumes great importance in forming the basis for further improvements in designs of future fast reactors. Efforts are being made in the countries concerned to varying degrees in order to ensure the preservation of the worldwide knowledge and experience gained so far.

France has done considerable work on preservation of knowledge and experience gained in the development of sodium cooled fast reactors (RAPSODIE, PHENIX, SUPERPHENIX, EFR and experimental facilities), as well as operating experience and has established some documentary banks. The largestdocumentary bank, called MADONA Encyclopaedia [2, 3], includes all aspects of technology of sodium cooled fast reactors (SFR). A special database has been created on all components and systems of the Superphenix reactor [3].

In Japan, all technical documents and principal databases are stored in various topical systems of knowledge preservation on SFR and, in particular, on the JOYO research reactor [4, 5] and MONJU demon-stration reactor [5]. Currently, a discussion on a general database on SFR and its development for JNC/JAERI (Japan Nuclear Cycle Development Institute/Japan Atomic Energy Research Institute) Joint Institute is under way. A special Super Archive has been created in the UK for the purpose of preservation of experience gained in the SFR area, in particular at the Prototype Fast Reactor (PFR) [6]. An electronic catalogue of documents issued on the research reactor KNK-II has been created [7]. Some work has been carried out in the Russian Federation on the preservation of knowledge on fast reactors. In particular, a database on experimental studies carried out at BFS-1 (Bolshoi Fizicheskiy Stand-1), BFS-2 (Bolshoi Fizicheskiy Stand-2) and KOBR (Koltsevoi Bystryi Reaktor) critical facilities at the IPPE (Institute for Physics and Power Engineering) has been

1

created [8]. A bibliographical catalogue of documents on SFR issued has been developed with IPPE participation.

The above approaches systematize the knowledge and experience on fast reactors gained at specific reactor facilities that have been designed, constructed and operated in each country. Such an approach is justified in general since preservation of practical experience and knowledge gained in design, construction and operation of specific reactors is undoubtedly an urgent task.

Preservation of knowledge gained in the SFR area has already acquired an international significance and has received a high priority within the framework of IAEA activities in this area. Several IAEA meetings have been organized on the preservation of SFR knowledge, including those held in Cadarache, France (March 2002), Idaho Falls, USA (April 2002), Daejeon, Republic of Korea (May 2003) and Obninsk, Russian Federation (February 2005). A preliminary version of the FRKPS structure was proposed at an IAEA consultants meeting in December 2004 in Vienna. This publication further develops the generalized FRKPS structure on the basis of:

— SFR experience gained in the Russian Federation;— Suggestions and recommendations received at the IAEA meetings on this topic;— Successful approaches implemented in the course of development of specific systems of SFR knowledge

preservation in some countries such as France and Japan.

It should be noted that the structure means not only the arrangement of information in FRKPS, but also the format of its presentation.

1.3. SCOPE

The IAEA has taken the initiative to coordinate efforts of the Member States in the preservation of knowledge in the area of fast reactors. In the framework of this initiative, the IAEA intends to create an interna-tional database combining information from different Member States on fast reactors through a web portal it has established and maintained. Other activities related to this initiative are being designed to provide accumu-lation and exchange of information on documents issued in the fast reactor area, to facilitate access to this information by users in different countries and to assist the Member States in preserving the experience gained in their countries.

A consultants meeting was held in Vienna in December 2004 , to discuss the issues of development and maintenance of an international FRKPS. An outcome of this meeting was the recognition that the creation of the taxonomy of the FRKPS was one of the urgent tasks for this purpose and a preliminary draft was developed. Under the coordination of the IAEA, the taxonomy was further developed to its current form based on a study of the Russian experience on fast reactors. Results of this study were also reviewed by experts from the USA and the IAEA at a special meeting organized for this purpose. This publication consolidates the results of the above study and lays the foundation for the taxonomy of the international database on fast reactors, along with the next steps that will formulate the required computer software and then test the concept with a pilot programme from participating countries. Thus the report may be useful for computer specialists who will create the software for the IAEA web portal, as well as for those who wish to develop similar electronic databases on fast reactors in different countries.

1.4. STRUCTURE

This publication describes the taxonomy of FRKPS and its basic requirements. Section 2 presents the concept of the FRKPS and its structure, and formulates the main requirements to be met by this taxonomy. Section 3 describes the FRKPS taxonomy that was developed, taking into account the requirements formulated in the previous section as well as proposals put forth at the IAEA consultants meeting in Vienna. Specific features, including a generalized topical structure that is universally applicable to different stages of development of fast reactors, are also discussed as a component of the FRKPS (specific branches of root structure of the FRKPS are presented in the Annex). Section 4 describes the format of presentation of

2

documents to be included in the FRKPS. Section 5 is devoted to the role of key words in the developed FRKPS taxonomy and an approach to their formation. Section 6 presents some recommendations to the users on desirable opportunities in the FRKPS. Section 7 describes further work that should be carried out on the FRKPS.

2. MAIN PRINCIPLES OF THE FRKPS AND ITS TAXONOMY

For the development of an appropriate taxonomy for the FRKPS it is necessary to describe the concept of this system and then to identify the requirements and principles that should be satisfied when developing its structure.

2.1. FRKPS CONCEPT

The main elements constituting the FRKPS concept are the following:

— The purpose for which the FRKPS database is created;— The knowledge area covered by this database;— The approach to presentation of information, which is contained in FRKPS;— Target users of this database.

Elaboration of each of the above elements gives rise to the proposed concept of the FRKPS described below.The main purpose of FRKPS is to ensure preservation of SFR knowledge and experience gained in

different countries in a form that facilitates effective search and use of the stored information. It is assumed that a carefully structured electronic database would not only preserve knowledge on fast reactors, but also facilitate classification of information on SFRs accumulated in different countries and exchange of this information between countries.

The knowledge area covered by this database pertains to the knowledge accumulated on SFRs, since real experience is available only on this type of fast reactor. The database should cover all aspects of reactor technology related to SFRs, as well as all options for implementation (including personnel training and lessons learned from different phases of SFR development and implementation) ever used, since this is the only way to ensure preservation of SFR technology as a whole. Nevertheless, the taxonomy of FRKPS under development should also have the flexibility for storing information on other types of fast reactor in case they are chosen for implementation in the future.

The approach to the presentation of information contained in the FRKPS database is primarily based on the fact that it should be an electronic database, since that is the only option that offers the capability for a rapid and effective search of the required information. It is obvious that classification of the wide variety of available documents and other materials on fast reactors requires a unified approach to the presentation of these documents in the database. There are two possible methods for unification of document presentation in the FRKPS.

The first method is modification of the original documents in accordance with a pre-developed and unified electronic format, including their translation into any one language chosen for FRKPS, for example English. Such an approach appears to be hardly feasible because of the enormous scope of work and, hence, considerable demands on financial and time resources. Besides, if some documents contain proprietary information this may become a significant barrier to including these documents in the common database.

The second method, which is based on concise information cards that reflect the content of the original documents, is more practical. This does not preclude storage of the original document in the FRKPS if the owner agrees. The documents would not be modified from the original language. Thus, some documents would be transferred to the FRKPS in full while others that perhaps contain proprietary information would exist in the FRKPS only with a concise description of the content on the information card. This approach requires that the

3

owner of the document guarantees its existence and that the information card that is prepared in a specific format indicates the location of the document. When necessary, the user of the FRKPS can contact the document owner for permission to obtain the original document.

The target users of the FRKPS will likely be specialists working in the area of fast reactors and students. Fast reactor technology embraces a wide range of disciplines. Thus, the FRKPS taxonomy must reflect this range of disciplines with multiple divisions such as neutronics, fuels and materials, thermal hydraulics, etc.

2.2. MAIN REQUIREMENTS FOR THE FRKPS TAXONOMY

Based on the above proposed concept for the FRKPS, specific requirements (criteria) to be met by the taxonomy of this information system are discussed below:

— Sufficient versatility, making it possible to cover all possible types of fast reactor in addition to SFR, and thus taking into account all possible trends of development of fast reactor technology.

— Adequate unification assuming common topical sections related to all types of fast reactor, as well as a unified format of material presentation. This should significantly facilitate the use and maintenance of the FRKPS.

— Adequate comprehensiveness to cover all aspects of fast reactor technology and all significant experience available on each specific reactor facility.

— A hierarchical nature of the structure that ensures a progressively detailed elaboration of each aspect of fast reactor technology with increasing structural level.

— An optimum range of the structure that excludes superfluous detail and hence facilitates database operation.

— Reasonable redundancy, allowing duplication of information in various sections of the system to ensure the presentation of complete information at the level of some system sections.

— Capability of developing and expanding, if necessary, thus facilitating maintenance of the system.

3. FRKPS TAXONOMY

The Vienna meeting proposed a hierarchical structure for the FRKPS taxonomy, consisting of two upper levels of the FRKPS that are represented as a two-dimensional matrix in which elements of the upper row are stages of implementation of reactor technology (1st structural level of FRKPS), and the columns under the upper row elements include topical sections corresponding to given stages of reactor technology implementation (2nd structural level of FRKPS). This matrix is shown in Fig. 1. It is proposed to divide each topical section presented in the matrix into progressively detailed subsections and connect them in such a way that each subsequent level is a more detailed presentation of the previous level. Therefore, each topical section of the upper level will have a certain branched root structure consisting of specialized topical sections.

The matrix is claimed to be versatile because its structure was developed with a hypothetical, generalized SFR power plant in mind. Moreover, this structure is applicable not only to any SFR nuclear power plant irrespective of the stage of its development, but also to any experimental fast reactor. This structure would undoubtedly be redundant with reference to some specific reactor facilities. However, this redundancy has an advantage because a given document may have information on any one of several aspects of the SFR. It should be noted that the matrix structure development is still far from complete. First, topical sections of the upper level require more development and expansion. Second, the root structure should be developed for all these sections. However, this approach to the development of FRKPS taxonomy with separation of stages and topical sections of reactor technology as shown in the matrix is considered to be highly useful. This approach, which may be called the universal stage topical hierarchical structure, (USTS), will be used in the following sections as a starting point for the development of a new FRKPS taxonomy.

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5

It was implied in the Vienna meeting that the USTS would be the structure for the entire database. However, it is now proposed that the USTS be a component of the FRKPS structure. The other component would be the structure for particular reactor facilities. This approach is taken based in anticipation that some users would search by topics or disciplines, while others may search the database by a particular reactor facility.

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(1) The top level (1st level) classifies reactor facilities into the following categories: — Experimental FR;— Demonstration and prototype nuclear power plant with FR;— Commercial nuclear power plant with FR;— General section containing information on all facilities, as well as activities performed without reference

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FIG. 2. First two levels of the FRKPS structure.

6

(2) The second level identifies each reactor facility (this level is absent for the general section).(3) The third and further levels correspond to structural levels of USTS described below. These levels are

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The USTS is applied to each reactor facility, as well as the general section. Figure 3 shows the USTS component for the FRKPS. It can be viewed as an expanded version of the USTS shown in Fig. 1. Each topic at

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nch

2-3

B

ran

ch 2

-4

Bra

nch

2-5

B

ran

ch 2

-6

Fu

el

Bra

nch

3-1

-1

Bra

nch

3-1

-2

Bra

nch

3-1

-3

Bra

nch

3-1

-4

Bra

nch

3-1

-5

Bra

nch

3-1

-6

Co

ola

nt

Bra

nch

3-2

-1

Bra

nch

3-2

-2

Bra

nch

3-2

-3

Bra

nch

3-2

-4

Bra

nch

3-2

-5

Bra

nch

3-2

-6

Str

uct

ura

l

mat

eria

ls

Bra

nch

3-3

-1

Bra

nch

3-3

-2

Bra

nch

3-3

-3

Bra

nch

3-3

-4

Bra

nch

3-3

-5

Bra

nch

3-3

-6

Ab

sorb

er

Bra

nch

3-4

-1

Bra

nch

3-4

-2

Bra

nch

3-4

-3

Bra

nch

3-4

-4

Bra

nch

3-4

-5

Bra

nch

3-4

-6

3

Mat

eria

l

beh

avio

ur

Oth

er m

ater

ials

B

ran

ch 3

-5-1

B

ran

ch 3

-5-2

B

ran

ch 3

-5-3

B

ran

ch 3

-5-4

B

ran

ch 3

-5-5

B

ran

ch 3

-5-6

4

Saf

ety

Bra

nch

4-1

B

ran

ch 4

-2

Bra

nch

4-3

B

ran

ch 4

-4

Bra

nch

4-5

B

ran

ch 4

-6

5

Syst

ems

& e

qu

ipm

ent

Bra

nch

5-1

B

ran

ch 5

-2

Bra

nch

5-3

B

ran

ch 5

-4

Bra

nch

5-5

B

ran

ch 5

-6

6

Co

ntr

ol

& m

onit

ori

ng

Bra

nch

6-1

B

ran

ch 6

-2

Bra

nch

6-3

B

ran

ch 6

-4

Bra

nch

6-5

B

ran

ch 6

-6

7

Eco

logy

& e

nvir

on

men

t B

ran

ch 7

-1

Bra

nch

7-2

B

ran

ch 7

-3

Bra

nch

7-4

*

Bra

nch

7-5

B

ran

ch 7

-6

8

Co

des

B

ran

ch 8

-1

Bra

nch

8-2

B

ran

ch 8

-3

Bra

nch

8-4

*

Bra

nch

8-5

B

ran

ch 8

-6

9

His

tory

& o

ther

asp

ects

B

ran

ch 9

-1

Bra

nch

9-2

B

ran

ch 9

-3

Bra

nch

9-4

B

ran

ch 9

-5

Bra

nch

9-6

FIG. 3. The first two levels of the USTS (stage & topic matrix).

