The qualification processes of simulation tools

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The qualification processes of simulation tools,components and systems within the framework of the

astrid project - description and examplesG. Gaillard-Groleas, M.-S. Chenaud, L. Cachon, T. Lambert, A. Mourgues,

Benoît Perrin, C. Bois

To cite this version:G. Gaillard-Groleas, M.-S. Chenaud, L. Cachon, T. Lambert, A. Mourgues, et al.. The qualificationprocesses of simulation tools, components and systems within the framework of the astrid project -description and examples. ICAPP, Apr 2017, Fukui And Kyoto, Japan. �cea-02435089�

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Proceedings of ICAPP 2017 April 24-28, 2017 - Fukui and Kyoto (Japan)

THE QUALIFICATION PROCESSES OF SIMULATION TOOLS, CO MPONENTS AND SYSTEMS WITHIN THE FRAMEWORK OF THE ASTRID PROJECT – DESCRIPTION A ND EXAMPLES

Geneviève GAILLARD-GROLEAS1*, Marie-Sophie CHENAUD1, Lionel CACHON1, Thierry LAMBERT1,

Alejandro MOURGUES², Benoit PERRIN2, Claude BOIS2

1 : CEA - Commissariat à l’Énergie Atomique, CEA/CADARACHE, 13108 St Paul Lez Durance, France.

2 : AREVA NP, 10 Rue Juliette Récamier 69456 Lyon Cedex, France.

*Contact author: email: [email protected]

ASTRID is the Advanced Sodium Technological Reactor for Industrial Demonstration which is intended to be a Generation IV prototype reactor, with substantial strong improvements in safety and operability. In order to meet the objectives of the 4th generation reactors and comply with the related specifications, the ASTRID project integrates innovative options.

From the beginning, the project took into account the qualification actions related to these choices and initiated the qualification program of the ASTRID Sodium Fast Reactor. The objectives were to collect needs expressed by different Technological Working Groups involved in ASTRID and to organize then the further treatment of the needs. A risk evaluation was also performed through an evaluation of the maturity level of the technical options using a Technological Readiness Level process (TRL ranking table).

The objective at the current stage of the project is to pursue this process and to supplement the approach by extending it to the entire ASTRID breakdown product structure in order to take into account the interfaces and the integration of the elementary systems. This paper presents the technical qualification method selected to homogenize the approach in the different fields of the ASTRID project.

The simulation tools which are very important to obtain confidence in the feasibility of the proposed innovations and to support the safety files must also follow a qualification process. This process, similar to that related to equipments and systems, is described.

Some examples are given to underline the importance of the different mock-ups used during the qualification processes.

I. INTRODUCTION The ASTRID reactor is a technological demonstrator

designed by the CEA together with its industrial partners, subjected to a very high level of requirements.

Innovative options have been introduced in the design to enhance safety and to take into account the lessons learnt from the Fukushima accident. These options enhance safety, improve reliability and operability and make the Generation IV SFR an attractive option for electricity production and fuel cycle management.

Consequently, these technological options combined with the new safety features are leading to new needs in terms of qualification, demonstration of the relevance of the proposed safety options, efficiency and robustness of the concepts.

The selection process of the design options and the safety studies of the ASTRID reactor also rely on the use of scientific computing tools, some of which need new functionalities to fully address the needs and particularities of this new reactor. These simulation tools need to be qualified for their use in the ASTRID studies.

Finally, the technological features as well as the simulation tools have to comply with a rigorous approach of qualification in order to meet the requirements of the French Regulation. It also has to comply with the schedule and the different milestones of the project.

This paper is going to describe the qualification process the components and the systems must comply with and the one to be followed by the simulation tools. The links and the similarities between the two qualification processes will be underlined. Some examples will be given to point out the importance of the different mock-ups used in the qualification processes.

II. DESCRIPTION OF THE PROCESSES II.A. Component and system qualification process

In every major and complex project principally

driven by innovation, the perspective of R&D needs and Qualification program is a matter of concern. As a consequence, it is essential to anticipate, as early as possible, these needs and to implement a qualification methodology.


During the Conceptual Design phase (named AVP2

phase, from 2013 till the end of 2015) the evaluation of the qualification program of the ASTRID Sodium Fast Reactor was initiated and a methodology was defined1. It consisted in collecting the exhaustive list of R&D needs and technological demonstration tests to be fulfilled on representative mock-ups before introducing the concept in the prototype. It has also been presented how this compilation of needs was managed, evaluated and prioritized in terms of Project Risk Management by means of a Technological Readiness Level grid (TRL).

In line with the work already accomplished, the implementation of the qualification process is presented. It defines the terminology to be adopted to standardize and facilitate relationships within the project. It also describes the different steps to be followed to perform a system or a component qualification. II.A.1. General Information

The objective at this stage of the project is to deal with the qualification from the design to the development of the product, which is the technological qualification.

The purpose of the qualification is to produce a qualification file, demonstrating that the equipment complies with the required performances and safety options. The qualification process must be coherent with the evolution of the project throughout its progress. The main steps of the qualification process can be represented as a V cycle as shown in figure 1.

These steps are going to be detailed hereafter.

Fig. 1: Main steps of the qualification process - V cycle.

II.A.2. Qualification Plan

An important inventory work must be done on the basis of the ASTRID product breakdown structure and the functional breakdown structure. The goal of this work is to determine which equipment or system must be qualified and what will be the subjects of the qualification (performances, lifetime, production method, sizing…).

It’s important to take into account the interfaces and the integration of the elementary systems. To do so, methodologies of evaluation of the degree of maturity can be used. These methodologies contribute to perform an exhaustive analysis of the notion of qualification. Beyond the Technology Readiness Level (TRL), the Integration Readiness Level (IRL) has been introduced to address some of the limitations associated with the original development of the TRLs2. The IRL is used to evaluate the integration readiness of any two TRL-assessed technologies. The System Readiness Levels (SRL) and the Manufacturing Readiness Levels (MRL) can also be useful in order to evaluate these aspects of the qualification.

The establishment of a strategy is also a key point because experimental tests are expensive. There are three kinds of qualification: • The one based on analysis consists in demonstrating

by a qualitative and/or quantitative reasoning that the product can fulfill his function(s). The method by analysis is often based on considerations of analogy between equipment and involves the use of simulation tools.

• The qualification can of course also be done with tests.

• Finally, the qualification can be a combination of test and analysis.

At the end of this stage, the qualification plan must be provided. This document synthesizes the work done, describes and justifies the strategy chosen to drive the qualification.

II.A.3. Qualification Program

The qualification program puts forward a more precise definition of the tasks identified in the qualification plan. It defines the type of tests which must be made and the associated schedule in collaboration with the concerned facilities. The qualification tests have to demonstrate that the equipment or system can work in its specified environment.

If tests are performed on mock-ups, the proof of transposition of the test to the considered case must be provided. II.A.4. Test Program

The test program can then be detailed. It often implies numerous exchanges with the facilities in which the tests are planned to be realized. It describes more precisely than the qualification program the tests to be done.


II.A.5. Test Preparation and Realization

This phase corresponds to the realization of a mock-up, a prototype, the realization of an experimental device, the modification of a facility…Generally this phase has been launched in parallel to the establishment of the qualification program.

The tests are then performed according to the test protocol developed on the basis of the test program. II.A.6. Test Report

The test report has to supply all the data allowing the interpretation and the exploitation of the tests. It has to meet the requirements of the qualification and test programs. II.A.6. Qualification File

To finish, the qualification file must be provided. This file has to demonstrate that the domain of the performed tests is in adequacy with the required qualification domain. It must demonstrate the qualification of the equipment and /or system with regards to its qualification plan. If it has not been done before and if tests have been performed on mock-ups, it must provide the proof of the transposition of the test to the considered case.

On the basis of the qualification file, the equipment or system can then be considered as qualified. The qualification file establishes the proof of the capacity of the equipment or system. II.B. Simulation Tools Qualification Process

The French Regulation for Basic Nuclear

Installations, issued in 2012, requires the safety demonstration to rely on calculation tools which are qualified for the domains they are used in.

