12th GIF-IAEA Interface MeetingVienna, 26-27 March 2018

IAEA Activities on Education and Training in Support of GenIV Sytems

Presented by Mikhail KhoroshevNuclear Power Technology Development Section

Outline

• Training courses on:- Research Reactors (RR): Material Testing

for Innovative Reactors- Super Critical Water Cooled Reactors

(SCWR)- Fast Reactors (FR)- (Very) High Temperature Gas Cooled

Reactors (V)HTGR• PC based simulators• E-learning planned modules

2

Research Reactors for testing new materials

Research Reactors for Development of Materials and Fuels for Innovative Nuclear Energy Systems

• Joint ICTP/IAEA Workshop

• 6-10 November 2017, ICTP, - Trieste, Italy

RRs utilization: ApplicationsApplication Number of RR

involvedNumber of countries

Education & Training 166 53

Neutron Activation Analysis 120 53

Radioisotope production 97 43

Material/fueltesting/irradiations 80 27

Neutron radiography 72 38

Neutron scattering 48 31

Si doping 28 18

Geochronology 26 22

Gem coloration 21 12

Neutron Therapy 17 12

Nuclear energy research 16 11

Nuclear Data Measurements 4 4

Other 130 38

Future Reactor Material ServiceTe

mpe

ratu

re (C

)

Displacement Damage (dpa)

S.J. Zinkle, 2007

6

Joint ICTP/IAEA Workshop“Research Reactors for Development of Materials and Fuels for Innovative Nuclear Energy Systems” 6-10 November 2017, ICTP, - Trieste, Italy

Workshop Topics

Capabilities of Material Test Reactors (MTRs)Radiation Effects in Materials and Research MethodsOverview of IAEA Publication, “Research Reactors for Development of Material and Fuels for Innovative Nuclear Energy Systems: A Compendium”Overview of non-critical facilities in support of development of Liquid Metal-cooled Fast Neutron Systems (LMFNS database)MTR Test Design, and Experiment Instrumentation Pre-Irradiation/Experiment Preparation Facilities Post Irradiation Examination Facilities Accelerated Screening of Irradiated MaterialsPossible Next Generation Reactors - Advanced Material Research Needs Qualifying Unique Coolants for Next Generation Reactors Material Testing in Pulsed Research ReactorsAccelerator Testing of Materials - Complement and Comparison with MTRs The Role of Low Power Research Reactors in Material R&D External Beams in Reactor Material ResearchMethods in Irradiation Experiment Modelling

Presentations available:http://indico.ictp.it/event/7993/other-view?view=ictptimetable

RRs of interest for GEN-IV Systems

Research Reactors for the Development of Materials and Fuels for Innovative Nuclear Energy Systems

http://www-pub.iaea.org/books/IAEABooks/10984/Research-Reactors-for-the-Development-of-Materials-and-Fuels-for-Innovative-Nuclear-Energy-Systems

5 Overview tables on RRs for GEN-IV:1) operational, 2) planned, 3) potential for material testing 4) pulsed mode RR, 5) examples of low power RR

TABLE A-1 OPERATIONAL RESEARCH REACTORS; OVERVIEW OF CURRENT CAPABILITIES FOR MATERIAL TESTING RESEARCH

IrradiationCountryResearchreactor

Scheduled and planned

life- time Operation

cycle

RowerTypeFuel

CoolantModeratorReflector

— number— height— diameterFlux, (ntm4!1):— total flux— fast flux ( XI . 1

MeV)Estimated dpa-'year

in steel

Test configurationTest environment

temperature and pressure range

Instrumentation and canirol

(irt-pite temperature, pressure.

JissttM g£l.4 mortiiorirtg, stress strain, etc.)

Otherfacilitiesfficdirrs,rientroit

trcWva/ftmdjrTLf/r.sr.f.

ete.J

fin-site PIE capabilities (hoi celts,

glove boxes, tools/or

stress analysis, etc.)