7

the third level of the FRKPS taxonomy corresponding to the first level of the USTS is expanded to an additional level of detail related to reactor technology stages (the fourth level of the FRKPS taxonomy and the second level of the USTS). This breakdown is logical because a given topic can be a part of all stages. For example, the information on the topic ‘Material Behaviour’ can apply to all stages of reactor development. Thus, this structure would be convenient to specialists in certain disciplines and students searching the database.

The topical items shown in Fig. 3 are based on experience gained with SFRs, although the USTS will be capable of incorporating information from other reactor types.

Thus, at the first structural level of the USTS, in Fig. 3, the following basic topical sections of fast reactor (FR) technology are listed:

(1) Aspects of FR neutronics;(2) Aspects of FR thermal hydraulics and thermal physics;(3) Problems related to FR materials, including fuel, coolant and its technology, structural materials, absorbers

and other auxiliary materials;(4) FR safety issues, including analysis of safety characteristics, safety systems and development of standards

and regulatory documents;(5) Technological systems and components — conceptual approaches and design studies on the systems and

components, their specific implementation and operation modes;(6) FR control and monitoring issues, including those on related systems;(7) FR ecological aspects and environmental impact;(8) FR mathematical modelling, including calculation results, computer codes in use and their description;(9) Economic and other aspects of FR, as well as historical documents, including memoirs, photographs,

movies, etc.;

Each of the topics shown in Fig. 3 is aimed at specific objectives or target functions. The target functions for each topic are given in Table 1.

The target functions for two areas need further discussion. These areas are: (1) design studies on systems and components, (2) FR mathematical modelling. These two areas of activity are closely connected and are a necessary component of many aspects of FR technology. For instance, development of nuclear fuel requires modelling and the specified performance of the fuel depends on design studies. However, these two areas of work were specified as separate topical sections because of their specific features. In Table 1 the area entitled Technological Systems and Components includes all FR systems and components except for safety systems, which are included under Safety Issues, and control and monitoring systems, which are included under Monitoring and Control. These FR technological systems and components are separate subsections of the Technological Systems and Components section.

On the basis of the SFR development history, many of the target functions are dependent on each other and a given target function may be applicable to more than one system or component. Some examples are given below:

— A controlled chain reaction is assured by a certain configuration and condition of reactor core (neutronics and thermal hydraulics) and performance of control and safety systems (monitoring and control, and safety issues);

— Decay heat removal from the reactor in the shutdown condition depends both on thermal hydraulics and safety aspects;

— For instance, the section related to mathematical modelling contains information that was developed to contribute to the solution of problems inherent in target functions defined in other FR technology areas (justification of decisions made in various aspects of FR technology, safety justification, etc.).

The above considerations demonstrate that one document may be related to several topical sections and, hence, it should be recorded in all related FRKPS sections. Thus reasonable redundancy must be allowed in the FRKPS for placement of a document (or its reference) in the different topical sections.

The list of general topical sections given in Table 1 is complemented by a section intended for accumu-lation of various facts on FR development history, such as photographs, movies, memoirs, etc. This section,

8

entitled Economic and Other Aspects, could be used for additional aspects of FR technology. The provision of such a section makes it possible to ensure the preservation of a comprehensive account of all information on FR which does not fall into the other topical sections.

Subsections corresponding to some categories of materials used in FR (fuel, coolant, structural materials, absorbers and auxiliary materials) are provided in a main topical section such as Material Behaviour.

The list of topical sections shown in Fig. 3 is intended to cover all areas of reactor technology related to fast reactors. The only exceptions are issues of fuel reprocessing technology within the framework of the fuel cycle. This topic is not presented as an independent topical section in the above list, since these issues are quite specific and do not relate directly to reactor technology itself. However, some specific issues related to the fuel cycle are contained in other topical sections and these issues have been taken into account in the corresponding subsec-tions.

In order to facilitate the use of USTS during its development, it is proposed to use abbreviated titles of the 1st level sections. These abbreviations are given in Table 2.

TABLE 1. TARGET FUNCTION FOR EACH ASPECT OF REACTOR TECHNOLOGY

General aspect of reactor technology

Target function

NeutronicsAssurance of controlled fission chain reaction under normal operating conditionsAssurance of protection of components and personnel against radiationAssurance of subcriticality under required conditions

Thermal hydraulics andthermal physics

Assurance of heat transfer and removal from the core to the tertiary circuitAssurance of required operating conditions of systems and components

Materials

Fuel Assurance of fuel serviceability in the fuel elements

Coolant Assurance of required coolant technology

Structural materials Assurance of serviceability of various nuclear power plant elements and components

Absorber Assurance of serviceability of absorber element materials

Other materials Assurance of serviceability of building structures, auxiliary systems and services

Safety issues

Justification and assurance of safe nuclear power plant operation under abnormal operating conditions, design basis accidents (DBAs) and beyond design basis accidents (BDBAs)Development and operation of safety systemsElaboration of criteria and requirements on assurance of FR safety

Technological systems and components

Development and adoption of principal conceptual decisions on composition and arrangement of technological systems, components and elements of nuclear power plant with FRDevelopment, design and operation of technological systems and components of nuclear power plant with FR

Monitoring and controlAssurance of monitoring and control of various parameters and characteristics of nuclear power plant and maintaining these characteristics within required range of values

EcologyMinimization of radiological and other effect on personnel and environmentChoice of nuclear power plant site, taking into account environmental impact

Mathematical modellingAdequate modelling of FR elements and systems and processes taking place in these systems

Economic and other aspectsComparative economic analysis of operation of nuclear power plants with FRPreservation of data on FR history — memoirs, photos and newsreel

9

The distribution of problems and the types of specialists needed to solve these problems will change with the stage of FR development. The specialists of various types who are involved, namely researchers, engineers, designers, operating personnel and regulatory body representatives will change with the degree of involvement depending on the stage. Such a division should be taken into account in the USTS. Therefore, the stages of fast reactor technology implementation are specified as the second level of USTS, in accordance with the list given in Fig. 1, excluding the Fuel Cycle stage. The stages of implementation are listed below:

(1) Basic Principles: Stage of development of basic principles and concept of the future nuclear power plant;(2) R & D: Stage of R & D work for support of nuclear power plant design and design approaches used within

its framework;(3) Design, Analysis, Licensing: Stage of development of nuclear power plant design and its licensing by the

regulatory body;(4) Manufacturing & Construction: Stage of nuclear power plant construction, manufacture and installation of

reactor components and systems;(5) Operation: Stage of nuclear power plant commissioning and operation to its final shutdown;(6) Decommissioning: Stage of development of nuclear power plant decommissioning project and its imple-

mentation.

All the stages listed above are applied to each specified nuclear power plant with its FR and components. The information from the specified nuclear power plant will thus exist in the FRKPS according to the stages shown above. The stage related to the fuel cycle mentioned in Fig. 1 is somewhat special, since it deals with adifferent subject, namely fresh and spent fuel and a set of systems and components intended for reprocessing or storage, depending on the fuel cycle concept adopted. Hence, the stage related to the implementation of the fuel cycle was not included in the USTS.

This breakdown of nuclear power plant development into stages follows the natural sequence of events in the implementation of any nuclear power plant with its specific design of FR or reactor plant. Of course, the major part of the work in the fast reactor area is carried out within the framework of development of a specific design. However, certain analytical and experimental studies in the area of fast reactors are carried out without application to a specific design. Such information will be placed in the section related to the R & D stage without indicating a specific facility.

TABLE 2. ABBREVIATED TITLES OF THE FIRST LEVEL SECTIONS

# Full title of topical section/subsectionBrief title of topical section/subsection

used in USTS of FRKPS

1 Aspects of FR neutronics Neutronics & reactor physics

2 Aspects of FR thermal hydraulics and thermal physics Thermal hydraulics & thermal physics3 Problems related to FR materials: Material behaviour:

—Fuel — Fuel—Coolant and their technology — Coolant—Structural materials — Structural materials—Absorber materials — Absorber materials—Other auxiliary materials — Auxiliary materials

4 FR safety issues Safety

5 Technological systems and components Systems & equipment

6 FR control and monitoring issues Control & monitoring

7 FR ecological aspects and environmental impact Ecology & environment

8 FR mathematical modelling Codes

9 Economic and other aspects of FR, including documents on FR history

History & other aspects

10

The first two levels adopted in the new USTS option are also represented as a stage topic matrix in Fig. 3. The root structure, the content of which is determined by the intersection of the topic section and the stage, refers to each cell of the matrix. These root structures, hereinafter called branches, have been numbered. The number of each branch is determined by the number of the section and the number of the stage to which it refers. The branches are hierarchical multi-level structures.

Some of branches in the matrix are marked with an asterisk (*) to indicate that the branch is absent due to the fact that the topic of work was not applicable at that stage. For example, Neutronics & Reactor Physics are not necessary elements of work at the Manufacturing & Construction or Decommissioning stages. The detailed structure of branches of the stage topic matrix is presented in the Annex.

In order to avoid excessive congestion of USTS, the extent of detail of the levels of its branches and related specific topical subsections is limited. The degree of detail of each branch goes down up to the level of system-functional problems related to a specific topical section, but not up to the level of specific components and elements. An exception is made for the main reactor plant components, such as steam generators (SG), interme-diate heat exchangers (IHX), main circulating pumps (MCP) etc., which are also included in USTS as separate subsections. Further detail of information up to the level of specific components and elements of systems is provided by use of key words. This approach to restriction of the number of levels in the branches and optimi-sation of FRKPS taxonomy makes it possible to also avoid excessive redundancy in duplicating placement of documents in different sections.

In order to ensure that the topical sections in the USTS are comprehensive, some FR components are included simultaneously in more than one topical section. For instance, the core is included in the Systems & Equipment and Neutronics & Reactor Physics sections.

General-industry components and off the shelf components and systems are not included in USTS. The proposed USTS has been developed as applied to a general nuclear power plant with an FR. Thus, this structure is sufficiently comprehensive but versatile enough to allow for further necessary extension.

4. FORMAT OF DOCUMENT PRESENTATION IN FRKPS

The method for inputing information (not the entire documents) into the FRKPS is by use of information cards (ICs). These information cards will follow a standard format. The ICs are the basic unit of the FRKPS. The advantage of this method is that it requires no translation of the original document. However, it is important that the IC gives an accurate and sufficient representation of the original document. The IC has to be comprehensive enough for the information to be correctly placed in all the pertinent sections of the FRKPS. The IC must also be comprehensive enough for the FRKPS to retrieve the information.

The format for the information included as a SQL file in English on the IC is given below:

(1) Title of the document; (2) Type of document (appropriate classification of the documents based on their type should be provided in

FRKPS, e.g. 1 — book, 2 — article, 3 — report, 4 — paper, 5 — theses, 6 — design document, 7 — code description, 8 — drawing, 9 — working material, 10 — memoirs, 11 — photographs, 12 — movies, etc. with necessary notes);

(3) Authors and institutions they represent; (4) Issuing country/countries of the document. (5) Title of magazine/publishing house issuing the document/meeting at which the document was presented; (6) Year of issue; (7) Volume of the document (number of pages); (8) Original document language; (9) Storage location of the hardcopy of the document (organization taking responsibility for storing the

original document; name of database, if available, in which the document has been included);(10) Set of key words (at least 10 key words for each document);

11

(11) Abstract of the document in the original language and in English (minimum number of characters, 1000, at least half of A4 format page, letter size 10, single spacing);

(12) Names of reactor facilities to which the document refers;(13) Names of reactor stages related to the document;(14) List of topical sections (directories) to which the document refers and where the reference labels should be

placed;(15) Indication of degree of accessibility of the original document;(16) Indication of availability of an electronic version of original document;(17) Electronic version of the original document as a separate document (if possible from the standpoint of its

confidentiality level);(18) Registration number (if available).