The Qualification level for a calculation tool is the final level which has to be performed after the well-known VVUQ (Verification, Validation and Uncertainties Quantification) process. This level is achieved at the end of a long-term process3 which involves several steps, briefly described hereafter.

Subsequent to the Development, the Verification

step ensures that the resolution of the equations is correct. In other words, it must be ensured that the calculation tool works as expected (correct digital implementation, correct numerical solution).

Then, the Validation of a scientific calculation tool

is the process of assessing its predictive ability of real

phenomena with regard to the use in the targeted field. It aims to achieve the quantification of uncertainties associated with the calculated quantities.

The validation is to ensure that the mathematical model developed for the calculation of physical phenomena has the ability to represent them properly in an identified domain. The validation is led according to the validation plan which must have been established previously and the content of which is represented in figure 2. The validation plan describes the strategy of the validation. The validation phase consists in comparing the results of the simulation tool to experimental data coming from mock-ups and/or reactor operation feedback, as well as to already qualified calculations (benchmarking). This might be called the analysis part of the validation plan.

The ASTRID simulation tools benefit from a vast experimental data base, relying on the feedback from numerous tests, particularly in the PHENIX and SUPERPHENIX reactors. Nevertheless, the innovative design options of ASTRID involve new needs in terms of R&D programs and motivate the development of new test facilities. Considering the considerable cost of these experiments and the need to widen the set of relevant experiments, international collaboration is required. These new testing needs are gathered in the experimental plan which is thus another part of the validation plan.

To be complete the validation plan must also deal with costs, risks and schedule.

Fig. 2: Content of the validation plan. Finally, the Qualification step is the last stage of

the process. The goals of this step are to ensure the validity and the relevance of the obtained results, as well as to demonstrate the quality and the confidence in the provided results. This step must be done by the calculation tool user.

During this step, it must be ensured that the field of use of the tool in the future study is consistent with its validation domain. The tool must be used in the domain where it is supposed to be valid and the proof of this verification must be provided.

checking the ability of the scientific csimulate reactor conditions, must also be provided. This transposition must also include the quantification of the associated uncertainties.

efficient tool to simulation tool application representation nparameters (called A, B, C…) phenomena simulated with the

Fig. 3domains.

justify and demonstrate the compliance to the approach through the formalization of this step in acce

all ASTRID partners in order to such as required by the French Safety Authorities. II.C.

and the simulation tools qualification process follow the same approach and are tightly linked.must be demonstrated that the equipment or the tool can be used with confidence and will fulfill the required performances.

to the qualification plan for equipment or a system. They both describe the strategy chosenqualification.

part of the qualificationsimulation concerned use. The qualificatvalidation built with the realization of experimentation

The transposition to reactor case, which involves checking the ability of the scientific csimulate reactor conditions, must also be provided. This transposition must also include the quantification of the associated uncertainties.

The representation

efficient tool to simulation tool application andrepresentation nparameters (called A, B, C…) phenomena simulated with the

Fig. 3: Representations of validation and application domains.

Every userjustify and demonstrate the compliance to the approach through the formalization of this step in accepting studies dedicated to the safety demonstration

The above described all ASTRID partners in order to such as required by the French Safety Authorities. II.C. Interaction between the

The components and systems qualification process

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pting studies dedicated to the safety demonstration

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pting studies dedicated to the safety demonstration

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such as required by the French Safety Authorities.

two previous processes

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In both cases it must be demonstrated that the equipment or the tool can be used with confidence and will fulfill the required

tool is equivalent to the qualification plan for equipment or a system. They

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processes

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In both cases it must be demonstrated that the equipment or the tool can be used with confidence and will fulfill the required

tool is equivalent to the qualification plan for equipment or a system. They

which will lead to the

n figure 4, the analysis can require the use of a

which has to be qualified for the ion of a tool relies on its

validation built with the realization of experimentation

which can be shared with equipment qualification.

Fig. 4components and systems quali III.

can be simulation tools or can also be useful for both of these needs. the importaqualification processes.

examples which are going to be given are only a part of the qualification process. III.A. III.A.1.

Conversion System (PCS) is leading to an important R&D and design program work which is in related paperscomponents allowing to transfer a total heat power of 1500 MWth between the 4 secondary sodium loops and the 8 gas loops of the power conversion system.

Heat Exchanger (CPHE) modules in a pressuplaying also a header motivations of this design are: (i) the bundle of plates is in compression (this limits the tensile structure), (ii) there is a limitation of constraints due to hyperstat(iii) the pressure drop on the gas side (vessel acting as header), (iv) is allowed for maintenance and inspection, (v) there are twoexchanger building

April 24

which can be shared with equipment qualification.

Fig. 4: Links between simulation tool qualification and components and systems quali III. EXAMPLES

As it has been described before, the experimentation can be performed simulation tools or can also be useful for both of these needs. Some examples are going to be given to underline the importance of the different mockqualification processes.

Of course, as it was described in section II, the examples which are going to be given are only a part of the qualification process. III.A. THE SODIUM GAS III.A.1. Introduction

The study of an ASTRID option with gas Power Conversion System (PCS) is leading to an important R&D and design program work which is in related paperscomponents is the Sodium / Gas Heaallowing to transfer a total heat power of 1500 MWth between the 4 secondary sodium loops and the 8 gas loops of the power conversion system.

The principle of the design is to put Compact Plate Heat Exchanger (CPHE) modules in a pressuplaying also a header motivations of this design are: (i) the bundle of plates is in compression (this limits the tensile structure), (ii) there is a limitation of constraints due to hyperstatism (each module is free to thermal expansion), (iii) the pressure drop on the gas side (vessel acting as header), (iv) is allowed for maintenance and inspection, (v) there are two confinement barriers between exchanger building

April 24-28, 2017

which can be shared with the equipment qualification.

Links between simulation tool qualification and components and systems quali

EXAMPLES

As it has been described before, the experimentation performed for components and systems or for

simulation tools or can also be useful for both of these Some examples are going to be given to underline

nce of the different mockqualification processes.

Of course, as it was described in section II, the examples which are going to be given are only a part of the qualification process.

THE SODIUM GAS

Introduction

The study of an ASTRID option with gas Power Conversion System (PCS) is leading to an important R&D and design program work which is in related papers4,5. In the gas PCS, one of the key

s the Sodium / Gas Heaallowing to transfer a total heat power of 1500 MWth between the 4 secondary sodium loops and the 8 gas loops of the power conversion system.

The principle of the design is to put Compact Plate Heat Exchanger (CPHE) modules in a pressuplaying also a header function (figure motivations of this design are: (i) the bundle of plates is in compression (this limits the tensile structure), (ii) there is a limitation of constraints due to

ism (each module is free to thermal expansion), (iii) the pressure drop on the gas side (vessel acting as header), (iv) is allowed for maintenance and inspection, (v) there are

confinement barriers between exchanger building environment

Proceedings of28, 2017 - Fukui and Kyoto (Japan)

the experimentation required for

Links between simulation tool qualification and components and systems qualification.

As it has been described before, the experimentation for components and systems or for


nce of the different mock-ups used during the

Of course, as it was described in section II, the examples which are going to be given are only a part of

THE SODIUM GAS HEAT EXCHANGER

The study of an ASTRID option with gas Power Conversion System (PCS) is leading to an important R&D and design program work which is extensively

. In the gas PCS, one of the key s the Sodium / Gas Heat Exchanger (SGHE),

allowing to transfer a total heat power of 1500 MWth between the 4 secondary sodium loops and the 8 gas loops of the power conversion system.