Design, manufacturing

disposition, shipping,

waste handl Lng and other

capabilities

Methodof access

anddegree of utilization

Miscellaneousand readiness for material

testing research

Belgium

BR-1

50-120 MW Tank-in-pool HEW

72-93% U-235Light water

With cosine flux profile

— Standard KO mm 0. 900 mm heighl

— Large 200 mm 0. 900 mm height

Thermal and fast neutron flux up to 10”nemos'

PWrR loop conditions Water pool conditions

Stagnant waier Stagnant men gas

Liquid metalVacuum

Air cooling flow

1 leatmg, (lux and temperaiure monitoring capabilities In various

rig designsTemp range 50-6(XJaC

tlannna irradiation

facility on-sile

fin-site hoi cells available

Full scale 3D heterogeneous M CNP

modelMCNPMC withIra ns mutation

trajectory analysis code

PIE facilities on-site

IPS design group and IPS manufacturing/

assembly in­house

Waste handlingA shipping

possible

Via collabo­ration

agreementCommercial

Long, proven

experience with

material testing

research, high flux

applications

China

CEFR

2011

65 MWPool type

UO: orMOXSodium coolant and moderatorStainless steel and boron reflector

251 irradiation positions for special test subassemblies, to be pul into;KL fuelsubassemblies,

1 neutron source subassembly and169 steel shielding subassembliesMax neutron flux (F) 3.5 * J0li memos'1Max9.3 dpa.'SOEFPIO

No special resting loopHigh temperature sodium static test facility (SSTF)- temperature SOO’C- cover gas Argon- Oxygen in sodium:

10 ppm,- Carbon in sodium:

10 ppm.High temperature sodium tliermal convection test loop (STCTL)- Max. temperature;

550"C;- Max. temperature C;- Flow speed; 4-10 _ a- J

H tgh Temperature sodium mass transfer lest loop (SMTTL)

Fuel-claddingchemicalinteractionout-of-pile testfacility(FCCITF)

— Max. test temperaiure 9tKK’C

— electron microscopy lab

— TEM operating at 200 tv. magnifications from 200(1 X to 1500 000 X.Equipped with a JEOL Instruments energy dispersive X-ray spectrometer.

— mechanical lest lab 3001 pendulum impact machines, tensile test machines and creep testing machines.

— hot cells— radiochemical

laboratory

Wide range of material

testing research

applications

30 Profiles - detailed information on RRs capabilities for material/fuel testing R&D

Super Critical Water Cooled Reactors SCWR

TRAINING COURSESREACTOR TECHNOLOGY

ASSESSMENTFormal process of specifying key factors, based on country- specific protocols, assigning relative importance to each, and quantitatively evaluating technology design in a consistent manner using reliable and comparable data, e.g.

IAEA Nuclear Energy SeriesNo. NP-T-2.1

Common User Considerations (CUC) by Developing Countries for Future Nuclear Energy Systems:Report of Stage 1

IAEA Nuclear Energy SeriesNo. NP-T-1.10

Nuclear Reactor Technology Assessment for Near Term Deployment

from ARIS and vendors. 2014 - 2017

OCEAN

OCEAN

ATLANTIC

OCEAN

ATLANTIC

OCEAN1

PACfFfC

Training Course on Science and Technology of SCWRs• One-week course on “Science and

Technology of SCWRs” were held in 2011, 2012 and 2013.

• Organized by the IAEA or the host organizations in cooperation with the IAEA.

Shanghai Jiao Tong University (SJTU), Shanghai, China, 26-30 August 2013

International Centre for Theoretical Physics (ICTP), Trieste, Italy,27 June -1 July 2011

McMaster University Hamilton, Canada, 16-21 July 2012

UOIT-IAEA Course on Science and Technology of SCWRsOshawa, Canada, 04 - 08 July 2013 13

Training Course on Science and Technology of SCWRs

• Lectures, covering from fundamental technologies to the up-to-date SCWR R&D status, include:- Introduction and Fundamental Technology;- SCWR Concepts;- Reactor Physics and Core Design- Thermal-Hydraulics and Safety;- Materials and Chemistry; and- Related special lectures.