Each document is presented in FRKPS in 2 files (SQL file and PDF file). The necessary number of reference labels is stored in related sections (directories) of FRKPS. ICs are accessible to the user as PDF files. The name of the IC is the title of the document.

A search of related topical sections for insertion of a new IC into the FRKPS taxonomy is determined by prompting on the key words listed in the IC when compared to the key words in the different topical sections in the FRKPS. Matches of key words will determine where the new IC resides in the FRKPS.

It is necessary to provide within the framework of the FRKPS an opportunity for creation of ICs, not only for individual documents but also for some arrays of documents. These arrays of documents can be, for instance, proceedings of the topical meetings or conferences, sets of papers related to specific research, etc.

The unified IC format for documents inserted into the FRKPS should be agreed to by the Member States to provide consistency from one country to the next with regard to the volume and selection of input to the FRKPS. The unified format of IC enables its placement in the FRKPS by using a computer prompt.

5. APPROACHES TO FORMATIONOF TOPICAL LISTS OF KEY WORDS

Lists of key words in the IC that are specified for each document included in the FRKPS are important components of the FRKPS taxonomy. All specific information contained in every document of the FRKPS can be divided into two parts. One part of the information (up to the level of systems and main components or global aspects of FR technology) can be described by the root structure of the FRKPS; the other part of the information (up to the level of separate elements and particular aspects of the problem) will be described by the set of key words. Thus key words allow describing detail specific information of each document, which is not reflected in the branch structure of the FRKPS.

To make the FRKPS user friendly an effort should be undertaken to systematically develop key word sets for the topical sections of the FRKPS. These key words would be used by specialists or students to query the FRKPS. The following features will be incorporated within the framework of the FRKPS:

— Formation of a thesaurus of key words (in English).— Compatibility of the thesaurus with the INIS thesaurus to the maximum possible extent.— A hierarchical structure of key word sets arranged in accordance with the FRKPS topical structure. For

this purpose, it is proposed to form lists of key words for all levels in each topical section. The list of key words for every level should automatically contain key word arrays of lower levels of this branch.

— When a new IC to be inserted into the FRKPS has a new key word which is absent in the FRKPS key words lists, this key word will be automatically included in the list of key words of this topical section and all related higher level topical sections.

12

— Access to files with the lists of topical session key words would be provided to the users at any structural level for the purpose of familiarization and use in the course of a search. Of course, the users would not be able to change the key words.

The above concept of a thesaurus of key words for the FRKPS will promote its further development and improvement.

6. BASIC REQUIREMENTS FOR THE FRKPS

The proposed FRKPS taxonomy and format of document presentation are designed to provide the following opportunities to the users:

— Search of documents by going down along the chosen branch level structure;— Multi-vector search of documents by using key words. The following attributes can be used as key words:

topic, reactor facility, author, country, year, topical key words, etc;— Making various search options by the combination of attributes:

(a) Search of the documents containing a certain combination of attributes within the framework of one document — this means that all documents will be chosen, whose information cards contain all the specified combination of attributes (logic combination ‘and’ for specified attributes);

(b) Selection of the documents containing at least one out of a certain combination of attributes in the description of the document (logic combination ‘or’ for specified attributes);

(c) Combined search using a logic combination ‘and/or’ for specified attributes — in this case the ICs, which contain all attributes specified with logic condition ‘and’ and at least one out of the other attributes specified with logic condition ‘or’ will be chosen;

— Search of both the totality of the documents in FRKPS and some selected sections and topics;— Sequential search (with narrowing or change of search vector), allowing for several sequential search

iterations with narrowing of the list of selected documents;— If necessary, saving of the list of the documents resulting from a search in a separate temporary file in the

FRKPS;— Direct access to the information card of any document (and the document itself if it is in the FRKPS) from

the list of those selected as a result of a search;— Access to FRKPS section from which a particular document was selected by the user;— Consolidation of various files containing results of searches into a common file.

7. FUTURE ACTIONS ON FRKPS DEVELOPMENT

Development of the FRKPS taxonomy is only a part of the work on the creation of the FRKPS as a whole. For the development of an effective FRKPS it is necessary to perform the following additional tasks:

— Develop the concept of ‘user-system’ and ‘contributor system’ interfaces and work out the requirements to be met by the FRKPS to enable these interfaces to be effective and friendly to the users and contributors;

— Develop recommendations to the contributors regarding the use of a qualitative selection of documents whose ICs could be included in the FRKPS and on suitable measures that would ensure saving of the original documents by their owners and guarantee their availability to the authorized users;

— Develop the concept of links between the FRKPS and national databases on fast reactors;— Develop guidance for users and contributors to the FRKPS.

13

Experts in the fast reactor area and IT experts should participate in the implementation of these tasks, thus providing a multi-disciplinary approach. Also, the representatives of all Member States interested in development of the FRKPS should participate in this work to provide an agreed and unified approach to the preparation of documents for inclusion in this database.

The immediate need is the development of the concept and requirements to be met by the above-mentioned interfaces. This task is required to be completed before the development of software for the FRKPS taxonomy and user system and contributor system interfaces.

It would be expedient to request the Member States to initiate actions necessary to enhance the collection and preservation of memoirs, etc. on fast reactor experience.

8. CONCLUSIONS

A multi-level Universal Stage–Topical Structure has been developed for an electronic Fast Reactor Knowledge Preservation System that covers all stages of implementation of the reactor technology and all its topical aspects.

The list of criteria to be met by the structure under development has been formulated. The proposed taxonomy has attempted to meet these criteria, which include the following:

— The developed FRKPS taxonomy is sufficiently comprehensive and versatile, as well as capable of being expanded in the future;

— The FRKPS taxonomy is developed using a hierarchy principle, i.e. progressing from general aspects of a topic to more specific aspects as the level number increases.

For convenience of the users, substructures related to particular reactor facilities have been separated from the general FRKPS taxonomy.

Format (list of attributes) of the document presentation in FRKPS has been elaborated.Proposals on the principles of organization of the user queries into FRKPS have been developed. These

proposals and FRKPS taxonomy itself are adapted to provide easy access to the system and various options of search of documents. Procedures of search and insertion of new documents into the FRKPS will be automated to the maximum extent.

Recommendations on further activities on the FRKPS development have been made.

14

Appendix

STRUCTURE OF BRANCHES OF STAGE-TOPICAL FRKPS MATRIX

Neutronics&Reactor

Physics

Basic

Principles

Shielding

Concept

Level 3

Level 4

Level 5 Core Concept Design Spent Fuel Storage

Concept

FIG. A-1. Scheme of branch 1-1.

Neutronics &

R&D

Microphysical

Data

Level 3

Level 4

Level 5 Theoretical

Reactor Physics Experimental

Reactor Physics

Core Basic Design &

Shielding

Basic Design

Neutron Cross-

Section Data

Fission

Data

Critical Facilities

Neutronic

Experiments

Level 6

Reactor

Experiments

Critical Facility

Experiments

Radioactivity

Decay DataMA

Behaviour

Transients Lifetime End

Experiments

Level 7

Level 8

Reactor Physics

Code Development & Validation

Variations


Neutronics&Reactor

Physics

Design, Analysis,

Licensing

Shielding

Design

Level 3

Level 4

Level 5 Core Neutronic

Design

Spent Fuel Storage

Neutronic Design


15

Neutronics&Reactor

Physics

Operation

Low Power

Commissioning

Level 3

Level 4

Level 5

Startup Tests Full Power

Operation

First Criticality

Tests

Reactivity Effects

Tests

Lower Power

Tests

Reactivity Effects

Tests

Full Power

Tests

Reactivity Effects

Tests

Level 6


Thermal Hydraulics &

Basic

Principles

Core Thermal

Hydraulic Concept

Level 3

Level 4

Level 5 NPP Thermal

Hydraulic Concept

Thermal Physics


16

Lev

el 3

Lev

el 4

Lev

el 6

Lev

el 5

Lev

el 7

Lev

el 8

Ther

mal

Hydra

uli

cs &

Ther

mal

Ph

ysic

s

R&

D

Hea

t E

xch

anger

Ther

mal

Hydra

uli

cs

Core

Ther

mal

Hydra

uli

cs

Out-

of-

Pil

e

Exp

erim

ents

NP

P C

ircu

it

Ther

mal

Hydra

uli

cs

Shie

ldin

g

Ther

mal

Hydra

uli

cs

Pum

p

Hyd

rauli

cs

In-P

ile

Exp

erim

ents

Ther

mal

Hydra

uli

c

Dat

a

Theo

reti

cal

Ther

mal

Hydra

uli

cs

Exp

erim

enta

l

Ther

mal

Hydra

uli

cs

Exp

erim

enta

l F

acil

itie

sM

ater

ial

Ther

mal

Ph

ysic

al P

rop

erti

es

Hyd

rauli

c

Dep

end

enci

es

Hea

t E

xch

ange

Dep

end

enci

es

Ther

mal

Hydra

uli

c

Exp

erim

ents

Fuel

Coola

nt

Inte

ract

ion

Oth

er E

quip

men

t

Ther

mal

Hydra

uli

cs

Coola

nt

Boil

ing

Nat

ura

l

Convec

tion

Outl

et

Ple

nu

m

Inle

t

Ple

nu

m

IHX

SG

AH

X

Fuel

Coola

nt

Ste

el

Ab

sorb

er

Oth

er

Mat

eria

ls

Sodiu

m&

NaK

Lea

d

LB

C

Gas

Oth

er

Coola

nts

Met

alli

c

Fuel

Oxid

e

Fuel

Nit

ride

Fuel

Car

bid

e

Fuel

Oth

er

Fuel

s

Tra

nsi

ents

Sta

tic

Tes

ts

Nat

ura

l

Cir

cula

tion

Lif

etim

e E

nd

Tes

ts

Coola

nt

Boil

ing

Eq

uip

men

t T

her

mal

Hyd

rauli

c M

od

elli

ng

Nat

ura

l

Convec

tion

Coola

nt

Boil

ing

FC

I

FC

I

Sta

inle

ss

Ste

el

Fer

riti

c

Ste

el

Oth

er

Ste

els

Code

Dev

elop

men

t &

Val

idat

ion


17

Ther

mal

Hydra

uli

cs &

Ther

mal

Ph

ysic

s

Des

ign,

Anal

ysis

,

Lic

ensi

ng

Hea

t E

xch

anger

Ther

mal

Hyd

rauli

cs

Lev

el 3

Lev

el 4

Lev

el 6

Lev

el 5

C

ore

Ther

mal

Hydra

uli

cs

Nat

ura

l

Convec

tion

NP

P C

ircu

it

Ther

mal

Hydra

uli

cs

Shie

ldin

g

Ther

mal

Hydra

uli

cs

Pum

p

Hyd

rauli

cs

Oth

er E

quip

men

t T

her

mal

Hyd

rauli

cs

IHX

SG

AH

X

Mai

n P

um

p

Auxil

iary

Pum

p


18

Core Heat

Exchangers

Other Equipment

Pumps

Level 6

Manufacturing &

Construction

Thermal

Hydraulic

Level 3

Level 4

Level 7

Fuel SA

Fertile SA

Control &

Safety Rods

Main Pump

Auxiliary Pump

IHX

SG

AHX

Thermal Hydraulics &

Level 5

Thermal Physics

Parameters Control


19

Ther

mal

Hydra

uli

cs &

Ther

mal

Ph

ysic

s

Op

erat

ion

Oth

er

Eq

uip

men

t

Core

Nat

ura

l

Cir

cula

tion

Lev

el 3

Lev

el 4

Lev

el 7

Lev

el 6

P

um

ps

Hea

t

Exch

ang

ers

Tra

nsi

ents

Sta

tic

Tes

ts

Fuel

SA

Fer

tile

SA

Contr

ol

&

Saf

ety

Rods

IHX

SG

AH

X

Eq

uip

men

t

Ther

mal

Hydra

uli

cs

Inte

gra

l T

her

mal

Hyd

rauli

c T

ests

L

evel

5

Mai

n P

um

p

Auxil

iary

Pum

p


20

Thermal Hydraulics

& Thermal Physics

Decommissioning

Level 3

Level 4

Level 5 Spent Fuel Storage

Thermal Hydraulics


Material

Behaviour

Absorber

Level 3

Level 3a

Fuel

Coolant Structural

Materials

Other

Materials

Family Branch 3-1 Family Branch 3-2 Family Branch 3-3 Family Branch 3-4 Family Branch 3-5

FIG. A-11. Scheme of family branch 3.