The principle of the design is to put Compact Plate Heat Exchanger (CPHE) modules in a pressu

function (figure motivations of this design are: (i) the bundle of plates is in compression (this limits the tensile solistructure), (ii) there is a limitation of constraints due to

ism (each module is free to thermal expansion), (iii) the pressure drop on the gas side (vessel acting as header), (iv) access to the module access is allowed for maintenance and inspection, (v) there are

confinement barriers between the sodiumenvironment (hence a module failure

roceedings of ICAPP 2017Fukui and Kyoto (Japan)

experimentation required for

Links between simulation tool qualification and



ups used during the


HEAT EXCHANGER

The study of an ASTRID option with gas Power Conversion System (PCS) is leading to an important R&D

extensively described . In the gas PCS, one of the key

t Exchanger (SGHE), allowing to transfer a total heat power of 1500 MWth between the 4 secondary sodium loops and the 8 gas loops

The principle of the design is to put Compact Plate Heat Exchanger (CPHE) modules in a pressurized vessel

function (figure 5). The main motivations of this design are: (i) the bundle of plates is in

icitations in the structure), (ii) there is a limitation of constraints due to

ism (each module is free to thermal expansion), (iii) the pressure drop on the gas side is minimized,

the module access is allowed for maintenance and inspection, (v) there are

sodium and the heat (hence a module failure

ICAPP 2017 Fukui and Kyoto (Japan)

experimentation required for

Links between simulation tool qualification and



ups used during the


The study of an ASTRID option with gas Power Conversion System (PCS) is leading to an important R&D

described . In the gas PCS, one of the key

t Exchanger (SGHE), allowing to transfer a total heat power of 1500 MWth between the 4 secondary sodium loops and the 8 gas loops

The principle of the design is to put Compact Plate ed vessel

The main motivations of this design are: (i) the bundle of plates is in

in the structure), (ii) there is a limitation of constraints due to

ism (each module is free to thermal expansion), minimized,

the module access is allowed for maintenance and inspection, (v) there are

heat (hence a module failure

has no impact on the outside), (vi) the Na inventory is low (<8m

based on diffusion bonding by hot isostatic pressing (DBHIP),manufacturing control.

in sodium. A large development and qualification program has bperformances, the design based on narrow channels and its compatibility with Na (draining, cleaning, potential selfdesign, manufacturing process definicharacterization, standards and rules update, …

II

into three main stages:

calculations: this innovations and related patents relative to (i) the design of the component itself, (ii) the manufacturing process, (iii) the exchange pattern allowing an impcompactness, (iv) homogeneous distribution of the modules.strongly rely on theoretical works, partially

experimental validation on a reduced scale with simulating fluid, on representative partsand models proposed and / or developed in the stage.

has no impact on the outside), (vi) the Na inventory is low (<8m3).

The manufacturing process foreseen for the CPHE is based on diffusion bonding by hot isostatic pressing (DBHIP), but with specific procedure allowing 100 % manufacturing control.

No CPHE has never been industrially manufactured in SGHE dimensions (fig.5sodium. A large development and qualification program has been launchperformances, the design based on narrow channels and its compatibility with Na (draining, cleaning, potential self-plugging), thermomechanical analyses to justify the design, manufacturing process definicharacterization, standards and rules update, …

III.A.2. R&D needs in SGHE qualification The development of this SGHE may be broken down

into three main stages:1. Conceptual studies and related justification

calculations: this innovations and related patents relative to (i) the design of the component itself, (ii) the manufacturing process, (iii) the exchange pattern allowing an impcompactness, (iv) homogeneous distribution of the modules.strongly rely on theoretical works, partially

2. Analytical validation

experimental validation on a reduced scale with simulating fluid, on representative partsand models proposed and / or developed in the stage. For the therm

has no impact on the outside), (vi) the Na inventory is low

The manufacturing process foreseen for the CPHE is based on diffusion bonding by hot isostatic pressing (DB

but with specific procedure allowing 100 % manufacturing control.

Fig. 5: SGHE design layout.

CPHE has never been industrially manufactured SGHE dimensions (fig.5

sodium. A large development and qualification program een launched, in order to qualify therm

performances, the design based on narrow channels and its compatibility with Na (draining, cleaning, potential

plugging), thermomechanical analyses to justify the design, manufacturing process definicharacterization, standards and rules update, …

R&D needs in SGHE qualification

The development of this SGHE may be broken down into three main stages:

1. Conceptual studies and related justification calculations: this stage has tinnovations and related patents relative to (i) the design of the component itself, (ii) the manufacturing process, (iii) the exchange pattern allowing an impcompactness, (iv) the Na collectors to ensure a homogeneous distribution of the modules.strongly rely on theoretical works, partially

2. Analytical validationexperimental validation on a reduced scale with simulating fluid, on representative partsand models proposed and / or developed in the

For the thermal hydraulic performance studies, the



but with specific procedure allowing 100 %

: SGHE design layout.

CPHE has never been industrially manufactured SGHE dimensions (fig.5), nor has

sodium. A large development and qualification program , in order to qualify therm


plugging), thermomechanical analyses to justify the design, manufacturing process definicharacterization, standards and rules update, …


The development of this SGHE may be broken down

1. Conceptual studies and related justification has to provide a certain number of

innovations and related patents relative to (i) the design of the component itself, (ii) the manufacturing process, (iii) the exchange pattern allowing an imp

Na collectors to ensure a homogeneous distribution of the modules.strongly rely on theoretical works, partially

2. Analytical validation where the experimental validation on a reduced scale with simulating fluid, on representative partsand models proposed and / or developed in the

hydraulic performance studies, the




: SGHE design layout.

CPHE has never been industrially manufactured , nor has been used with

sodium. A large development and qualification program , in order to qualify thermal hydraulic


plugging), thermomechanical analyses to justify the design, manufacturing process definition, material characterization, standards and rules update, …



1. Conceptual studies and related justification a certain number of

innovations and related patents relative to (i) the design of the component itself, (ii) the manufacturing process, (iii) the exchange pattern allowing an improved thermal

Na collectors to ensure a homogeneous distribution of the modules. These studies strongly rely on theoretical works, partially validated.

objective is the experimental validation on a reduced scale with simulating fluid, on representative parts of the concepts and models proposed and / or developed in the previous



The manufacturing process foreseen for the CPHE is based on diffusion bonding by hot isostatic pressing (DB-


CPHE has never been industrially manufactured been used with

sodium. A large development and qualification program hydraulic


plugging), thermomechanical analyses to justify the tion, material


1. Conceptual studies and related justification a certain number of

innovations and related patents relative to (i) the design of the component itself, (ii) the manufacturing process, (iii)

roved thermal Na collectors to ensure a

These studies

objective is the experimental validation on a reduced scale with

the concepts previous


validations were cachannelNa headers by means of waterat channel scale and scale 1

calculated and measured ch

account in a same test all the significant parameters validated individually in the previous stages. For thatneeded awith ASTRID conditions. In order to limit the risk and associated costs, two qualifications scales were chosen:

•

•

April 24

validations were cachannel5 (test sections implementing Na headers by means of waterat channel scale and scale 1

Fig. 6

calculated and measured ch

3. Global qualification: the objective is to take into account in a same test all the significant parameters validated individually in the previous stages. For thatneeded a functional with ASTRID conditions. In order to limit the risk and associated costs, two qualifications scales were chosen:

• Small scale: tests on elementary Heat eXmock-ups with a heat power capacity These tests are performed(Fig. 7) which is Installation of R&D for Utilization of sodium) platform. The objective hydraulic performances of the current exchange as well as to validate in a preliminary way the thermomechanical band thus the assembly process. These experimental tests have started in 2013 the TRL index from 2 to 4.Complementary to thtests are carried out in parallel on belonging to

• Scale 1: tests on a large tests facility named NSET belonging to the CHEOPS platformThe NSET facility 10 MWth. This facility is designed to bring validation on the operation and performance of exchanger module (scale ASTRID) and components (regrouping a set of modules, conditions. These tests ASTRID Basic design phase. The objective is to qualify in detail the(especially the

April 24-28, 2017

validations were carried out on the scale of the gas(test sections implementing

Na headers by means of waterat channel scale and scale 1 on DANA

6: DANAH facility. Illustrationcalculated and measured channels outlet velocity profiles.