UOIT-IAEA Course on Science and Technology of SCWRsOshawa, Canada, 04 - 08 July 2013 14

Fast Reactors (FR)

Liquid Metal Cooled Fast Neutron Systems (LMFNS)

Fast Reactors:Training Courses and Workshops• IAEA Workshops and Schools on Innovative Nuclear Energy Systems

• Recent Course: Joint ICTP-IAEA Workshop on the Physics and Technology of Innovative Nuclear Energy Systems for Sustainable Development,29 Aug - 02 Sept 2016, Trieste, Italy- Imparted theoretical foundation of all aspects of innovative nuclear energy systems- Familiarized students with models and codes for design and safety analysis- Provided an active forum for sharing new ideas

• Next ICTP-IAEA Workshop on Innovative NESs20 - 24 August 2018, Trieste, Italy- Open for Applications

“Preparing the next generation..."

29 August - 2 September 2016 Miframare, Trieste

The Abdus Solam

International Centre for Theoretical Physics

IAEA 16

Workshop on the Physics and Technology of Innovative Nuclear Energy Systems for Sustainable Development

TOPICS:

Global scenario for nuclear energy;Innovative reactor concepts and fuel cycle options,Reactor physics of innovative nuclear energy systems;Status of advanced primary components and development and qualification of new structural materials,New safety approaches, safety requirements and safety design criteria;Passive safety systems and other enabling safety technologies;Safety analysis including severe accident scenarios;Advanced modelling and simulation.Status of research and technology development in support of innovative reactor and fuel cycle technologies.

MM&UME

Group Activity -IBasics of SFR Core Thermal-Hydraulic Modeling

Group Activity IIPassive shutdown system: Coolant loss / Temp. Excursion

Workshop on the Development of Material and Fuels for Innovative Nuclear Energy Systems

IAEA.org NUCLEUS

MfWsIAEA Catalogue of Facilities in Support of L

Home LMFNS Facities Database Overview of SFR Overview of LFR LMFNS Compendium

Catalogue of Facilities in Support of Liquid Metal-cooled Fast Neutron Systems (LMFNS Catalogue)

This LMFNS catalogue is a living database, which is, in its current form, presents an electronic version of section 4 of the IAEA Nuclear Energy Series publication (in progress) "Experimental Facilities in Support of Liquid Metal Cooled Fast Neutron Systems. A Compendium”.

LMFNS Compendium. Summary of the IAEA publication

To overview the potential capabilities of 150 experimental facilities in 14 IAEA Member States to support the development and deployment of the innovative Liquid Metal cooled Fast Neutron Systems (LMFNS) and navigate yourself through the LMFNS Facilities Database” click on the below buttons:

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The Abdus Salam

6-10 November 2017 Miramare, Trieste - Italy(CTP International Centre

for Theoretical Physics

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Overview of SFR Overview of LFR

For detailed information on these facilities 1) click on the below button "LMFNS Facilities Database" (also on top of this page), 2) select the Coolant technology - SFR, LFR or both in the search box, 3) use other search and filtering tools as appropriate. 4) click on the Facility Profile you are interested in.

LMFNS Facilities Database

Overview of experimental facilities in support of Sodium cooled Fast Reactors (SFR)

Content Editor

Profile C ountry Facility Alain application

SFR 1 China CEDISFR 2 China ESPRESSOSFR 3 China FRIYG-1SFR 4 China HTMTSLSFR 5 China HTTCSLSFR 6 China MSSPDSFR - China SIPHONSFR S China TSBSSFR 9 France BACCARASFR 10 France CARNAC

CHEOPS -SFR 11 France NABYNE_

EsaCHEOPS -

SFR 12 France NAIMMO_EsaCHEOPS-SFR 13 France NSET_Esa

SFR 14 France CORONADIADEM OSFR 15 France Na

SFR 16 France DOLMENSFR 17 France FUTUNA 2SFR IS France IRINASFR 19 France LIQUIDUSSFR 20 France MASURCASFR 21 France MECANASFR 22 France PEMDYNSFR 23 France PENELOPESFR 24 France PLATEAUSFR 25 France PLINIUS 2

SUPERFENSFR 26 France NECSFR 27 France VKS2SFR 2S G ermany ALINASFR 29 G ermany DRESDYNSFR 30 G ermany KASOLASFR 31 G ermany NATANSFR 32 G ermany SOLTEC

SOOkWSFR 33 India Sodium

LoopSFR 34 India RIM

IN SOTSFR 35 India

Zero power

Overview of experimental facilities in support of Heavy Liquide Metal cooled Fast Neutron Systems, i.e Lead/LBE cooled fast reactors (LFR)