Fuel

Basic Principles

Fuel Type

Option

Level 3a

Level 4

Level 5 Main Technical

Decisions

Fuel Cycle

Concept

Material

BehaviourLevel 3

FIG. A-12. Scheme of branch 3-1-1.

21

Fuel-Steel

Interaction

R&D

Carbide

Fuel

Level 3

Level 5 Metallic

Fuel Oxide

Fuel Nitride

Fuel

Other

Fuels

A

Fuel

Technology Irradiation

Tests

Material

Behaviour

Fuel

A A A A

Level 3a

Level 4

Level 6 Post Irradiation

Tests

Fuel Production

Method

Fuel

Reprocessing

Mechanical

Properties

Swelling

Level 7

Fuel

Properties

Chemical

Properties

Aqueous

Methods Non-Aqueous

Methods

Pellet

Fuel

Vipac

Fuel

Level 8

Code

Development &

lid iValidation


Design, Analysis,

Licensing

Carbide

Fuel

Level 3

Level 5 Metallic

Fuel Oxide

Fuel Nitride

Fuel

Other

Fuels

A

Fuel Production

Technology Fuel

Reprocessing

Material

Behaviour

Fuel

A A A A

Level 3a

Level 4

Level 6 Refueling

Schedule

Aqueous

Technology

Non-Aqueous

Technology

Pellet

Fuel

Vipac

Fuel

Level 7


22

Manufacturing&

Construction

Carbide

Fuel

Level 3

Level 5

Metallic

Fuel Oxide

Fuel Nitride

Fuel

Other

Fuels

Fuel Quality

Control

Material

Behaviour

Fuel Level 3a

Level 4

Level 6

Regulatory

Documents


Operation

Carbide

Fuel

Level 3

Level 5 Metallic

Fuel Oxide

Fuel Nitride

Fuel

Other

Fuels

A

Irradiation

Tests Post Irradiation

Tests

Material

Behaviour

Fuel

A A A A

Level 3a

Level 4

Level 6


23

Fuel

Tre

atm

ent

Fuel

Ins p

ecti

on

Fuel

Ins p

ecti

on

Fuel

Tre

atm

ent

Fuel

Ins p

ecti

on

Car

bid

e

Fuel

Oxid

e

Fuel

Oth

er

Fuels

Fuel

Ins p

ecti

on

Fuel

Tre

atm

ent

Fuel

Tre

atm

ent

Fuel

Ins p

ecti

on

Fuel

Tre

atm

ent

Nit

rid

e

Fuel

Met

alli

c

Fuel

Fai

led

Fuel

Fai

led

Fuel

Fai

led

Fuel

Fai

led

Fuel

Fai

led

Fuel

Lev

el 3

Lev

el 3

a

Lev

el 6

Lev

el 5

Lev

el 4

Lev

el 7

Mat

eria

l

Beh

avio

ur

Fuel

Dec

om

mis

sio

nin

g


24

Coo

lant

Bas

ic P

rinci

ple

s

Lev

el 3

a

Lev

el 4

Lev

el 5

M

ain T

echn

ical

Dec

isio

ns

Coo

lant

Opti

on

Mat

eria

l

Beh

avio

ur

Lev

el 3


25

Gas

L

ead

Oth

er

Coola

nts

L

BC

S

odiu

m &

NaK

Lev

el 3

Lev

el 3

a

Lev

el 7

Lev

el 5

Lev

el 4

Mat

eria

l

Beh

avio

ur

Coola

nt

R&

D

Coola

nt

Imp

uri

ty

Contr

ol

Met

hod

Coola

nt

Puri

fica

tion M

etho

d

Eq

uip

men

t

Cle

anin

g M

ethod

Coola

nt

Rep

roce

ssin

g M

ethod

Lev

el 8

Rad

ioac

tivit

y

Chem

ical

P

rop

erti

es

Coola

nt

Tec

hnolo

gy

Coola

nt

Pro

per

ties

Loca

liza

tion

Met

hod

Loca

liza

tion

Met

hod

Coola

nt

Pro

per

ties

Loca

liza

tion

Met

hod

Coola

nt

Tec

hnolo

gy

Gas

Tec

hnolo

gy

Gas

Pro

per

ties

A

B

B

A

SG

Lea

k

Pro

tect

ion M

etho

d

Coola

nt

Lea

k

Det

ecti

on M

ethod

Coola

nt

Fir

e

Exti

nguis

hin

g M

ethod

Coola

nt

Imp

uri

ty

Contr

ol

Met

hod

Coola

nt

Puri

fica

tion M

etho

d

Coola

nt

Oxid

izat

ion M

ethod

Eq

uip

men

t

Cle

anin

g M

ethod

Rad

ioac

tivit

y

Chem

ical

Pro

per

ties

SG

Lea

k

Pro

tect

ion M

etho

d

Coola

nt

Lea

k

Det

ecti

on M

ethod

Coola

nt

Rep

roce

ssin

g M

ethod

Gas

Im

puri

ty C

ontr

ol

Met

hod

Gas

Puri

fica

tion M

etho

d

Gas

Rep

roce

ssin

g

Met

hod

Rad

ioac

tivit

y

Chem

ical

Pro

per

ties

Gas

Lea

k

Pro

tect

ion M

etho

d

Gas

Lea

k

Det

ecti

on M

ethod

Coola

nt-

Wat

er

Inte

ract

ion

Coola

nt-

Air

Inte

ract

ion

Coola

nt-

Ste

el

Inte

ract

ion

Coola

nt-

Fuel

Inte

ract

ion

Coola

nt-

Wat

er

Inte

ract

ion

Coola

nt-

Ste

el

Inte

ract

ion

Coola

nt-

Fuel

Inte

ract

ion

Gas

-Ste

el I

nte

ract

ion

Gas

-Fuel

Inte

ract

ion

Act

ive

Met

hod

Pas

sive

Met

hod

Sm

all

Lea

k

Lar

ge

Lea

k

Lev

el 6

Code

Dev

elop

men

t&

Val

idat

ion

Code

Dev

elop

men

t&

Val

idat

ion

Code

Dev

elop

men

t&

Val

idat

ion


26

Gas

L

ead

Oth

er

Coola

nts

L

BC

Sodiu

m&

NaK

Lev

el 3

Lev

el 3

a

Lev

el 6

Lev

el 5

Lev

el 4

Mat

eria

l

Beh

avio

ur

Coola

nt

Des

ign,

Anal

ysis

,

Lic

ensi

ng

Coola

nt

Imp

uri

ty

Contr

ol

Tec

hnolo

gy

Coola

nt

Puri

fica

tion

Tec

hnolo

gy

Eq

uip

men

t C

lean

ing

Tec

hnolo

gy

Gas

Im

puri

ty C

ontr

ol

Tec

hnolo

gy

Gas

Puri

fica

tion

Tec

hnolo

gy

Coola

nt

Imp

uri

ty

Contr

ol

Tec

hnolo

gy

Coola

nt

Puri

fica

tion

Tec

hnolo

gy

Eq

uip

men

t C

lean

ing

Tec

hnolo

gy

Coola

nt

Imp

uri

ty

Contr

ol

Tec

hnolo

gy

Coola

nt

Puri

fica

tion

Tec

hnolo

gy

Eq

uip

men

t C

lean

ing

Tec

hnolo

gy

Coola

nt

Imp

uri

ty

Contr

ol

Tec

hnolo

gy

Coola

nt

Puri

fica

tion

Tec

hnolo

gy

Eq

uip

men

t C

lean

ing

Tec

hnolo

gy

Coola

nt

Oxid

izat

ion

Tec

hnolo

gy

Coola

nt

Oxid

izat

ion

Tec

hnolo

gy


27

Gas

Lea

d

Oth

er

Coo

lants

LB

C

Sod

ium

&N

aK

Lev

el 3

Lev

el 3

a

Lev

el 6

Lev

el 5

Lev

el 4

Mat

eria

l

Beh

avio

ur

Coo

lant

Man

ufa

cturi

ng&

Co

nst

ruct

ion

Coo

lant

Pro

duct

ion

Coo

lant

Tra

nsp

ort

atio

n

Coo

lant

Rec

epti

on

Tec

hno

log

y

Qual

ity

Co

ntr

ol

Coo

lant

Req

uir

em

ents

Coo

lant

Pro

duct

ion

Coo

lant

Tra

nsp

ort

atio

n

Coo

lant

Rec

epti

on

Tec

hno

log

y

Qual

ity

Co

ntr

ol

Coo

lant

Req

uir

em

ents

Coo

lant

Pro

duct

ion

Coo

lant

Tra

nsp

ort

atio

n

Coo

lant

Rec

epti

on

Tec

hno

log

y

Qual

ity

Co

ntr

ol

Coo

lant

Req

uir

em

ents

Coo

lant

Pro

duct

ion

Coo

lant

Tra

nsp

ort

atio

n

Coo

lant

Rec

epti

on

Tec

hno

log

y

Qual

ity

Co

ntr

ol

Coo

lant

Req

uir

em

ents

Coo

lant

Pro

duct

ion

Coo

lant

Tra

nsp

ort

atio

n

Coo

lant

Rec

epti

on

Tec

hno

log

y

Qual

ity

Co

ntr

ol

Coo

lant

Re q

uir

em

ents

Lev

el 7


28

Gas

Lea

d

Oth

er

Coo

lants

LB

C

Sod

ium

&N

aK

Lev

el 3

Lev

el 3

a

Lev

el 6

Lev

el 5

Lev

el 4

Mat

eria

l

Beh

avio

ur

Coo

lant

Oper

atio

n

Coo

lant

Puri

fica

tio

n

Equip

men

t

Cle

anin

g R

egim

e

Coo

lant

Dra

inage

Cas

es

Outs

ide

Lea

ks

SG

Lea

ks

Coo

lant

Lea

ks

Lea

d

Puri

fica

tio

n

Lea

d

Oxid

izat

ion

Equip

men

t

Cle

anin

g R

egim

e

Outs

ide

Lea

ks

SG

Lea

ks

Lea

d

Lea

ks

LB

C

Puri

fica

tio

n

LB

C

Oxid

izat

ion

Equip

men

t

Cle

anin

g R

egim

e

Outs

ide

Lea

ks

SG

Lea

ks

LB

C

Lea

ks

Gas

Puri

fica

tio

n

Gas

Lea

ks

Outs

ide

Lea

ks

Coo

lant

Puri

fica

tio

n

Equip

men

t

Cle

anin

g R

egim

e

Coo

lant

Dra

inage

Cas

es

Outs

ide

Lea

ks

SG

Lea

ks

Coo

lant

Lea

ks

Lev

el 7


29

Gas

Lea

d

Oth

er

Coo

lants

LB

C

Sod

ium

&N

aK

Lev

el 3

Lev

el 3

a

Lev

el 6

Lev

el 5

Lev

el 4

Mat

eria

l

Beh

avio

ur

Coo

lant

Dec

om

mis

sio

nin

g

Coo

lant

Puri

fica

tio

n

Coo

lant

Dra

inage

Coo

lant

Sto

rage

Coo

lant

Res

idues

Cir

cuit

Cle

anin

g

Coo

lant

Re p

roce

ssin

g

Lea

d

Puri

fica

tio

n

Lea

d

Dra

inage

Lea

d

Sto

rage

Coo

lant

Res

idues

Cir

cuit

Cle

anin

g

Lea

d

Rep

roce

ssin

g

LB

C

Puri

fica

tio

n

LB

C

Dra

inage

LB

C

Sto

rage

Coo

lant

Res

idues

Cir

cuit

Cle

anin

g

LB

C

Rep

roce

ssin

g

Coo

lant

Puri

fica

tio

n

Coo

lant

Dra

inage

Coo

lant

Sto

rage

Coo

lant

Res

idues

Cir

cuit

Cle

anin

g

Coo

lant

Rep

roce

ssin

g

Lev

el 7

Rep

roce

ssin

g

Tec

hno

log

y

Rep

roce

ssin

g

Fac

ilit

y

Rep

roce

ssin

g

Tec

hno

log

y

Rep

roce

ssin

g

Fac

ilit

y

Rep

roce

ssin

g

Tec

hno

log

y

Rep

roce

ssin

g

Fac

ilit

y

Rep

roce

ssin

g

Tec

hno

log

y

Rep

roce

ssin

g

Fac

ilit

y


30

Structural

Materials

Basic Principles

Level 3a

Level 4


Decisions

Steel

Type Option

Material

BehaviourLevel 3


31

Lev

el 6

Oth

er S

teel

s

Fer

riti

c S

teel

Sta

inle

ss S

teel

Lev

el 3

Lev

el 3

a

Lev

el 5

Lev

el 4

Mat

eria

l

Beh

avio

ur

Str

uct

ura

l

Mat

eria

ls

R&

D

Ste

el

Pro

per

ties

Ste

el

Tec

hno

log

y

Irra

dia

tio

n

Tes

ts

Po

st I

rrad

iati

on

Tes

ts

Imp

uri

ty A

dhes

ion

Inves

tigat

ion

Mec

han

ical

Pro

per

ties

Chem

ical

Pro

per

ties

Sw

elli

ng

Qual

ity C

ontr

ol

Met

hod

Wel

din

g

Met

hod

Lev

el 7

Ste

el

Pro

per

ties

Ste

el

Tec

hno

log

y

Irra

dia

tio

n

Tes

ts

Po

st I

rrad

iati

on

Tes

ts

Imp

uri

ty A

dhes

ion

Inves

tigat

ion

Mec

han

ical

Pro

per

ties

Chem

ical

Pro

per

ties

Sw

elli

ng

Qual

ity C

ontr

ol

Met

hod

Wel

din

g

Met

hod

Ste

el

Pro

per

ties

Ste

el

Tec

hno

log

y

Irra

dia

tio

n

Tes

ts

Po

st I

rrad

iati

on

Tes

ts

Imp

uri

ty A

dhes

ion

Inves

tigat

ion

Mec

han

ical

Pro

per

ties

Chem

ical

Pro

per

ties

Sw

elli

ng

Qual

ity C

ontr

ol

Met

hod

Wel

din

g

Met

hod

Co

de

Dev

elo

pm

ent&

Validat

ion


32

Ferritic

Steel Other

SteelsStainless

Steel

Level 3

Level 3a

Level 6

Level 5

Level 4

Material

Behaviour

Structural

Design, Analysis,

Licensing

Steel

Treatment

Welding

Technology

Resource

Parameters

Steel

Treatment

Welding

Technology

Resource

Parameters

Steel

Treatment

Welding

Technology

Resource

Parameters

Materials


Regulatory

Documents Steel

Quality Control

Level 3

Level 3a

Level 5

Level 4

Material

Behaviour

Structural

Manufacturing&

Construction

Ferritic

Steel Other

Steels

Stainless

Steel

Level 6

Material s


33

Ferritic

SteelOther

SteelsStainless

Steel

Level 3

Level 3a

Level 6

Level 5

Level 4

Material

Behaviour

Structural Materials

Operation

Quality

Control

Resource

Tests

Irradiation

Tests

Quality

Control

Resource

Tests

Irradiation

Tests

Quality

Control

Resource

Tests

Irradiation

Tests

Post Irradiation

Tests Post Irradiation

Tests

Post Irradiation

Tests


Ferritic

Steel Other

Steels Stainless

Steel

Level 3

Level 3a

Level 6

Level 5

Level 4

Material

Behaviour

Structural

Materials

Decommissioning

Surface Decontamination

Method

Radioactivity

Control

Lifetime End

Tests


Method

Radioactivity

Control

Lifetime End

Tests


Method

Radioactivity

Control

Lifetime End

Tests


34

Absorber Materials

Basic Principles

Level 3a

Level 4

Level 5 Main Technical Decisions Absorber

Type Option

Material

Behaviour

Level 3


Level 3

Level 3a

Level 6

Level 5

Level 4

Level 7

Absorber

Technology

Absorber

Properties

Material

Behaviour