3. Global qualification: the objective is to take into account in a same test all the significant parameters validated individually in the previous stages. For that

functional heat exchanger mockwith ASTRID conditions. In order to limit the risk and associated costs, two qualifications scales were chosen:

cale: tests on elementary Heat eXups with a heat power capacity

These tests are performedwhich is part of

Installation of R&D for Utilization of sodium) . The objective

hydraulic performances of the current exchange as well as to validate in a preliminary way the thermomechanical behavior of the bundle of plates and thus the assembly process. These experimental

started in 2013 the TRL index from 2 to 4.Complementary to these tests, a series of elementary tests are carried out in parallel on

to the PAPIRUS platform

Scale 1: tests on a large tests facility named NSET belonging to the CHEOPS platformThe NSET facility will allow10 MWth. This facility is designed to bring validation on the operation and performance of exchanger module (scale ASTRID) and components (regrouping a set of

, scale 1:12) in . These tests will

ASTRID Basic design phase. The objective is to in detail the

especially the design of the sodium


rried out on the scale of the gas(test sections implementing LASER viewing

Na headers by means of water-to-sodium similarity tests on DANAH facility (fig.6

: DANAH facility. Illustrationannels outlet velocity profiles.

3. Global qualification: the objective is to take into account in a same test all the significant parameters validated individually in the previous stages. For that

exchanger mockwith ASTRID conditions. In order to limit the risk and associated costs, two qualifications scales were chosen:

cale: tests on elementary Heat eXups with a heat power capacity

These tests are performed in the DIADEMO facility part of the PAPIRUS (Park of small

Installation of R&D for Utilization of sodium) . The objective is to validate the therm

hydraulic performances of the current exchange as well as to validate in a preliminary way the

ehavior of the bundle of plates and thus the assembly process. These experimental

started in 2013 and will contribute to raise the TRL index from 2 to 4.

ese tests, a series of elementary tests are carried out in parallel on

the PAPIRUS platform1.

Scale 1: tests on a large tests facility named NSET belonging to the CHEOPS platform

will allow a power 10 MWth. This facility is designed to bring validation on the operation and performance of exchanger module (scale ≈1 of the ones foreseen for ASTRID) and components (regrouping a set of

scale 1:12) in stationarywill be performed during the

ASTRID Basic design phase. The objective is to heat exchange,

design of the sodium


rried out on the scale of the gas-side LASER viewing

sodium similarity tests facility (fig.6).

: DANAH facility. Illustration showing annels outlet velocity profiles.

3. Global qualification: the objective is to take into account in a same test all the significant parameters validated individually in the previous stages. For that, it is

exchanger mock-up working with ASTRID conditions. In order to limit the risk and associated costs, two qualifications scales were chosen:

cale: tests on elementary Heat eXchanger (HX)ups with a heat power capacity up to 40 kW.

n the DIADEMO facility the PAPIRUS (Park of small

Installation of R&D for Utilization of sodium) is to validate the therm

hydraulic performances of the current exchange part, as well as to validate in a preliminary way the


contribute to raise

ese tests, a series of elementary tests are carried out in parallel on other facilities

Scale 1: tests on a large tests facility named NSET (see § III.B.2)

power exchange up to 10 MWth. This facility is designed to bring validation on the operation and performance of the heat

1 of the ones foreseen for ASTRID) and components (regrouping a set of

tionary and transient be performed during the

ASTRID Basic design phase. The objective is to heat exchange, the design

design of the sodium manifold), the


side

LASER viewing), sodium similarity tests

.

annels outlet velocity profiles.

3. Global qualification: the objective is to take into account in a same test all the significant parameters

it is up working

with ASTRID conditions. In order to limit the risk and

(HX) 40 kW.

n the DIADEMO facility the PAPIRUS (Park of small

Installation of R&D for Utilization of sodium) is to validate the thermal

part, as well as to validate in a preliminary way the


contribute to raise

ese tests, a series of elementary facilities

Scale 1: tests on a large tests facility named NSET (see § III.B.2). exchange up to

10 MWth. This facility is designed to bring validation heat

1 of the ones foreseen for ASTRID) and components (regrouping a set of

transient be performed during the

ASTRID Basic design phase. The objective is to design

the

III.B.

hydraulics and vessel.

III.B.1.

thermalproblematics:

certaintaken

manufacturing process with itsstrategy monitoring. These qualification tests will raise the TRL index from 5 to 7.

Fig. 7: Picture of the

(CPHE)

III.B. HYDRAULICS

BEHAVIOR An important

hydraulics and vessel.

III.B.1. Needs

The qualification in the field of hydraulics and thermal hydraulicproblematics:

• Overall problematics: that is to say thermal hydraulicconvection of the primary loop.

• Local problematics which are:o Gas entrainment and v

surfaces.o Gas accumulation within the vessel (in particular

in the diagrid).o Presence of sodium aerosols in the cover gas

plenum and its influence on heat transfer.o The non

between the gas (and aerosols) and sodium its impact on the upper part of the inner vessel.

o Thermal fatigue of the (ACS) fluctuations.

Some R&D needs

certain thermal hydraulictaken into account

manufacturing process with its and the instrumentation for in

monitoring. These qualification tests will raise the TRL index from 5 to 7.

: Picture of the Compact Plate Heat Exchanger

(CPHE) and DIADEMO facility.

HYDRAULICS and BEHAVIOR OF THE PRIMARY CIRCUIT

An important subject in Sodium Fast Reactors is the hydraulics and Thermal Hydraulic

Needs Identification

qualification in the field of hydraulics and hydraulics must deal with the following

Overall problematics: that is to say thermal ydraulics of the primary circuit as well as

convection of the primary loop.problematics which are:

as entrainment and vsurfaces. Gas accumulation within the vessel (in particular in the diagrid). Presence of sodium aerosols in the cover gas plenum and its influence on heat transfer.The non-permanent position of the interface between the gas (and aerosols) and sodium its impact on the upper part of the inner vessel.

hermal fatigue of the (ACS) due to core outlet temperature fluctuations.

Some R&D needs concerning the validation ofhermal hydraulics

into account.

manufacturing process with its manufacturing control instrumentation for in

monitoring. These qualification tests will raise the

Compact Plate Heat Exchanger

and DIADEMO facility.

and THERMALOF THE PRIMARY CIRCUIT

in Sodium Fast Reactors is the ydraulics (TH)

Identification

qualification in the field of hydraulics and must deal with the following

Overall problematics: that is to say thermal s of the primary circuit as well as

convection of the primary loop. problematics which are:

as entrainment and vortex creation on f

Gas accumulation within the vessel (in particular

Presence of sodium aerosols in the cover gas plenum and its influence on heat transfer.

permanent position of the interface between the gas (and aerosols) and sodium its impact on the upper part of the inner vessel.

hermal fatigue of the Abovedue to core outlet temperature

concerning the validation of computing tools must also be

manufacturing control instrumentation for in-service



and DIADEMO facility.

THERMAL HYDRAULICOF THE PRIMARY CIRCUIT

in Sodium Fast Reactors is the (TH) of the primary


Overall problematics: that is to say thermal s of the primary circuit as well as natural

ortex creation on f


Presence of sodium aerosols in the cover gas plenum and its influence on heat transfer.

permanent position of the interface between the gas (and aerosols) and sodium its impact on the upper part of the inner vessel.

Above Core Structure due to core outlet temperature

concerning the validation ofcomputing tools must also be

manufacturing control service



HYDRAULIC S OF THE PRIMARY CIRCUIT

in Sodium Fast Reactors is the of the primary


Overall problematics: that is to say thermal natural

ortex creation on free


Presence of sodium aerosols in the cover gas

permanent position of the interface between the gas (and aerosols) and sodium and its impact on the upper part of the inner vessel.