Content Editor

Profile Count it Facility Main application

Zero power DBA and □EC

ThermalHydraulics

LFR 1 Belgium COMPLOT

LFR 2 Belgium CRAFT 32

LFR 3 Belgium ESCAPE

LFR 4 Belgium HELOIS HI

LFR 5 Belgium HUM

LFR 6 Belgium LILIPL TTER

LFR 7 Belgium LEMETS1

LFR S Belgium LEMETS2

LFR 9 Belgium LEMETS3

LFR 10 Belgium LEMETS4

LFR 11 Belgium MEXICO

LFR 12 Belgium MYRRHABELLE

LFR 13 Belgium SHAKESPEARE

LFR 14 Belgium RHAPTER

LFR 15 Belgium VENUS-FLFR 16 China CLEAR-0 |

LFR 17 China CLEAR -S

LFR IS China KATIN H -M

LFR 19 China KYLIN n -S

LFR 20 China KYUN H TH FC

LFR 21 China KATES' H -TH MC

LFR 22 China KATES' H-THN'C

LFR 23 Czech Republic CALLISTO

LFR 24 Czech Republic COLONRII

LFR 25 Czech Republic COLONRI n

LFR 26 Czech Republic MATLOO

LFR 27 EU LFREF

LFR 28 France BACCARA

LFR 29 France MASURCA |

LFR 30 Germany CORELLA

LFR 31 Germany CORRIDA

LFR 32 Germany COSTA

LFR 33 Germany CRISLA

Cross cutting facility

IAEA.org NUCLEUS \ jjI! ? ft 1 KHOROSHEV, Mikhail

IAEA I Catalogue of Facilities in Support of L Search this site

Home LMFNS Facilities Database Overview of SFR Overview of LFR LMFNS Compendium

View All

Main research field,s)

Reactor type SFRLFRCross-cutting (dual application)Country

COMPonent LFR LOop Tests

Max Power (kW)

75

□ Belgium

□ China_ , lure Facility name

U Czech Republic .r totWl COMPLOT

U EU

□ France

□ Germany

□ India

□ Italy

□ Japan

□ Korea

□ Latvia

0 Russia

□ Spain

□ Sweden

□USA _ _

LILIPUTTER

CRAFT V2

E-SCAPE

HELIOS

Corrosion LFR Research for Advanced Fast reactor Technology

European LFRSCAIedPoolExperiment

HEavy Liquid LFRmetalOxygencontrolSystem

Heavy LFR Metals Lab

Liquid Lead LFR alloyInnovative PUmp Technology TEst Rig

Belgium

Belgium

Belgium

Belgium

Belgium

60

100

10

Zero power facility for V&V and licensing purposesDesign basis accidents (DBA) and design extended conditions (DEC)Thermal-hydraulicsCoolant chemistryMaterialsSystems and componentsInstrumentation & ISI&RCross-cutting (dual application for SFR&LFR)

tCoolant of the faci Iity Status Main research field(s) Max Operating Temperature (°C) Max Operating Pressure (MPa)

Lead-bismuth in operation Thermal-hydraulics,Systems and eutectic (LBE).Air components,Instrumentation &

ISI&R

Lead-bismuth in operation Coolanteutectic (LBE) chemistry,Materials,Instrumentation

& ISI&R

Lead-bismuth under Design basis accidents (DBA) andeutectic construction design extended conditions(LBE),Air,Other (DEC),Thermal-

hydraulics,Instrumentation & ISI&R

Lead-bismuth in operation Coolant chemistryeutectic (LBE)

Lead-bismuth in operation Coolanteutectic (LBE) chemistry,Materials,Instrumentation

& ISI&R

Lead-bismuth in operation Coolant chemistry,Systems and eutectic (LBE) components,Instrumentation &

ISI&R

400

200

320

450

500

16

0.1

07

0.05

200

Fast Reactor Knowledge Preservation: FRKP Portal

CRPs data uploaded: (Designed and ready for use by projects3 participants)