Absorber Materials

R&D

Mechanical

Properties

Swelling

Chemical

Properties

Absorber-Steel

Interaction

Absorber Production

Method

Absorber Reprocessing

Method

Irradiation

Tests

Post Irradiation

Tests

Code Development&

Validation


35

Absorber Materials

Design, Analysis,

Licensing

Absorber Reprocessing

Technology

Level 3a

Level 4

Level 5 Absorber

Production

Refueling

Schedule

Material

BehaviourLevel 3


Absorber Materials

Manufacturing&

Construction

Level 3a

Level 4

Level 5 Absorber Quality

Control

Regulatory

Documents

Material

BehaviourLevel 3


Absorber Materials

Operation

Level 3a

Level 4

Level 5 Irradiation

Tests

Post Irradiation

Tests

Material

BehaviourLevel 3


36

Absorber Materials

Decommissioning

Level 3a

Level 4

Level 5 Absorber Rod

Inspection

Absorber Rod

Treatment

Material

BehaviourLevel 3

Failed

Absorber Rods Level 6


Other Materials

Basic Principles

Level 3a

Level 4


Decisions

Material

Options

Material

BehaviourLevel 3


37

Heat

Isolation

Concrete

Level 6

Material

Behaviour

Other Materials

R&D

Cable

Material

Other

Materials

Heat Isolation

Properties

Concrete

Properties Cable Material

Properties

Material

Properties

Coolant-Heat

Isolation

Fire

Resistance

Fire

Resistance

Mechanical

Properties

Chemical

Properties

Coolant-Concrete

Interaction

Level 7

Level 3

Level 3a

Level 5

Level 4

Level 8

Code Development&

Validation


Heat

Isolation

Concrete

Level 3

Level 3a

Level 6

Level 5

Level 4

Material

Behaviour

Other Materials

Design, Analysis,

Licensing

Cable

Material

Other

Materials

Design

Requirements

Design

Requirements

Design

Requirements

Design

Requirements


38

Regulatory

DocumentsQuality

Control

Level 3

Level 3a

Level 5

Level 4

Material

Behaviour

Other Materials

Manufacturing&

Construction

Heat

Isolation Cable

Material

Concrete Level 6 Other

Materials


Resource

Tests

Inspection

Level 3

Level 3a

Level 5

Level 4

Material

Behaviour

Other Materials

Operation

Heat

Isolation Cable

Material

Concrete Level 6 Other

Materials


39

Heat

Isolation

Concrete

Level 3

Level 3a

Level 6

Level 5

Level 4

Material

Behaviour

Other Materials

Decommissioning

Cable

Material

Other

Materials

Concrete

Inspection

Concrete

Treatment

Material

Inspection

Material

Treatment

Material

Inspection

Material

Treatment

Material

Inspection

Material

Treatment


Basic Principles

Safety

Safety Philosophy

Safety Standards

Key Safety

Requirements

Key Safety

Decisions

Level 3

Level 4

Level 5

Level 6


40

Saf

ety

R

&D

Ab

norm

al

Cas

es

Qual

ity

Contr

ol

DB

A

BD

BA

Saf

ety

Rel

ated

E

xp

erim

ents

Sodiu

m F

ire

Exti

nguis

hin

g

Sys

tem

Sodiu

m L

eak

Det

ecti

on

Sys

tem

SG

Lea

k

Pro

tect

ion

Sys

tem

Saf

ety

Sys

tem

s

Lev

el 3

Lev

el 4

Lev

el 6

Lev

el 7

Lev

el 8

Lev

el 5

Lev

el 9

Saf

ety

Anal

ysis

Pro

bab

ilis

tic

Saf

ety

Ass

essm

ent

Exp

erim

enta

l

Res

ult

s

In-P

ile

Exp

erim

ents

Out-

of-

Pil

e

Exp

erim

ents

Exp

erim

enta

l

Fac

ilit

ies

Tra

nsi

ents

Nat

ura

l

Cir

cula

tion

Coola

nt

Boil

ing

Tra

nsi

ent

Model

ling

Nat

ura

l

Convec

tion

Coola

nt

Boil

ing

Coola

nt

Lea

kag

e

Lif

etim

e E

nd

Tes

ts

FC

I

Post

-CD

A

Tes

ts

Pro

tect

ion

Sys

tem

s

Loca

lizi

ng

Sys

tem

s

Supp

ly

Sys

tem

s

Shutd

ow

n

Sys

tem

D

HR

S

Sei

smic

P

rote

ctio

n

Eq

uip

men

t

Ele

ctri

city

S

upp

ly S

yst

emW

ater

Supp

ly

Sys

tem

Oth

er S

up

ply

Sys

tem

s S

odiu

m&

NaK

Lea

d

LB

C

Gas

R

eact

ivit

y

BD

BA

Hea

t R

emo

val

B

DB

A

Coola

nt

Lea

kag

e B

DB

A

Oth

er

BD

BA

Saf

ety

Sta

ndar

ds

Wat

er F

inal

Hea

t S

ink

Air

Fin

al H

eat

Sin

k

Ter

tiar

y C

ircu

it

Sys

tem

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epen

den

t

Sys

tem

DR

CS

ICC

S

RV

CS

SG

Lea

k

Pro

tect

ion

Sys

tem

SG

Lea

k

Pro

tect

ion

Sys

tem

Act

ive

Sys

tem

Pas

sive

Sys

tem

Sm

all

Lea

k

Lar

ge

Lea

k

Act

ive

Sys

tem

Pas

sive

Sys

tem

FC

I

Core

Cat

cher

Fai

led F

uel

Tes

ts

Code

Dev

elop

men

t &

Val

idat

ion


41

Rea

ctiv

ity

BD

BA

Hea

t R

emo

val

BD

BA

Coola

nt

Lea

kag

e B

DB

A

Oth

er

BD

BA

Saf

ety

Des

ign,

Anal

ysis

,

Lic

ensi

ng

Ab

norm

al

Cas

es

Qual

ity

Contr

ol

DB

A

BD

BA

Rel

iab

ilit

y

Anal

ysis

Sodiu

m F

ire

Exti

nguis

hin

g

Sys

tem

Sodiu

m L

eak

Det

ecti

on

Sys

tem

SG

Lea

k

Pro

tect

ion

Sys

tem

Saf

ety

Sys

tem

s

Lev

el 3

Lev

el 4

Lev

el 6

Lev

el 7

Lev

el 8

Lev

el 5

Lev

el 9

Saf

ety

Anal

ysis

Pro

bab

ilis

tic

Saf

ety

Ass

essm

ent

Pro

tect

ion

Sys

tem

s

Loca

lisi

ng

Sys

tem

s

Supp

ly

Sys

tem

s

Shutd

ow

n

Sys

tem

D

HR

S

Sei

smic

P

rote

ctio

n

Eq

uip

men

t

Ele

ctri

city

S

upp

ly S

yst

em

Wat

erS

upp

ly S

yst

emO

ther

S

upp

ly S

yst

ems

Sodiu

m&

NaK

Lea

d

LB

C

Gas

Saf

ety

Sta

ndar

ds

Wat

er F

inal

Hea

t S

ink

Air

Fin

al H

eat

Sin

k

Ter

tiar

y C

ircu

it

Sys

tem

Ind

epen

den

t

Sys

tem

DR

CS

ICC

S

RV

CS

SG

Lea

k

Pro

tect

ion

Sys

tem

SG

Lea

k

Pro

tect

ion

Sys

tem

Act

ive

Sys

tem

Pas

sive

Sys

tem

Sm

all

Lea

k

Lar

ge

Lea

k

Act

ive

Sys

tem

Pas

sive

Sys

tem

Sei

smic

Anal

ysis

Core

Cat

cher


42

Saf

ety

Man

ufa

cturi

ng&

Const

ruct

ion

Sys

tem

Eq

uip

men

t Q

ual

ity

Contr

ol

Lev

el 3

Lev

el 4

Lev

el 6

Lev

el 7

Lev

el 8

Lev

el 5

Lev

el 9

Saf

ety

Sta

ndar

ds

Sodiu

m F

ire

Exti

nguis

hin

g

Sys

tem

Sodiu

m L

eak

Det

ecti

on

Sys

tem

SG

Lea

k

Pro

tect

ion

Sys

tem

Pro

tect

ion

Sys

tem

s

Loca

lisi

ng

Sys

tem

s

Supp

ly

Sys

tem

s

Shutd

ow

n

Sys

tem

D

HR

S

Sei

smic

P

rote

ctio

n

Eq

uip

men

t

Ele

ctri

city

S

upp

ly S

yst

em

Wat

erS

upp

ly S

yst

emO

ther

Supp

ly S

yst

ems

Sodiu

m&

NaK

Lea

d

LB

C

Gas

Wat

er F

inal

Hea

t S

ink

Air

Fin

al H

eat

Sin

k

Ter

tiar

y C

ircu

it

Sys

tem

Ind

epen

den

t

Sys

tem

DR

CS

ICC

S

RV

CS

SG

Lea

k

Pro

tect

ion

Sys

tem

SG

Lea

k

Pro

tect

ion

Sys

tem

Act

ive

Sys

tem

Pas

sive

Sys

tem

Sm

all

Lea

k

Lar

ge

Lea

k

Act

ive

Sys

tem

Pas

sive

Sys

tem


43

Level 5

Level 3

Level 4

Branch 4-5-1 Branch 4-5-2 Branch 4-5-3 Branch 4-5-4

Safety

Operation

Startup Tests Low Power

Commissioning Full Power Operation

ISI&R

Safety

Standards


44

Sodiu

m F

ire

Exti

nguis

hin

g

Sys

tem

Sodiu

m L

eak

Det

ecti

on

Sys

tem

SG

Lea

k

Pro

tect

ion

Sys

tem

Saf

ety

Sys

tem

s

Lev

el 5

Lev

el 7

Lev

el 8

Lev

el 9

Lev

el 6

Lev

el 1

0

Pro

tect

ion

Sys

tem

s

Loca

lisi

ng

Sys

tem

s

Supp

ly

Sys

tem

s

Shutd

ow

n

Sys

tem

D

HR

S

Sei

smic

P

rote

ctio

n

Eq

uip

men

t

Ele

ctri

city

S

upp

ly S

yst

emW

ater

Supp

ly S

yst

emO

ther

Supp

ly S

yst

ems

Sodiu

m &

NaK

Lea

d

LB

C

Gas

Wat

er F

inal

Hea

t S

ink

Air

Fin

al H

eat

Sin

k

Ter

tiar

y C

ircu

it

Sys

tem

Ind

epen

den

t

Sys

tem

DR

CS

ICC

S

RV

CS

SG

Lea

k

Pro

tect

ion

Sys

tem

SG

Lea

k

Pro

tect

ion

Sys

tem

Act

ive

Sys

tem

Pas

sive

Sys

tem

Sm

all

Lea

k

Lar

ge

Lea

k

Act

ive

Sys

tem

Pas

sive

Sys

tem

Sta

rtup

Tes

ts

Ab

norm

al&

Em

erg

ency

Op

erat

ion


45

Sodiu

m F

ire

Exti

nguis

hin

g

Sys

tem

Sodiu

m L

eak

Det

ecti

on

Sys

tem

SG

Lea

k

Pro

tect

ion

Sys

tem

Saf

ety

Sys

tem

s

Lev

el 5

Lev

el 7

Lev

el 8

Lev

el 9

Lev

el 6

Lev

el 1

0

Pro

tect

ion

Sys

tem

s

Loca

lisi

ng

Sys

tem

s

Supp

ly

Sys

tem

s

Shutd

ow

n

Sys

tem

D

HR

S

Sei

smic

P

rote

ctio

n

Eq

uip

men

t

Ele

ctri

city

S

upp

ly S

yst

em

Wat

erS

upp

ly S

yst

emO

ther

Supp

ly S

yst

ems

Sodiu

m &

NaK

Lea

d

LB

C

Gas

Wat

er F

inal

Hea

t S

ink

Air

Fin

al H

eat

Sin

k

Ter

tiar

y C

ircu

it

Sys

tem

Ind

epen

den

t

Sys

tem

DR

CS

ICC

S

RV

CS

SG

Lea

k

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tect

ion

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tem

SG

Lea

k

Pro

tect

ion

Sys

tem

Act

ive

Sys

tem

Pas

sive

Sys

tem

Sm

all

Lea

k

Lar

ge

Lea

k

Act

ive

Sys

tem

Pas

sive

Sys

tem

Low

Pow

er C

om

mis

sionin

g

Ab

norm

al&

Em

erg

ency

Op

erat

ion


46

Sodiu

m F

ire

Exti

nguis

hin

g

Sys

tem

Sodiu

m L

eak

Det

ecti

on

Sys

tem

SG

Lea

k

Pro

tect

ion

Sys

tem

Saf

ety

Sys

tem

s

Lev

el 5

Lev

el 7

Lev

el 8

Lev

el 9

Lev

el 6

Lev

el 1

0

Pro

tect

ion

Sys

tem

s

Loca

lisi

ng

Sys

tem

s

Supp

ly

Sys

tem

s

Shutd

ow

n

Sys

tem

D

HR

S

Sei

smic

P

rote

ctio

n

Eq

uip

men

t

Ele

ctri

city

S

upp

ly S

yst

em

Wat

erS

upp

ly S

yst

emO

ther

Supp

ly S

yst

ems

Sodiu

m &

NaK

Lea

d

LB

C

Gas

Wat

er F

inal

Hea

t S

ink

Air

Fin

al H

eat

Sin

k

Ter

tiar

y C

ircu

it

Sys

tem

Ind

epen

den

t

Sys

tem

DR

CS

ICC

S

RV

CS

SG

Lea

k

Pro

tect

ion

Sys

tem

SG

Lea

k

Pro

tect

ion

Sys

tem

Act

ive

Sys

tem

Pas

sive

Sys

tem

Sm

all

Lea

k

Lar

ge

Lea

k

Act

ive

Sys

tem

Pas

sive

Sys

tem

Full

Pow

er

Op

erat

ion

Ab

norm

al&

Em

erg

ency

Op

erat

ion


47

Sodiu

m F

ire

Exti

nguis

hin

g

Sys

tem

Sodiu

m L

eak

Det

ecti

on

Sys

tem

SG

Lea

k

Pro

tect

ion

Sys

tem

Saf

ety

Sys

tem

s

Lev

el 5

Lev

el 7

Lev

el 8

Lev

el 9

Lev

el 6

Lev

el 1

0

Pro

tect

ion

Sys

tem

s

Loca

lisi

ng

Sys

tem

s

Supp

ly

Sys

tem

s

Shutd

ow

n

Sys

tem

D

HR

S

Sei

smic

P

rote

ctio

n

Eq

uip

men

t

Ele

ctri

city

S

upp

ly S

yst

emW

ater

Supp

ly S

yst

emO

ther

Supp

ly S

yst

ems

Sodiu

m &

NaK

Lea

d

LB

C

Gas

Wat

er F

inal

Hea

t S

ink

Air

Fin

al H

eat

Sin

k

Ter

tiar

y C

ircu

it

Sys

tem

Ind

epen

den

t

Sys

tem

DR

CS

ICC

S

RV

CS

SG

Lea

k

Pro

tect

ion

Sys

tem

SG

Lea

k

Pro

tect

ion

Sys

tem

Act

ive

Sys

tem

Pas

sive

Sys

tem

Sm

all

Lea

k

Lar

ge

Lea

k

Act

ive

Sys

tem

Pas

sive

Sys

tem

ISI

& R

Ab

norm

al&

Em

erg

ency

Op

erat

ion


48

Saf

ety

Dec

om

mis

sionin

g

Ab

norm

al

Cas

es

Qual

ity

Contr

ol

D

BA

B

DB

A

Sodiu

m F

ire

Exti

nguis

hin

g

Sys

tem

Sodiu

m L

eak

Det

ecti

on

Sys