Core Structure due to core outlet temperature

concerning the validation of computing tools must also be

components such as IHX They will not be presented in this paper.III.B

database, needed hydraulicMost of them are in water sodium W

where different R&D studies will be performed. GISEH platform simulant fluids (water or air) in support of SFR program. Within it, a new (see fidi

PLATEAU

realized plenum (360°, scale 1/mThe Laser velocimetry the flow distribution.

MICAShot plenum (with possibility to realize transientsvalidate CFD studied are: •

•

April 24

Some additional needs in TH are concerning main components such as IHX They will not be presented in this paper.III.B.2. New experiment

Following the analysis of the available experimental database, it has been established that new experiments are needed in order hydraulics and Most of them are in water sodium are also needed Water environment moc

The GISEHwhere different R&D studies will be performed. GISEH platform simulant fluids (water or air) in support of SFR program. Within it, a new (see figure 8distribution to

The following tests are or will be performed on PLATEAU with different mock

The MICAS

realized (see figure 9plenum (360°, scale 1/m3/h and the range of water temperature is 10 to 60°C.The mock-up Laser velocimetry the flow distribution.

MICAS is used to confirm the overall TH behavior of the hot plenum (with possibility to realize transientsvalidate CFD studied are: • Free surface

free surface immersed components.

• Gas entrainment

April 24-28, 2017

Some additional needs in TH are concerning main components such as IHX (Intermediate Heat eXchanger)They will not be presented in this paper.

New experimental needs

Following the analysis of the available experimental it has been established that new experiments are

in order to achieve and thermal hydraulic

Most of them are in water are also needed.

environment mock-upshe GISEH platform consists of

where different R&D studies will be performed. GISEH platform comprises simulant fluids (water or air) in support of SFR program. Within it, a new multipurpose

gure 8), named PLATEAU enables stribution to mockups.

Fig.8: PLATEAU facility

The following tests are or will be performed on with different mock

MICAS mock-up6

(see figure 9). It represents plenum (360°, scale 1/6). The maximum flowrate is 350

/h and the range of water temperature is 10 to 60°C. is plunged into a water pool

Laser velocimetry in order to get the flow distribution.

used to confirm the overall TH behavior of the hot plenum (with possibility to realize transientsvalidate CFD simulation tools

Free surface deformationfree surface can induce thermal immersed components. Gas entrainment.


Some additional needs in TH are concerning main (Intermediate Heat eXchanger)

They will not be presented in this paper. needs


achieve the qualification of the thermal hydraulics in the primary vessel.

Most of them are in water environment

ups: consists of several

where different R&D studies will be performed. comprises the facilities operating with

simulant fluids (water or air) in support of SFR program. multipurpose facility, today

named PLATEAU enables

: PLATEAU facility

The following tests are or will be performed on with different mock-ups:

up6 is the first which has been represents the ASTThe maximum flowrate is 350

/h and the range of water temperature is 10 to 60°C.is plunged into a water pool

in order to get a 3D representation of

used to confirm the overall TH behavior of the hot plenum (with possibility to realize transients

simulation tools. The mains issues to be

deformation because oscillationcan induce thermal


Some additional needs in TH are concerning main (Intermediate Heat eXchanger)


the qualification of the the primary vessel.

environment but some with

several test benches where different R&D studies will be performed. The

the facilities operating with simulant fluids (water or air) in support of SFR program.

today operationalnamed PLATEAU enables water

: PLATEAU facility

The following tests are or will be performed on

is the first which has been the ASTRID upper

The maximum flowrate is 350 /h and the range of water temperature is 10 to 60°C.

is plunged into a water pool to perform representation of

used to confirm the overall TH behavior of the hot plenum (with possibility to realize transients) and

. The mains issues to be

scillations of the can induce thermal stress on the


Some additional needs in TH are concerning main

(Intermediate Heat eXchanger).


the qualification of the the primary vessel.

with

benches The

the facilities operating with simulant fluids (water or air) in support of SFR program.

operational water

The following tests are or will be performed on

is the first which has been RID upper

The maximum flowrate is 350 /h and the range of water temperature is 10 to 60°C.

to perform representation of

used to confirm the overall TH behavior of the ) and to

. The mains issues to be

of the on the


• Thermal interface behavior: location, fluctuations. • TH stability and flow distribution at the IHX inlet. • Thermal and flow pattern in the ACS.

Fig.9: MICAS mock-up

The MILIPOSO mock-up, which is currently being

designed, will represent the Pump / Diagrid connection (360°, scale 1/6). In this mock-up, will be studied: • the hydraulic stability of the outlet flow coming from

different pump /diagrid connections, • the hydraulics in the diagrid in normal conditions and

asymmetrical situations (break of a pipe, pump shutdown),

• the behavior of the gas (identification of the accumulation zones).

The MISHOCO mock-up will represent a part of the

core and the hot plenum. It is currently in the definition design phase and could be a 120° sector and a 1/3 scale.

With an up-to date design and on a bigger scale compared to the MICAS mock-up, it will allow to study thermal hydraulics in the hot plenum, thermal fluctuations at the core outlet and inter wrapper flows. It will also bring new data for the validation of CFD (Computational Fluid Dynamic) simulation tools.

A hot and cold plenum integral mock-up will be

useful for the study of the natural convection initiating. The scale is to be defined; it could be about 1/10.

Following the tests that will be performed on MILIPOSO, other tests could be required to demonstrate the elimination of gas entrainment in the core. These tests would involve higher flow rates than those available on PLATEAU. Sodium environment mocks-up:

In addition to the tests performed in water environment, some needs require a sodium environment.

CHEOPS (see figure 10) is a CEA technological platform which is planned to be built by 2020. It will be a

set of large sodium facilities for component or system qualification. Some experiments are planned in the NAIMMO test section. NAIMMO is a static sodium vessel allowing for static and dynamic conditions. The issue to be studied is the behavior of sodium aerosols (heat transfers, deposition kinetics…) as support to the qualification of the roof slab (penetrations and thermal protections).

Fig.10: CHEOPS drawing - Integration in the environment

The need of a large scale test in sodium environment

in order to check the natural convection in the primary circuit and the decay heat removal system efficiency is under evaluation.

Finally, some needs specially require increasing the validation data of the thermohydraulic simulation tools.

This is the aim of the R&D program with JAEA which involves tests to be performed in the PLANDTL sodium facility (in particular for the inter-wrapper flow calculation qualification). III.C. CORE ASSEMBLIES III.C.1. Introduction / Background

The ASTRID core assemblies Qualification Plan is dedicated to the licensing of the start-up ASTRID core. This Qualification Plan concerns the internal and external fuel assemblies (RBA), the diversified and independent fast-acting automatic reactor shutdown systems (RBC and RBD), the complementary safety devices dedicated to core damage prevention (RBH), the reflector assemblies and the lateral neutronic protection (RBN) and the mitigation devices.

Two main type of test are performed: out of pile and in-pile test.

hydraulic and thermal hydraulic testsodium/water similarity conditions or in sodium).

Eand Sirradiation tests under representative conditions.

will be completed by the Control Plan and Performance Rise Plan. The main goal of the first one is to confirm the quirradiation examination of ASTRID a

aBoth will be performed in

is based on the usemqualification and the maturity of the in pile behavior knowledge for material, components and assemblies.

of out

III.C.2. Out

Qualification Plan and some assembly design studies need dedicated tests to allow maturity level increasing.

already underway to qualify of

mechanical tests will be performed in sodium on the innovative head of Upper Neutron ShieldingThese tests consist of behavior in sodium with the aim to absence of the

currently performed in support of the innovative dashpot design of the fast acting shutdown system (RBD).tests are carrieproperties are close to sodium conditions (sodium/water similaritassembly.

bundle, the hexagonal wrapper tube and the dashpot (cylinder and piston), in terms of geomaterials. Fthe main

The outhydraulic and thermal hydraulic testsodium/water similarity conditions or in sodium).

The in-Examinations and SUPERPHENIXirradiation tests under representative conditions.