1. EBR-II Shutdown Heat Removal Test Analysis2. Monju_UPNC: Sodium Natural Convection in the Upper

Plenum of the MONJU Reactor Vessel3. Phenix_CRW: Control Rod Withdrawal Tests Performed

During the PHENIX End-of-Life Experiments4. Phenix_NCT: Sodium Natural Circulation Tests Performed

During the PHENIX End-of-Life Experiments

• New CRP on "Radioactive Release from the Prototype Fast Breeder Reactor (PFBR) under Severe Accident Conditions "

• Passive Shutdown Systems for Fast neutron reactors

Available also on the web:• Experimental Facilities in support of Development and

Deployment of Liquid Metal Cooled Fast Neutron Systems (LMFNS). LMFNS catalogue is a live database

• FR 17 conference

FR Taxonomy was revised in 2016 and applied in the FRKP portal

High Temperature Gas Cooled Reactors HTGR

HTGR Technology Training CoursesPlan to develop a comprehensive course on HTGRs

1st course hosted by INET 22-26 October 2012, Beijing, China

TechnologyNeutronics Thermalfluid

Fuel Materials Safety Core Structure Design Source Term Management

Power Conversion Process Heat Applications SUB-SYSTEMS Waste management

Licensing ASPECTS Decommissioning Economics

More than 40 participants from 17 Member States

discussed the technological features of modular HTGR designs, including

inherent safety characteristics, and how these impact the design choices and safety evaluation of this reactor type. 2nd course hosted by BATAN 19-23 Oct

2015, Serpong, Indonesia

Safety Analysis Course based on Juelich HCP code under consideration for 16-20 July 2018 General HtGr Technology training course scheduled for 2018 not funded

Examples of test facilities for demonstration / R&D in MS

China HTR-PM test facilities- HTR-10 research reactor- Full scale, under HTR-PM helium conditions: steam

generator unit; helium circulator; fuel handling system; control rods driving system; small absorber balls reserve shutdown system; helium purification system; reactor protection system and control room

- Demo Fuel production facility followed by the commercial fuel plant (fuel tested in Petten)

USANatural circulation Shutdown heat removal Test Facility (NSTF)High Temperature Test Facility (Loss of Forced Cooling/ Air Ingress Studies)Fuel fabrication and AGR irradiation tests and PIE

- High temperature materials (metals)- Graphite irradiation / characterization

South Africa- Helium test facility: tests full scale systems and

components- Heat Transfer Test Facility

Historical test facilities in Germany

PC based simulators

IAEA PC Based Basic Principle Nuclear Power Plants Simulators

Learning-by-Doing Education and Training on Reactor Technologies

in Support of Member States' Human Resource and Capacity Building

IAEA Programme Objective“Assist Member States in training nuclear researchers, engineers, and nuclear regulators”

Systematic Education and Training on various topics

IAEA established an Education & Training Courses based on active learning (learning-by-doing) with nuclear reactor simulation computer programs (basic principle simulators) to assist Member States in educating & training their nuclear professionals.

❖ Basic Principle Simulators provide a thorough demonstration of the basic operational principles of NPPs by illustrating general concepts, and demonstrating and displaying fundamental physical processes of the plant:o Operational characteristics o Reactivity control systems o Safety systemso Responses to transients and accidents.

❖ Reactor Technology Assessment Stageo The best technology for a national objective and needs o Training in reactor technologies o Learning of the technology specifics: ARIS data base

IAEA PC Based Basic Principle Nuclear Power Plants Simulators

IAEA assist Member States in educating nuclear researchers, engineers, and regulators with effective learning-by-doing approach integrating the

all 4 learning dimensions

Apply material to real-world examples Group discussion Explain course material Z

Written and spoken explar

Written summariesVisual and outlines to group members

discussionsDiagrams, sketches, \ pictures, movies, etc. Flow charts and concept

Clearly circle, underline, i important information

Review materials and think of possible applications Write short summaries of

Intuitive Learners- Interpret theories with facts- Spell out important details to

remember- Offer tips for checking Sensing

work, especially on Learnersdetailed problems

- Connect theories to real-world issues

- Explain how abstract theories are applied to solve real problems

- Link theory to practice

NEW: SMR Simulator 4 learning dimensions

IAEA arranges for:• Distribution of simulation software, and corresponding training materials• Management of existing suite of simulators• Development of new simulators• Organization of training courses and workshops