tem

Saf

ety

Sys

tem

s

Lev

el 3

Lev

el 4

Lev

el 6

Lev

el 7

Lev

el 8

Lev

el 5

Lev

el 9

Saf

ety

Anal

ysis

Pro

tect

ion

Sys

tem

s

Loca

lisi

ng

Sys

tem

s

Shutd

ow

n

Sys

tem

Sei

smic

P

rote

ctio

n

Eq

uip

men

t S

odiu

m &

NaK

Lea

d

LB

C

Gas

Saf

ety

Sta

ndar

ds

Act

ive

Sys

tem

Pas

sive

Sys

tem


49

Basic Principles

Systems &

Equipment

Design Philosophy Regulatory

Documents

NPP Concept

Core & SA

Level 3

Level 4

Level 5

Level 6

System &

Equipment

Concept


50

Sys

tem

s &

Eq

uip

men

t

R &

D

Core

Pri

mar

y C

ircu

it

Ter

tiar

y C

ircu

itN

PP

Sys

tem

s

Fuel

Sub

asse

mb

ly

Fer

tile

Sub

asse

mb

ly

SA

Mec

han

ical

In

tera

ctio

n

Modula

r

Conce

pt

SG

Sec

ondar

y

Pum

p

Oth

er

Com

ponen

ts

Ven

tila

tion

Sys

tem

Cover

Gas

Sys

tem

Hea

ting S

yste

m

Puri

fica

tion

Sys

tem

Dra

inag

e

Sys

tem

Oth

er

Sys

tem

s

Cover

Gas

Sys

tem

Puri

fica

tion

Sys

tem

Dra

inag

e S

yste

m

Oth

er S

yste

ms

In-V

esse

l

Str

uct

ure

s

IHX

Pri

mar

y P

um

p

Ref

uel

ing

Sys

tem

Oth

er

Com

ponen

ts

Fuel

Pin

Fer

tile

Pin

Pool

Conce

pt

Mai

n

Com

ponen

ts

Auxil

iary

Sys

tem

s

Cover

Gas

Sys

tem

Puri

fica

tion

Sys

tem

Dra

inag

e S

yste

m

Oth

er S

yste

ms

In-V

esse

l

Str

uct

ure

s

IHX

Pri

mar

y P

um

p

Ref

uel

ing

Sys

tem

Oth

er

Com

ponen

ts

Cover

Gas

Sys

tem

Puri

fica

tion

Sys

tem

Dra

inag

e S

yste

m

Oth

er S

yste

ms

In-V

esse

l

Str

uct

ure

s

IHX

Pri

mar

y P

um

p

Ref

uel

ing

Sys

tem

Oth

er

Com

ponen

ts

Cover

Gas

Sys

tem

Puri

fica

tion

Sys

tem

Dra

inag

e S

yste

m

Oth

er S

yste

ms

In-V

esse

l

Str

uct

ure

s

IHX

Pri

mar

y P

um

p

Ref

uel

ing

Sys

tem

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er

Com

ponen

ts

Loop

Conce

pt

Mai

n

Com

ponen

ts

Auxil

iary

Sys

tem

s

Mult

i-V

esse

l

Conce

pt

Mai

n

Com

ponen

ts

Auxil

iary

Sys

tem

s

Mai

n

Com

ponen

ts

Auxil

iary

Sys

tem

s

Sec

ondar

y

Cir

cuit

Mai

n

Com

ponen

ts

Auxil

iary

Sys

tem

s

Lev

el 3

Lev

el 4

Lev

el 5

Lev

el 6

Lev

el 7

Cold

Tra

p

1 c

ircu

it

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Tra

p

1 c

ircu

it

Cold

Tra

p

1 c

ircu

it

Cold

Tra

p

1 c

ircu

it

Cold

Tra

p

2 c

ircu

it

Lev

el 8

Cae

sium

Tra

pC

aesi

um

Tra

pC

aesi

um

Tra

pC

aesi

um

Tra

p

Fai

led S

A

Det

ecti

on

Sys

tem

Code

Dev

elop

men

t &

Val

idat

ion

Code

Dev

elop

men

t &

Val

idat

ion

Code

Dev

elop

men

t &

Val

idat

ion

Code

Dev

elop

men

t &

Val

idat

ion

Code

Dev

elop

men

t &

Val

idat

ion


51

Init

ial

Core

Des

ign

Fai

led S

A

Det

ecti

on

Sys

tem

Ter

tiar

y

Cir

cuit

Core

Core

Modif

icat

ions

Lev

el 3

Lev

el 4

Lev

el 5

Lev

el 6

Lev

el 7

NP

P

Sys

tem

s

Ven

tila

tion

Sys

tem

Hea

ting

Sys

tem

Sp

ecia

l

Ven

tila

tion

Conven

tional

Ven

tila

tion

Lev

el 8

SG

Sec

ondar

y

Pum

p

Oth

er

Com

ponen

ts

Cover

Gas

Sys

tem

Puri

fica

tion

Sys

tem

Dra

inag

eS

yste

m

Oth

er

Sys

tem

s

Sec

ondar

y

Cir

cuit

Mai

n

Com

ponen

ts

Auxil

iary

Sys

tem

s

Cold

Tra

p

2 c

ircu

it

Pri

mar

y

Cir

cuit

Modula

r

Conce

pt

Cover

Gas

Sys

tem

Puri

fica

tion

Sys

tem

Dra

inag

e

Sys

tem

Oth

er S

yste

ms

In-V

esse

l

Str

uct

ure

s

IHX

Pri

mar

y P

um

p

Ref

uel

ing

Sys

tem

Oth

er

Com

ponen

ts

Pool

Conce

pt

Mai

n

Com

ponen

ts

Auxil

iary

Sys

tem

s

Cover

Gas

Sys

tem

Puri

fica

tion

Sys

tem

Dra

inag

e

Sys

tem

Oth

er S

yste

ms

In-V

esse

l

Str

uct

ure

s

IHX

Pri

mar

y P

um

p

Ref

uel

ing

Sys

tem

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er

Com

ponen

ts

Cover

Gas

Sys

tem

Puri

fica

tion

Sys

tem

Dra

inag

e

Sys

tem

Oth

er S

yste

ms

In-V

esse

l

Str

uct

ure

s

IHX

Pri

mar

y P

um

p

Ref

uel

ing

Sys

tem

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er

Com

ponen

ts

Cover

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Sys

tem

Puri

fica

tion

Sys

tem

Dra

inag

e

Sys

tem

Oth

er S

yste

ms

In-V

esse

l

Str

uct

ure

s

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Pri

mar

y P

um

p

Ref

uel

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Sys

tem

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er

Com

ponen

ts

Loop

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pt

Mai

n

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ponen

ts

Auxil

iary

Sys

tem

s

Mult

i-V

esse

l

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pt

Mai

n

Com

ponen

ts

Auxil

iary

Sys

tem

s

Mai

n

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ponen

ts

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iary

Sys

tem

s

Cold

Tra

p

1 c

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it

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Tra

p

1 c

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it

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Tra

p

1 c

ircu

it

Cold

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p

1 c

ircu

it

Cae

sium

Tra

pC

aesi

um

Tra

pC

aesi

um

Tra

pC

aesi

um

Tra

p

Sys

tem

s &

E

quip

men

t

Des

ign,

Anal

ysis

,

Lic

ensi

ng

Fuel

Sub

asse

mb

ly

Fer

tile

S

ub

asse

mb

ly

Fer

tile

P

in

Fuel

Pin

Fuel

Sub

asse

mb

ly

Fer

tile

Sub

asse

mb

ly

Fer

tile

Pin

Fuel

Pin


52

Lev

el 3

Lev

el 4

Lev

el 6

Lev

el 7

Lev

el 8

Sys

tem

s&

Eq

uip

men

t

Man

ufa

cturi

ng

&

Const

ruct

ion

Core

Pri

mar

y C

ircu

itT

erti

ary

Cir

cuit

NP

P

Sys

tem

s

Fuel

Sub

asse

mb

ly

Fer

tile

Sub

asse

mb

ly

Fai

led S

A

Det

ecti

on

Sys

tem

Modula

r

Conce

pt

SG

Sec

ondar

y

Pum

p

Oth

er

Com

ponen

ts

Ven

tila

tion

Sys

tem

Cover

Gas

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tem

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ting

Sys

tem

Puri

fica

tion

Sys

tem

Dra

inag

e

Sys

tem

Oth

er

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tem

s

Cover

Gas

Sys

tem

Puri

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tion

Sys

tem

Dra

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e

Sys

tem

Oth

er S

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ms

In-V

esse

l

Str

uct

ure

s

IHX

Pri

mar

y P

um

p

Ref

uel

ing

Sys

tem

Oth

er

Com

ponen

ts

Fuel

Pin

Fer

tile

Pin

Pool

Conce

pt

Mai

n

Com

ponen

ts

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iary

Sys

tem

s

Cover

Gas

Sys

tem

Puri

fica

tion

Sys

tem

Dra

inag

e

Sys

tem

Oth

er S

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ms

In-V

esse

l

Str

uct

ure

s

IHX

Pri

mar

y P

um

p

Ref

uel

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Sys

tem

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er

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ts

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Sys

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e

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l

Str

uct

ure

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y P

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Ref

uel

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Sys

tem

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Sys

tem

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tion

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tem

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ms

In-V

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l

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mar

y P

um

p

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Sys

tem

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er

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ponen

ts

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pt

Mai

n

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ts

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iary

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tem

s

Mult

i-V

esse

l

Conce

pt

Mai

n

Com

ponen

ts

Auxil

iary

Sys

tem

s

Mai

n

Com

ponen

ts

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iary

Sys

tem

s

Sec

ondar

y

Cir

cuit

Mai

n

Com

ponen

ts

Auxil

iary

Sys

tem

s

Sp

ecia

l

Ven

tila

tion

Conven

tional

Ven

tila

tion

Sys

tem

& E

quip

men

t

Qual

ity

Contr

ol

Reg

ula

tory

Do

cum

ents

L

evel

5

Cold

Tra

p

1 c

ircu

it

Cold

Tra

p

2 c

ircu

it

Lev

el 9

Cold

Tra

p

1 c

ircu

it

Cold

Tra

p

1 c

ircu

it

Cold

Tra

p

1 c

ircu

it

Cae

sium

Tra

pC

aesi

um

Tra

pC

aesi

um

Tra

pC

aesi

um

Tra

p


53

Level 5

Level 3

Level 4

Branch 5-5-1 Branch 5-5-2 Branch 5-5-3 Branch 5-5-4

Systems &

Equipment

Operation

Startup Tests Low Power

Commissioning Full Power

Operation

ISI & R Regulatory

Documents


54

Lev

el 9

Lev

el 5

Lev

el 6

Lev

el 7

Lev

el 8

Pri

mar

y C

ircu

itN

PP

Sys

tem

s

Modula

r

Conce

pt

Cover

Gas

Sys

tem

Puri

fica

tion

Sys

tem

Dra

inag

e

Sys

tem

Oth

er S

yste

ms

Pri

mar

y P

um

p

Ref

uel

ing

Sys

tem

Oth

er

Com

ponen

ts

Pool

Conce

pt

Mai

n

Com

ponen

ts

Auxil

iary

Sys

tem

s

Cover

Gas

Sys

tem

Puri

fica

tion

Sys

tem

Dra

inag

e

Sys

tem

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er S

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ms

Pri

mar

y P

um

p

Ref

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ing

Sys

tem

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er

Com

ponen

ts

Cover

Gas

Sys

tem

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tion

Sys

tem

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inag

e

Sys

tem

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ms

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mar

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p

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tem

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ts

Cover

Gas

Sys

tem

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tem

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e

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tem

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ts

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pt

Mai