The ASTRID core assemblies Qualification Plan

will be completed by the Control Plan and Performance Rise Plan. The main goal of the first one is to confirm the quirradiation examination of ASTRID a

The second one is assembly lifetime at the equilibrium core condiBoth will be performed in

As indicated before, the qualification methodology is based on the usemethod for qualification –and the maturity of the in pile behavior knowledge for material, components and assemblies.

The two paragraphs below present a few examples of out-of-pile and in

III.C.2. Out-of

Usual outQualification Plan and some assembly design studies need dedicated tests to allow maturity level increasing.

For example, mechanical and hydraulic tests are already underway to qualify of the fuel assembly and

Concerning the fuel assembly, as an example, mechanical tests will be performed in sodium on the innovative head of Upper Neutron ShieldingThese tests consist of behavior in sodium with the aim to absence of the

Another example concerns the hydraulic tescurrently performed in support of the innovative dashpot design of the fast acting shutdown system (RBD).tests are carrieproperties are close to sodium conditions (sodium/water similarity conditions) assembly.

The mockbundle, the hexagonal wrapper tube and the dashpot (cylinder and piston), in terms of geomaterials. Figure the main components.

The out-of-pile tests consist of mechanical tests, hydraulic and thermal hydraulic testsodium/water similarity conditions or in sodium).

-pile test consist of Post xaminations (PIE) of pin irradiated in the past (P

UPERPHENIX programirradiation tests under representative conditions.

The ASTRID core assemblies Qualification Plan will be completed by the Control Plan and Performance Rise Plan. The main goal of the first one is to confirm the qualification results inirradiation examination of ASTRID a

The second one is dedicated to the increasing of ssembly lifetime at the equilibrium core condi

Both will be performed in the

As indicated before, the qualification methodology is based on the use of the

ethod for both main processes necessary to the – the maturity of the manufacturing process

and the maturity of the in pile behavior knowledge for material, components and assemblies.

The two paragraphs below present a few examples pile and in-pile test

of-pile test examples

out-of-pile tests are commonly included to the Qualification Plan and some assembly design studies need dedicated tests to allow maturity level increasing.

For example, mechanical and hydraulic tests are already underway to qualify

fuel assembly and the Concerning the fuel assembly, as an example,

mechanical tests will be performed in sodium on the innovative head of Upper Neutron ShieldingThese tests consist of the validation of the behavior in sodium with the aim to absence of the risk of seizure

Another example concerns the hydraulic tescurrently performed in support of the innovative dashpot design of the fast acting shutdown system (RBD).tests are carried out in water where the thermalproperties are close to sodium conditions (sodium/water

y conditions) in

The mock-up is representative of the absorber rod bundle, the hexagonal wrapper tube and the dashpot (cylinder and piston), in terms of geo

igure 11 hereafter components.

pile tests consist of mechanical tests, hydraulic and thermal hydraulic testsodium/water similarity conditions or in sodium).

pile test consist of Post of pin irradiated in the past (P

rograms) and of experimental irradiation tests under representative conditions.

The ASTRID core assemblies Qualification Plan will be completed by the Control Plan and Performance Rise Plan. The main goal of the first one is

alification results inirradiation examination of ASTRID assemblies.

dedicated to the increasing of ssembly lifetime at the equilibrium core condi

the ASTRID reactor.

As indicated before, the qualification methodology the Technology Readiness Level

main processes necessary to the the maturity of the manufacturing process

and the maturity of the in pile behavior knowledge for material, components and assemblies.

The two paragraphs below present a few examples e tests.

pile test examples

pile tests are commonly included to the Qualification Plan and some assembly design studies need dedicated tests to allow maturity level increasing.

For example, mechanical and hydraulic tests are already underway to qualify the concept

the reactor shutdown systems. Concerning the fuel assembly, as an example,

mechanical tests will be performed in sodium on the innovative head of Upper Neutron Shielding

the validation of the behavior in sodium with the aim to

ure during handling phases. Another example concerns the hydraulic tes

currently performed in support of the innovative dashpot design of the fast acting shutdown system (RBD).

d out in water where the thermalproperties are close to sodium conditions (sodium/water

a scale-1 mock

up is representative of the absorber rod bundle, the hexagonal wrapper tube and the dashpot (cylinder and piston), in terms of geometry, mass and

11 hereafter presents the mock

pile tests consist of mechanical tests, hydraulic and thermal hydraulic tests (in water at sodium/water similarity conditions or in sodium).

pile test consist of Post Irradiation of pin irradiated in the past (PHENIX

) and of experimental irradiation tests under representative conditions.

The ASTRID core assemblies Qualification Plan will be completed by the Control Plan and Performance Rise Plan. The main goal of the first one is

alification results in-situ by postssemblies.

dedicated to the increasing of ssembly lifetime at the equilibrium core conditions.

ASTRID reactor.

As indicated before, the qualification methodology Technology Readiness Level


and the maturity of the in pile behavior knowledge for

The two paragraphs below present a few examples

pile tests are commonly included to the Qualification Plan and some assembly design studies need dedicated tests to allow maturity level increasing.

For example, mechanical and hydraulic tests are concept and components

reactor shutdown systems. Concerning the fuel assembly, as an example,

mechanical tests will be performed in sodium on the innovative head of Upper Neutron Shielding device

the validation of the functional behavior in sodium with the aim to demonstrate the

during handling phases. Another example concerns the hydraulic tes

currently performed in support of the innovative dashpot design of the fast acting shutdown system (RBD). These

d out in water where the thermal-hydraulic properties are close to sodium conditions (sodium/water

mock-up of the

up is representative of the absorber rod bundle, the hexagonal wrapper tube and the dashpot

metry, mass and presents the mock-up with

pile tests consist of mechanical tests, (in water at

Irradiation HENIX

) and of experimental

The ASTRID core assemblies Qualification Plan will be completed by the Control Plan and the Performance Rise Plan. The main goal of the first one is

situ by post-

dedicated to the increasing of

As indicated before, the qualification methodology Technology Readiness Level


and the maturity of the in pile behavior knowledge for

The two paragraphs below present a few examples

pile tests are commonly included to the Qualification Plan and some assembly design studies need

For example, mechanical and hydraulic tests are components

reactor shutdown systems. Concerning the fuel assembly, as an example,

mechanical tests will be performed in sodium on the device.

functional demonstrate the

Another example concerns the hydraulic tests

currently performed in support of the innovative dashpot These

hydraulic properties are close to sodium conditions (sodium/water

up of the

up is representative of the absorber rod bundle, the hexagonal wrapper tube and the dashpot

metry, mass and up with

first results confirm the dashpot design (confirmation of no vibration risk at nominal conditions, of rod drop time, of braking kinetic…).

Center located at “Le Cloop with the mock

April 24

Fig. 11

These tests began in the beginning of 2016 and the

first results confirm the dashpot design (confirmation of no vibration risk at nominal conditions, of rod drop time, of braking kinetic…).

They are Center located at “Le Cloop with the mock

Fig. 12: Test loop for dashpot hydraulic test

April 24-28, 2017

Fig. 11: RBD Dashpot m

These tests began in the beginning of 2016 and the first results confirm the dashpot design (confirmation of no vibration risk at nominal conditions, of rod drop time, of braking kinetic…).

They are conducted by AREVACenter located at “Le Creusot”. Floop with the mock-up.