IAEA COLLECTION OF PC-BASED NUCLEAR REACTOR SIMULATORS IN E&T

• Computer based tools are the state of the art learning approaches• IAEA PC based simulators are designed to provide insight and

understanding of the general design and operational characteristic of various power reactor systems:- PWR, BWR, WWER, PHWR, iPWR and have

• Focus on education and training in classrooms, and not licensing or reactor operator training, or benchmarks of other computer codes and methods

30

■rlKIIAEA PC Basic Principle Simulators

Effective hands-on educational & training tools

Pressurized Water Reactor (P WR)Sim u!atorsr@-PCTRAN:Conventional-Two-LoopPressurized-WaterReactor-(PWR)5

<S-Advanced PWR:Two-Loop-LargePWR-(Korean-OPR-1000)^

<® - Russian-type-PWR{WWER-1000)5

@-Advanced PassivePWR-(AP-600)l' <§-lntegral-Pressurized-WaterReactor-(SMR)5

Boiling-Water Reactor(BWRs)Simulators\@-Conventional-Boiling Water-Reactor-(BWR) with Active Safety Systems*-

<@-AdvancedBWRwithPassiveSafety-Systems-(ESBWR)T

Pressurized Heavy Water Reactor (PHWRfr<&-Conventional Pressurized ■HeavyWater-ReactorPHWR-(CANDU-9)y @-AdvancedPHWR<ACR-700)l

Part- Task Simulator@-MicroRhysicsSimulator(Lite)5

UnderDevelopment<§-HighTemperatureGas-CooledReactor-(HTGR)5

- S od i u m-Coo I ed • F ast-Rea ctor(S F R)5[

HTGR proposed SimulatorBasic principle simulator

• Planned unfunded activity

• Draft specification has been developed

Reference plant Modular Prismatic and Pebble-bed designs

Status Need identifiedDraft specification developed

Proposed features Indirect (steam); Direct gas turbine and cogeneration variations proposed.Fuel handling module

High Pressure Turbine Trip

Intermediate Pressure Turbine Failure of Helium Circulator

Low Pressure Turbine Trip Helium Inventory system trip

Water flow rate (kg/s)

Reactor Neutron Pwr (%) 99.98

Reactor Thermal Pwr (%) 100.31

Closure of main isolation valve

Malfunction of Condensor

Helium Purification system trip

Reactor Trip

Steam Generator Tube Failure

Loss of Feedwater Accident

4 6

Time

4 6Time

Time '-P?

Scroll 0

120100

1: Reactor Vessel

5: Condensor6: High Pressure Turbine

1Z: Recuperator13: feedwater Storage Tank

15:Dump tank

HTGRSIMULATOR 1 -

Hot Steam temperature (C) 570CONTROLHe hum flow , Initial

.‘jj* Condition Setting

LOOPS SCREEN Hot Steam pressure (MPa) 16.7

Hot Helium Temperature (C) 750 ---.J

SFR Educational Simulator

• Funded by IAEA RB + MEXT-Japan + in-kind contributions from other interested MSs

• Detailed technical specifications are ready.

ai,d

Representative mimic33

E- learning

Proposal:Development of E-Learning Modules on Nuclear PowerTechnology DevelopmentThe IAEA is seeking to develop NPTD E-learning modules in order to:• provide capabilities for awareness training to a broader target audiences in IAEA Member States• increase effectiveness of its instructor-led (‘face-to-face’), ‘blended learning training courses and

pre-training courses

General specification of the scope of work

• Water-cooled reactors & simulators• Small and medium sized reactors and modular reactors (SMR)• Advanced technology for fast reactors & Fast Reactors simulator• Advanced technology for gas cooled reactors• Technology development for advanced reactors for non-electric applications• The IAEA Severe Accident Management Guideline SAMG-D Toolkit• Facilities in support of fast reactors development (Liquid metal-cooled fast neutron systems)• other

For each module the scope should be specified by the working group and agreed with the PM.• up to 5 lectures per 1 module are recommended• one lecture no more than 1 hour• one lecture should be split in several 10-15 minutes sections

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Atoms for peace and development

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