n

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ts

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iary

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tem

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Mult

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l

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pt

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n

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iary

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s

Mai

n

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ts

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iary

Sys

tem

s

Cold

Tra

p

1 c

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it

Sec

ondar

y

Pum

p

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er

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ponen

ts

Cover

Gas

Sys

tem

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fica

tion

Sys

tem

Dra

inag

e

Sys

tem

Oth

er

Sys

tem

s

Sec

ondar

y

Cir

cuit

Mai

n

Com

ponen

ts

Auxil

iary

Sys

tem

s

Cold

Tra

p

2 c

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it

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Tra

p

1 c

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it

Cold

Tra

p

1 c

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it

Cold

Tra

p

1 c

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it

Cae

sium

Tra

pC

aesi

um

Tra

pC

aesi

um

Tra

p

Cae

sium

Tra

p

Sta

rtup

Tes

ts

Ab

norm

al &

E

mer

gen

cy

Op

erat

ion

Fai

led F

uel

Op

erat

ion

Core

Fir

st C

riti

cali

ty

Tes

ts

Ven

tila

tion

Sys

tem

Hea

ting

Sys

tem

Sp

ecia

l

Ven

tila

tion

Conven

tional

Ven

tila

tion


55

Pri

mar

y

Cir

cuit

Ter

tiar

y

Cir

cuit

NP

P

Sys

tem

s

Modula

r

Conce

pt

SG

Sec

ondar

y

Pum

p

Oth

er

Com

ponen

ts

Cover

Gas

Sys

tem

Puri

fica

tion

Sys

tem

Dra

inag

e

Sys

tem

Oth

er

Sys

tem

s

Cover

Gas

Sys

tem

Puri

fica

tion

Sys

tem

Dra

inag

e

Sys

tem

Oth

er S

yste

ms

IHX

Pri

mar

y P

um

p

Oth

er

Com

ponen

ts

Pool

Conce

pt

Mai

n

Com

ponen

ts

Auxil

iary

Sys

tem

s

Cover

Gas

Sys

tem

Puri

fica

tion

Sys

tem

Dra

inag

e

Sys

tem

Oth

er S

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ms

IHX

Pri

mar

y P

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p

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ponen

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Cover

Gas

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tem

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fica

tion

Sys

tem

Dra

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Sys

tem

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ms

IHX

Pri

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p

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ponen

ts

Cover

Gas

Sys

tem

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fica

tion

Sys

tem

Dra

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e

Sys

tem

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er S

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ms

IHX

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mar

y P

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p

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ponen

ts

Loop

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pt

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n

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ponen

ts

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iary

Sys

tem

s

Mult

i-V

esse

l

Conce

pt

Mai

n

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ponen

ts

Auxil

iary

Sys

tem

s

Mai

n

Com

ponen

ts

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iary

Sys

tem

s

Sec

ondar

y

Cir

cuit

Mai

n

Com

ponen

ts

Auxil

iary

Sys

tem

s

Cold

Tra

p

1 c

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it

Cold

Tra

p

2 c

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it

Cold

Tra

p

1 c

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it

Cold

Tra

p

1 c

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it

Cold

Tra

p

1 c

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it

Cae

sium

Tra

pC

aesi

um

Tra

pC

aesi

um

Tra

p

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Tra

p

Low

Pow

er

Com

mis

sionin

g

Ab

norm

al &

E

mer

gen

cy

Op

erat

ion

Fai

led F

uel

Op

erat

ion

Core

Low

Pow

er

Tes

ts

Lev

el 9

Lev

el 5

Lev

el 6

Lev

el 7

Lev

el 8


56

Core

Full

Pow

er

Tes

ts

Burn

up

Tes

ts

Pri

mar

y C

ircu

itT

erti

ary

Cir

cuit

NP

P

Sys

tem

s

Modula

r

Conce

pt

SG

Sec

ondar

y

Pum

p

Oth

er

Com

ponen

ts

Cover

Gas

Sys

tem

Puri

fica

tion

Sys

tem

Dra

inag

e

Sys

tem

Oth

er

Sys

tem

s

Cover

Gas

Sys

tem

Puri

fica

tion

Sys

tem

Dra

inag

e

Sys

tem

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er S

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ms

IHX

Pri

mar

y P

um

p

Ref

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ing

Sys

tem

Oth

er

Com

ponen

ts

Pool

Conce

pt

Mai

n

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ponen

ts

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iary

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tem

s

Cover

Gas

Sys

tem

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fica

tion

Sys

tem

Dra

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e

Sys

tem

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ms

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mar

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p

Ref

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tem

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tem

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ms

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p

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tem

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Mult

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Mai

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s

Ven

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tem

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tem

Sp

ecia

l

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tila

tion

Conven

tional

Ven

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Cold

Tra

p

1 c

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it

Cold

Tra

p

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p

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p

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pC

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p

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p

Full

Pow

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per

atio

n

Ab

norm

al &

E

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cy

Op

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ion

Fai

led F

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Op

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ion

Lev

el 9

Lev

el 5

Lev

el 6

Lev

el 7

Lev

el 8


57

Core

Pri

mar

y

Cir

cuit

Ter

tiar

y

Cir

cuit

NP

P

Sys

tem

s

Modula

r

Conce

pt

SG

Sec

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y

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p

Oth

er

Com

ponen

ts

Cover

Gas

Sys

tem

Puri

fica

tion

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tem

Dra

inag

e

Sys

tem

Oth

er

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tem

s

Cover

Gas

Sys

tem

Puri

fica

tion

Sys

tem

Dra

inag

e

Sys

tem

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er S

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ms

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Pri

mar

y P

um

p

Oth

er

Com

ponen

ts

Pool

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pt

Mai

n

Com

ponen

ts

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iary

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tem

s

Cover

Gas

Sys

tem

Puri

fica

tion

Sys

tem

Dra

inag

e

Sys

tem

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ms

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Pri

mar

y P

um

p

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Com

ponen

ts

Cover

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Sys

tem

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fica

tion

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tem

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inag

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tem

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er S

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ms

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Pri

mar

y P

um

p

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er

Com

ponen

ts

Cover

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Sys

tem

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fica

tion

Sys

tem

Dra

inag

e

Sys

tem

Oth

er S

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ms

IHX

Pri

mar

y P

um

p

Oth

er

Com

ponen

ts

Loop

Conce

pt

Mai

n

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ponen

ts

Auxil

iary

Sys

tem

s

Mult

i-V

esse

l

Conce

pt

Mai

n

Com

ponen

ts

Auxil

iary

Sys

tem

s

Mai

n

Com

ponen

ts

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iary

Sys

tem

s

Sec

ondar

y

Cir

cuit

Mai

n

Com

ponen

ts

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iary

Sys

tem

s

Ven

tila

tion

Sys

tem

Hea

ting

Sys

tem

Sp

ecia

l

Ven

tila

tion

Conven

tional

Ven

tila

tion

Cold

Tra

p

1 c

ircu

it

Cold

Tra

p

2 c

ircu

it

Cold

Tra

p

1 c

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it

Cold

Tra

p

1 c

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it

Cold

Tra

p

1 c

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it

Cae

sium

Tra

pC

aesi

um

Tra

pC

aesi

um

Tra

p

Cae

sium

Tra

p

ISI

& R

Ab

norm

al &

E

mer

gen

cy

Op

erat

ion

Lev

el 9

Lev

el 5

Lev

el 6

Lev

el 7

Lev

el 8


58

67

Sys

tem

s &

E

quip

men

t

Dec

om

mis

sionin

g

Core

Pri

mar

y

Cir

cuit

N

PP

Sys

tem

s

Ab

norm

al&

E

mer

gen

cy

Op

erat

ion

Core

Unlo

adin

g

SA

Cle

anin

g

SA

Insp

ecti

on

Modula

r

Conce

pt

SG

Oth

er

Com

ponen

ts

Conven

tional

Ven

tila

tion