: Test loop for dashpot hydraulic test NP Technical Center


: RBD Dashpot mock

These tests began in the beginning of 2016 and the first results confirm the dashpot design (confirmation of no vibration risk at nominal conditions, of rod drop time,

conducted by AREVA NP sot”. Figure 12

: Test loop for dashpot hydraulic test

Technical Center


ock-up


at the Technical igure 12 shows the test

: Test loop for dashpot hydraulic test – AREVA



the Technical shows the test

AREVA

and chocks measurements and rod drop repeatability tests. III.C.3. In

fabrication and irradiation experience, gained through the French SFR Program allowed developing rand material solutions for the first ASTRID cores.

irradiation efrom Pirradiation experiments under represen

experimental irradiation tests are being designed, firstly withArrangement on the ASTRID Program and SFR Collaboration (irradiation test planed in Jand also in Russian Fast Reactors (BN600 for fuel tests and BOR

dedicated to absorber pin design studies is currently designed and discussed with BOR(

from PCEA with the aim to materials

on MATINA 2/3 pins dedicated to the Reflector development with magnesium oxide pins or the PIE program on Pmodelling code improvement (CEA fuel called

then on PAVIX 8 irradiated fuel pinsgoal is the validation of the axially heterogeneobehavior. ZEBRE and PAVIX 8 fuel pins were indeed constituted, like ASTRID pins, by fertile and fissile columns distributed axially along the pin.

irradiation was about 12 to 13 at% close to the ASTRID int

performed in CEA hPAVIX 8 PIE program is underway and will be completed at the end of 2017.

The test campaign willand chocks measurements and rod drop repeatability tests. III.C.3. In-Pile Test examples

As indicated before, the maturity, in terms of fabrication and irradiation experience, gained through the French SFR Program allowed developing rand material solutions for the first ASTRID cores.

These solutions hirradiation examinations on irradiated pins or structure from PHENIXirradiation experiments under represen

In the outline of Qualification Plan, several experimental irradiation tests are being designed, firstly within the framework of CEAArrangement on the ASTRID Program and SFR Collaboration (irradiation test planed in Jand also in Russian Fast Reactors (BN600 for fuel tests and BOR-60 for steel materials and absorber).

As an example, dedicated to absorber pin design studies is currently designed and discussed with BOR(Russian Research Institute of Atomic Reactors).

Concerning from PHENIXCEA program named “Pwith the aim to materials and the concept

In this framework, we can mention the PIE programs on MATINA 2/3 pins dedicated to the Reflector development with magnesium oxide pins or the PIE program on PHENIXmodelling code improvement (CEA fuel called GERMINAL).

We can also mention PIE program on ZEBRE pins then on PAVIX 8 irradiated fuel pinsgoal is the validation of the axially heterogeneobehavior. ZEBRE and PAVIX 8 fuel pins were indeed constituted, like ASTRID pins, by fertile and fissile columns distributed axially along the pin.

The Burnirradiation was about 12 to 13 at% close to the ASTRID internal core fuel pin average Burn

The PIE program on ZEBRE fuel pins was already performed in CEA hPAVIX 8 PIE program is underway and will be completed at the end of 2017.

The test campaign willand chocks measurements and rod drop repeatability tests.

Pile Test examples


These solutions have to be validated, either by post xaminations on irradiated pins or structure

HENIX and SUPERPHENIXirradiation experiments under represen

In the outline of Qualification Plan, several experimental irradiation tests are being designed, firstly

in the framework of CEAArrangement on the ASTRID Program and SFR Collaboration (irradiation test planed in Jand also in Russian Fast Reactors (BN600 for fuel tests

60 for steel materials and absorber). As an example, the

dedicated to absorber pin design studies is currently designed and discussed with BOR

Research Institute of Atomic Reactors). Concerning the PIE on irradiated pins or structure

HENIX and SUPERPHENIXprogram named “PHENIX

with the aim to contribute to the qualification of and the concept of

In this framework, we can mention the PIE programs on MATINA 2/3 pins dedicated to the Reflector development with magnesium oxide pins or the PIE

HENIX standard fuel dedicated to CEA fuel modelling code improvement (CEA fuel

GERMINAL). We can also mention PIE program on ZEBRE pins

then on PAVIX 8 irradiated fuel pinsgoal is the validation of the axially heterogeneobehavior. ZEBRE and PAVIX 8 fuel pins were indeed constituted, like ASTRID pins, by fertile and fissile columns distributed axially along the pin.

The Burn-Up reached at the end of PAVIX 8 irradiation was about 12 to 13 at% close to the ASTRID

ernal core fuel pin average BurnThe PIE program on ZEBRE fuel pins was already

performed in CEA hot laboratory (see PAVIX 8 PIE program is underway and will be completed at the end of 2017.

The test campaign will continue with acceleration and chocks measurements and rod drop repeatability tests.

Pile Test examples


ave to be validated, either by post xaminations on irradiated pins or structure

UPERPHENIX irradiation experiments under representative conditions.


in the framework of CEA-JAEA Implementing Arrangement on the ASTRID Program and SFR Collaboration (irradiation test planed in Jand also in Russian Fast Reactors (BN600 for fuel tests

60 for steel materials and absorber). the MACARON irradiation test

dedicated to absorber pin design studies is currently designed and discussed with BOR-60 teams

Research Institute of Atomic Reactors). PIE on irradiated pins or structure

UPERPHENIX reactors, a dedicated HENIX Treasure”

contribute to the qualification of of the ASTRID assemblies.


standard fuel dedicated to CEA fuel modelling code improvement (CEA fuel

We can also mention PIE program on ZEBRE pins then on PAVIX 8 irradiated fuel pins8 goal is the validation of the axially heterogeneobehavior. ZEBRE and PAVIX 8 fuel pins were indeed constituted, like ASTRID pins, by fertile and fissile columns distributed axially along the pin.

Up reached at the end of PAVIX 8 irradiation was about 12 to 13 at% close to the ASTRID

ernal core fuel pin average Burn-Up. The PIE program on ZEBRE fuel pins was already

ot laboratory (see figure 13PAVIX 8 PIE program is underway and will be completed at the end of 2017.

with acceleration and chocks measurements and rod drop repeatability tests.

As indicated before, the maturity, in terms of fabrication and irradiation experience, gained through the French SFR Program allowed developing robust design and material solutions for the first ASTRID cores.


reactors, or by tative conditions.


JAEA Implementing Arrangement on the ASTRID Program and SFR Collaboration (irradiation test planed in JOYO reactor) and also in Russian Fast Reactors (BN600 for fuel tests

60 for steel materials and absorber). MACARON irradiation test

dedicated to absorber pin design studies is currently 60 teams of RIAR

Research Institute of Atomic Reactors). PIE on irradiated pins or structure

reactors, a dedicated Treasure”7 is planned

contribute to the qualification of ASTRID assemblies.


standard fuel dedicated to CEA fuel modelling code improvement (CEA fuel simulation tool

We can also mention PIE program on ZEBRE pins which the main

goal is the validation of the axially heterogeneous fuel behavior. ZEBRE and PAVIX 8 fuel pins were indeed constituted, like ASTRID pins, by fertile and fissile columns distributed axially along the pin.


The PIE program on ZEBRE fuel pins was already figure 13) and the

PAVIX 8 PIE program is underway and will be

with acceleration and chocks measurements and rod drop repeatability tests.

As indicated before, the maturity, in terms of fabrication and irradiation experience, gained through the

obust design


reactors, or by tative conditions.


JAEA Implementing Arrangement on the ASTRID Program and SFR

OYO reactor) and also in Russian Fast Reactors (BN600 for fuel tests

MACARON irradiation test dedicated to absorber pin design studies is currently

RIAR

PIE on irradiated pins or structure reactors, a dedicated

s planned contribute to the qualification of the

In this framework, we can mention the PIE programs

on MATINA 2/3 pins dedicated to the Reflector development with magnesium oxide pins or the PIE

standard fuel dedicated to CEA fuel simulation tool

We can also mention PIE program on ZEBRE pins which the main

us fuel behavior. ZEBRE and PAVIX 8 fuel pins were indeed constituted, like ASTRID pins, by fertile and fissile


The PIE program on ZEBRE fuel pins was already ) and the

PAVIX 8 PIE program is underway and will be

Sand the experimental irradiation tests planned under representativewill complete the fuel pin qualification by confirmation of the inTRL6 level. The TR7 and 8 levels will be reached during ASTRID operation through the carrying out of Performance Rise Plan. IV

important task especially when the industrial project is integrating several significant innovative options.

of engineering standardized qequipment and systems as well as simulation tools.

evolutions of choice options of the projectprogress

absolutely necessary, because every project has cost and time constraints.

level of performance in regards with the planned R&D program will lead to prioritize the actions and to identify several major project risks.

needed for ASTRIDof them here.

persons working on these programsindustrial partners eAREVA NP team)project team.

April 24

Fig. 13: Metallography

fissile/fertile interface (12.1 at %)

All the fSUPER PHENIXand the experimental irradiation tests planned under representative will complete the fuel pin qualification by confirmation of the in-pile fuel behavior step and will allTRL6 level. The TR7 and 8 levels will be reached during ASTRID operation through the carrying out of Performance Rise Plan. IV . CONCLUSIONS

The qualification

important task especially when the industrial project is integrating several significant innovative options.

In addition, in ASTRID case, due to its wide numbeof engineering standardized qequipment and systems as well as simulation tools.

The qualification evolutions of choice options of the projectprogress.

The prioritization absolutely necessary, because every project has cost and time constraints.

Thus, the evaluation of a reasonable but acceptable level of performance in regards with the planned R&D program will lead to prioritize the actions and to identify several major project risks.

Many peneeded for ASTRIDof them here.

However, the authors would likpersons working on these programsindustrial partners eAREVA NP team)project team.

April 24-28, 2017

: Metallography fissile/fertile interface (12.1 at %)

All the fuel PIE results obtained on PHENIX pins will allow reaching TRL 5/6 level

and the experimental irradiation tests planned under conditions in JOYO or BN 600 reactors

will complete the fuel pin qualification by confirmation of pile fuel behavior step and will all

TRL6 level. The TR7 and 8 levels will be reached during ASTRID operation through the carrying out of Performance Rise Plan.

. CONCLUSIONS

ualification which has to be performed important task especially when the industrial project is integrating several significant innovative options.

In addition, in ASTRID case, due to its wide numbeof engineering participants, it was standardized qualification processequipment and systems as well as simulation tools.

qualification approach evolutions of choice options of the project

prioritization among the different needs absolutely necessary, because every project has cost and time constraints.

Thus, the evaluation of a reasonable but acceptable level of performance in regards with the planned R&D program will lead to prioritize the actions and to identify several major project risks.

ACKNOWLEDGMENTS

Many persons are involved in theneeded for ASTRID and it is not possible to mention all

However, the authors would lik

persons working on these programsindustrial partners engineering teams (in particular AREVA NP team), the R&D teams


: Metallography – ZEBRE Fuel Pellets fissile/fertile interface (12.1 at %)

uel PIE results obtained on P

pins will allow reaching TRL 5/6 level and the experimental irradiation tests planned under

conditions in JOYO or BN 600 reactors will complete the fuel pin qualification by confirmation of

pile fuel behavior step and will allTRL6 level. The TR7 and 8 levels will be reached during ASTRID operation through the carrying out of

which has to be performed important task especially when the industrial project is integrating several significant innovative options.

In addition, in ASTRID case, due to its wide numbeparticipants, it was necessary to

ualification processes concerning equipment and systems as well as simulation tools.

approach must be attentive to the evolutions of choice options of the project

among the different needs absolutely necessary, because every project has cost and

Thus, the evaluation of a reasonable but acceptable level of performance in regards with the planned R&D program will lead to prioritize the actions and to identify

ACKNOWLEDGMENTS

are involved in theand it is not possible to mention all

However, the authors would like to thank the persons working on these programs in the

ngineering teams (in particular R&D teams and in the ASTRID

Fissile column


ZEBRE Fuel Pellets – fissile/fertile interface (12.1 at %)

uel PIE results obtained on PHENIX and pins will allow reaching TRL 5/6 level


will complete the fuel pin qualification by confirmation of pile fuel behavior step and will allow achieving

TRL6 level. The TR7 and 8 levels will be reached during ASTRID operation through the carrying out of the

which has to be performed is an important task especially when the industrial project is integrating several significant innovative options.

In addition, in ASTRID case, due to its wide numbenecessary to implement

es concerning equipment and systems as well as simulation tools.

must be attentive to the evolutions of choice options of the project throughout its

among the different needs absolutely necessary, because every project has cost and


ACKNOWLEDGMENTS

are involved in the qualification and it is not possible to mention all

e to thank the in the ASTRID

ngineering teams (in particular and in the ASTRID

Fertile column


and pins will allow reaching TRL 5/6 level


will complete the fuel pin qualification by confirmation of ow achieving

TRL6 level. The TR7 and 8 levels will be reached during the

is an important task especially when the industrial project is

In addition, in ASTRID case, due to its wide number implement

es concerning

must be attentive to the hroughout its

among the different needs is absolutely necessary, because every project has cost and


qualification and it is not possible to mention all

e to thank the ASTRID

ngineering teams (in particular and in the ASTRID


ACRONYMS

ASTRID: Advanced Sodium Technological Reactor for

Industrial Demonstration AVP2: Conceptual design studies, phase 2 CEA: French Atomic Energy Commission CFD: Computational Fluid Dynamic CPHE: Compact Plate Heat Exchanger DB-HIP: Diffusion Bonding by Hot Isostatic Pressing HX: Heat eXchanger IHX: Intermediate Heat eXchanger IRL: Integration Readiness Level JAEA: Japan Atomic Energy Agency MRL: Manufacturing Readiness Level PCS: Power Conversion System PIE: Post Irradiation Examinations R&D: Research and Development RBA: Internal and external fuel assemblies RBC: Independent fast-acting automatic reactor

shutdown systems RBD: Diversified fast-acting automatic reactor

shutdown systems RBH: Complementary safety devices RBN: Reflector assemblies and the lateral neutronic

protection RIAR: Research Institute of Atomic Reactors SFR: Sodium Fast Reactor SGHE: Sodium Gas Heat Exchanger SRL: System Readiness Level ST: Simulation Tool TH: Thermal Hydraulics TRL: Technological Readiness Level VVUQ: Verification, Validation and Uncertainties

Quantification

REFERENCES

1. G. RODRIGUEZ and al., “Qualification program of the ASTRID SFR project: Definition, Methodology and associated Risk Evaluation & Management”, Proc. of ICAPP 2015, Paper 15093, Nice, FRANCE (2015).

2. J. A. FERNANDEZ, SANDIA Report, “Contextual

Role of TRLs and MRLs in Technology Management”, SAND2010-7595 (2010).

3. G. GAILLARD-GROLEAS and al., “Improvements

in simulation tools to be developed within the framework of the ASTRID project”, Proc. of ICAPP 2016, Paper 16385, San Francisco, CA, USA, (2016).

4. G. LAFFONT et al. “ASTRID power conversion system based on steam and gas options”, Proc. of ICAPP 2014, Paper 14116, p. 447-455, ANS, Charlotte, USA (2014).

5. L. CACHON et al. “Status of the Sodium Gas Heat

Exchanger (SGHE) Development for the Nitrogen Power Conversion System Planned for the ASTRID SFR Prototype”, Proc. of ICAPP 2015, Paper 15439, SFEN, Nice, France (2015).

6. D.GUENADOU, I. TKATSHENKO and P.

AUBERT” PLATEAU facility in support to ASTRID and the SFR program: an overview of the first mock-up of the ASTRID upper plenum, MICAS 16th International Topical Meeting on Nuclear Thermal-Hydraulics (NURETH-16), Chicago, USA, Paper 12895 (2015).

7. I. MUNOZ et al. “Recovery of Nuclear materials

from PHENIX to support qualification of ASTRID design options” Proc. Of FR13 Conference, Paris, France (2013).

8. B. RABU et al. “Post-Irradiation Examinations on

PHENIX axially heterogeneous pins relevant to ASTRID fuel design: ZEBRE and PAVIX irradiations” Proc. of ACTINIDES 2013 Conference, Karlsruhe, Germany (2013).

Documents

The qualification processes of simulation tools