Puri

fica

tion

Sys

tem

Sp

ecia

l

Ven

tila

tion

Oth

er

Sys

tem

s

Puri

fica

tion

Sys

tem

Oth

er S

yste

ms

Rea

ctor

Ves

sel

In-V

esse

l

Str

uct

ure

s

Pip

ings

Oth

er

Com

ponen

ts

Core

Uti

liza

tion

Pool

Conce

pt

Loop

Conce

pt

Mult

i-V

esse

l

Conce

pt

Sec

ondar

y

Cir

cuit

Mai

n

Com

ponen

ts

Auxil

iary

Sys

tem

s

Cold

Tra

p

1 c

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it

Cold

Tra

p

2 c

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it

Lev

el 3

Lev

el 4

Lev

el 5

Lev

el 7

Lev

el 8

Lev

el 9

Cae

sium

Tra

p

SR

W

Com

ponen

t

Uti

liza

tion

Mai

n

Com

ponen

ts

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iary

Sys

tem

s

Surf

ace

Dec

onta

min

atio

n

Mai

n

Com

ponen

ts

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iary

Sys

tem

s

LR

W

Com

ponen

t

Uti

liza

tion

Com

ponen

t

Uti

liza

tion

A

A

A

A

Rep

roce

ssin

g

Tec

hnolo

gy

Rep

roce

ssin

g

Fac

ilit

y

LR

W S

tora

ge

Rep

roce

ssin

g

Tec

hnolo

gy

Rep

roce

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g

Fac

ilit

y

SR

W S

tora

ge

Hea

ting

Sys

tem

Ven

tila

tion

Sys

tem

Lev

el 6


59

Control &

Basic Principles

Level 3

Level 4

Level 5 Control

Concept

Regulatory

Documents

Monitoring


Level 6

Code Development &

Validation

NPP Control

System

Reactor Control

System

Level 3

Level 5

Level 4

Control & Monitoring

R & D

Neutronic Control

System

Thermal Hydraulic

Control System

Failed Fuel Detection

System

Temperature

Control

Flowrate

Control

Level 7

Coolant Level Control

System

Thermal Hydraulic

Control System

Pump

Control System

Coolant Purification

Control System

Hydrogen Detection

System

Temperature

Control

Flowrate

Control

Pressure

Control

Seismic

Control System

Radioactivity Control

System

Auxiliary

Control Systems

Coolant Boiling

Control

Simulator

System


60

Simulator

System

NPP Control

System

Reactor Control System


Design, Analysis,

Licensing

Neutronic Control

System

Thermal Hydraulic

Control System

Failed Fuel Detection

System

Temperature

Control

Flowrate

Control

Level 3

Level 6

Level 5

Level 4

Level 7

Coolant Level Control

System

Thermal Hydraulic

Control System

Pump

Control System


Control System

Hydrogen Detection

System

Temperature

Control

Flowrate

Control

Pressure

Control

Seismic

Control System

Radioactivity Control

System

Auxiliary

Control Systems

Equipment &

Personnel

Control

Technique

Control Room Design

Reserved Control

Room Design

Detectors

Man-Machine Interface

Auxiliary Equipment Coolant Boiling

Control


61

Level 3

Level 7

Level 6

Level 4

Level 8

Level 5

NPP Control

System

Reactor Control

System

Control &

Monitoring

Manufacturing &

Construction

Neutronic Control

System

Thermal

Hydraulic Control

Failed Fuel

Detection System

Temperature

Control

Flowrate

Control

Coolant Level

Control System

Thermal

Hydraulic Control

Pump

Control System

Coolant

Purification

Hydrogen

Detection System

Temperature

Control

Flowrate

Control

Pressure

Control

Seismic

Control System

Radioactivity

Control System

Auxiliary Control

Systems

Regulatory

DocumentsSystem &

Equipment

Equipment

Detectors

Control Room

Equipment

Reserved Control

Room Equipment

Auxiliary

Equipment

Coolant Boiling

Control


62

Simulator

System NPP Control

System

Reactor Control

System

Level 3

Level 6

Level 5

Level 4


Operation

Neutronic Control

System

Thermal Hydraulic

Control System

Failed Fuel

Detection System

Temperature

Control

Flowrate

Control Level 7

Coolant Level

Control System

Thermal Hydraulic

Control System

Pump

Control System


Control System

Hydrogen Detection

System

Temperature

Control

Flowrate

Control

Pressure

Control

Seismic

Control System

Radioactivity

Control System

Auxiliary Control

Systems

Abnormal &

Emergency Cases

Abnormal &

Emergency Cases

Equipment &

Personnel

Common System

Faults

Personnel

Errors

Coolant Boiling

Control


63

Level 6

NPP Control

System

Reactor Control

System

Level 3

Level 5

Level 4


Decommissioning

Thermal Hydraulic

Control System

Failed Fuel

Detection System

Thermal Hydraulic

Control System

Coolant

Purification Control

Seismic

Control System

Radioactivity

Control System

Auxiliary Control

Systems

Equipment &

Personnel

Equipment

Faults

Personnel

Errors


External Impact

Internal Impact

Level 3

Level 8

Level 6

Level 4

Ecology &

Environment

Basic Principles

Fuel Aspects

Coolant Aspects Level 7

Seismic Impact

Analysis

Industrial Impact

Analysis

Climate Impact

Analysis

Regulatory

Documents

Site Option Level 5

Sodium & NaK

Lead

LBC

Gas

Other

Coolants


64

External Impact

Internal Impact

Level 3

Level 7

Level 4

Ecology &

Environment

R & D

Fuel Aspects

Coolant Aspects Level 6

Seismic Impact

Analysis

Industrial Impact

Analysis

Climate Impact

Analysis

Level 5

Sodium & NaK

Lead

LBC

Gas

Other

Coolants

Code Development &

Validation


Plant Impact on

Personnel

Site Environmental

Impact

Level 3

Level 4

Ecology &

Environment

Design, Analysis,

Licensing

Level 6

Seismic Impact

Analysis

Industrial Impact

Analysis

Climate Impact

Analysis

Level 5 Plant Impact on

Environment


65

Ecology &

Environment

Operation

Level 3

Level 4

Level 5 Site Environment

Monitoring Personnel

Monitoring

SRW

LRW

Level 6 Normal

OperationIncidents &

Accidents

Normal

OperationIncidents &

Accidents

SRW

LRW

Level 7


Personnel

Monitoring

Decommissioning

Strategy

Level 3

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Ecology &

Environment

Decommissioning

Level 6

Basic

Principles

Coolant

Reprocessing Ecology

Component

Reprocessing Ecology

Level 5 Site Environment

Monitoring

Road Map

External Impact

Level 7

SRW

LRW


66

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70

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Codes

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Codes

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Basic Principles

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R & D

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Level 4

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Studies

NPP

Economics

Fuel Cycle

Economics Level 6

Photos

Movies

NPP Decommissioning

Code Development

& Validation

Economics


71

History &

Other Aspects

Design, Analysis,

Licensing

Level 3

Level 4

Level 5

Memoirs Economical

Aspects

Economical

Parameters

Comparative

Estimates

Level 6


History &

Other Aspects

Manufacturing &

Construction

Level 3

Level 4

Level 5

Memoirs Economical

Parameters

Photos

Movies


History &

Other Aspects

Operation

Level 3

Level 4

Level 5

Memoirs Economical

Parameters

Photos

Movies


72

History &

Other Aspects

Decommissioning

Level 3

Level 4

Level 5

Memoirs Economical

Aspects

Economical

Studies

Economical

Parameters

Level 6

Photos

Movies


73

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REFERENCES

[1] INTERNATIONAL ATOMIC ENERGY AGENCY, Knowledge Management for Nuclear Industry Operating Organizations, IAEA-TECDOC-1510, IAEA, Vienna (2006).

[2] BAQUE, F., “French knowledge preservation on sodium fast reactors: Feedback experience of the MADONA encyclopaedia project”, paper presented at IAEA Technical Committee Mtg on Analyses of and Lessons Learned from the Operational Experience with Fast Reactor Equipment and Systems, Obninsk, 2005.

[3] INTERNATIONAL ATOMIC ENERGY AGENCY, Operational and Decommissioning Experience with Fast Reactors, IAEA-TECDOC-1405, IAEA, Vienna (2004).

[4] AOYAMA, T., “JOYO MK-II core characteristics database”, paper presented at IAEA Technical Committee Mtg on Preservation of Fast Reactor Physics Knowledge, Daejeon, 2003.

[5] MOCHIZUKI, H., NAGATA, T., “Knowledge preservation programme for sodium-cooled fast reactors in JNC”, paper presented at IAEA Technical Committee Mtg on Analyses of and Lessons Learned from the Operational Experience with Fast Reactor Equipment and Systems, Obninsk, 2005.

[6] SMITH, P.J., “PFR operational experience and knowledge base”, paper presented at IAEA Technical Committee Mtg on Analyses of and Lessons Learned from the Operational Experience with Fast Reactor Equipment and Systems, Obninsk, 2005.

[7] PROJECT FOCUS: KNK-II REACTOR, KARLSRUHE, GERMANY, Knowledge Base Full Text, IAEA, Vienna (2004) CD-ROM.

[8] BEDNYAKOV, S.M., “Experimental database development status for BFS type zero power fast critical facilities”, paper presented at IAEA Technical Committee Mtg on Analyses of and Lessons Learned from the Operational Experience with Fast Reactor Equipment and Systems”, Obninsk, 2005.

75

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ABBREVIATIONS

AHX Air heat exchanger

BDBA Beyond design basis accident

CDA Core disruption accident

DBA Design basis accident

DHRS Decay heat removal system

DRCS Direct reactor cooling system

FBR Fast breeder reactor

FC Fuel cycle

FCI Fuel–coolant interaction

FR Fast reactor

FRKPS Fast reactor knowledge preservation system

IC Information card

ICCS Intermediate circuit cooling system

IHX Intermediate heat-exchanger

INIS International nuclear information system

ISI & R In-service inspection & repair

LBC Lead–bismuth coolant

LRW Liquid radioactive wastes

MA Minor actinide

MCP Main circulating pump

RVCS Reactor vessel cooling system

SA Subassembly

SFR Sodium cooled fast reactor

SG Steam generator

SRW Solid radioactive wastes

USTS Universal stage topic structure

77

.

CONTRIBUTORS TO DRAFTING AND REVIEW

Ashurko, Yu.M. Institute for Physics and Power Engineering, Russian Federation

Balanda, V.I. International Atomic Energy Agency

Kosilov, A.N. International Atomic Energy Agency

LeSage, L.G. Consultant, United States of America

Poplavskiy, V.M. Institute for Physics and Power Engineering, Russian Federation

Stanculescu, A. International Atomic Energy Agency

Walters, L.C. Consultant, United States of America

Yanev, Y.L. International Atomic Energy Agency

Technical Meetings

Vienna, Austria: 8–10 December 2004, 13–17 February 2006

79

6.06mm

IAEA Nuclear Energy Series No. NP-T-6.3Fast Reactor Know

ledge Preservation System: Taxonom

y and Basic Requirements

INTERNATIONAL ATOMIC ENERGY AGENCYVIENNA

ISBN 978–92–0–100708–7ISSN 1995–7807

IAEA Nuclear Energy Series

Technical Reports

Fast Reactor Knowledge Preservation System: Taxonomy and Basic Requirements

No. NG-T-6.3

08-04321_P1320_covI-IV.indd 1 2008-11-19 14:24:04