TWG-FR Activity Report May 2016 May 2017 · TWG-FR Activity Report May 2016 – May 2017 Vladimir...

Vladimir Kriventsev, IAEA, NPTDS, FR Team

50th Meeting of TWG-FR, 15-18 May 2017, Vienna

TWG-FR Activity Report

May 2016 – May 2017

Vladimir Kriventsev, Mikhail Khoroshev, Chirayu Batra

Fast Reactor Team

Nuclear Power technology Development Section,

Division of Nuclear Power

Department of Nuclear Energy

http://www.iaea.org/NuclearPower/FR

50th Meeting of the Technical Working

Group on Fast Reactors (TWG-FR)

IAEA, Vienna, 18– 18 May 2017

http://iaea.org/NuclearPower/FR


50th Meeting of TWG-FR, 15-18 May 2017, Vienna 2

Outline

Fast Reactor Technology Development Team

Programmatic Approach for IAEA FR Activities

Review of last 12 months FR-related activities Meetings

Studies and Publications

Education & Training

Knowledge preservation

Safety

Status of CRPs

Planned Activities

FR17 Conference in Yekaterinburg



IAEA Fast Reactor

Technology Development Team

Division of Nuclear Power

Nuclear Power Technology

Development Section

NPTDS

Head: Mr S. Monti

Fast Reactor Technology

Development Team

DDG: Mr M. Chudakov

DIR: Mr D. Hahn

3



FR Team: Objectives

• Create an effective platform for exchange of information

• Produce technical reports on Fast Reactors and Accelerator Driven

Systems

• Support R&D activities focused on main FR issues

• Agree and converge on safety approaches, design criteria and

guidelines at international level

• Share data on experimental facilities

• Develop, verify and validate advanced simulation tools through

experimental benchmarking

• Provide opportunities for Education and Training

• Collect, retrieve, preserve and make available existing documents,

data and information on fast reactors

4



Programme Definition Process

IAEA Statute &

GC Resolutions (e.g.

Strengthening Document)

MP1 Medium Term Strategy Biennial

Programme & Budget

Programme Content TMs, CMs, CRPs, ICSPs, Training,

Publications, Tool-kits, Portals

Advice from SAGNE

Advice from TWG



IAEA Technical Working Group on Fast Reactors (TWG-FR)

Members of the IAEA Technical Working Group on Fast Reactors

Full Members

Belarus Brazil

China France

Germany India

Italy Japan

Kazakhstan Korea, republic of

Netherlands Russian Federation

Slovakia Sweden

Switzerland Ukraine

UK USA

European Commission OECD/NEA

Observers

Argentina Belgium

Czech Republic Mexico

Romania Spain

Generation-IV International Forum (GIF)

a) Provide advice and guidance

b) Forum for information and knowledge sharing

c) Link between IAEA activities and national communities

d) Provide advice in planning and implementing CRPs

e) Develop and review selected documents

f) Contribute to status report, technical meetings, topical conferences

g) Identify important topic for SAGNE

h) Encourage participation of young professionals in IAEA activities

“The Driving Force…”

6



Programmatic Mindmap of

FR Activities

Modelling and Simulations

Technology Support

Safety

Knowledge Preservation

Education and Training

Information Exchange

International Cooperation

7



Programmatic Areas

•Coordinated Research Projects (CRPs)

•EBR-II (Shutdown Heat Removal Tests)

•NAPRO (Sodium properties)

•PSFR Source Term

•CEFR Start-Up Tests

•FFTF (ULOF Tests)

Modelling and Simulations

• Fast reactor knowledge preservation portal (FRKP)

• Liquid metal cooled fast neutron system database (LMFNS)


• SFR Simulator for Educational Purposes

• ICTP-IAEA Workshop on the Physics and Technology of Innovative Nuclear Energy Systems


• Joint IAEA-GIF Technical Meeting on Safety of SFR

• Passive Shutdown Systems for Fast Neutron Systems – NES Publication

Safety

• NAPRO: CRP

• LMFNS Catalogue Technology Support

8



Meetings 2016-2017



Action Responsible persons Date

Distribution of draft minutes of the meeting for comments IAEA SciSec May-16

Recommendations on involvement of industries in TWG-FR activities CEA, KTH, KAERI May-16

Implement TWG-FR recommendations on FR17 in the Conference

announcement IAEA SciSec Jun-16

New CRP on CEFR Physic start-up (half a year delay)

Expression of interests to be sent to Mr Zhang and Mr

Kriventsev Interested organizations

Sep-16 (May-

17)

Submission of final pre-proposal to NACA/CCRA Mr Kriventsev End 2016

CM to develop detailed CRP proposal 1st Q 2017

end 2017

Endorsement of detailed proposal by TWG-FR and submission

to CCRA TWG-FR + Mr Kriventsev

May-17

Mid 2017

Research contracts and agreements Interested organizations 2nd Half 2017

1st Half 2018

1st RCM Mr Kriventsev 2018

New CRP on heavy liquid metal technology: preparation of pre-

proposal to be presented to next TWG-FR meeting

Italy (ENEA), Romania

(INR), China (INEST),

Russia (NIKIET),

Next 12 months

FR Seminar in Romania (subject to TC funds) INIR + IAEA Secretariat 2018

Suggestions to IAEA Secretariat on celebration 50th anniversary

TWG-FR TWG-FR End of 2016

Action List (49th TWG-FR 2016)



• TM on commissioning and construction to be

possibly held in 2018. Final decision to be taken at

next TWG-FR meeting

• FR Seminar in Romania: to be organized in 2018

if supported by TC regional project

• TM on knowledge preservation. To be confirmed

to TWG-FR by IAEA secretariat, depending on

budget availability. Otherwise postponed to 2017

New Meetings Proposed at

49th TWG-FR in May 2016



2016: Meetings Date Title Major Output/Outcome

26-29 Apr Fourth Research Coordination Meeting on Benchmark Analyses of an EBR-II

Shutdown Heat Removal Test

Draft TECDOC

now in Printing

03-06 May First Research Coordination Meeting on Radioactive Release from the Prototype Fast

Breeder Reactor under Severe Accident Conditions

Technical Specifications

finalized; Benchmark

Started

16-20 May 49th Meeting of the Technical Working Group on Fast Reactors (TWG-FR) Future Planning &

Actions

11-12 July Meeting of the FR17 International Advisory Committee FR17 Structure; ISPC

29 Aug -

02 Sep

Joint ICTP-IAEA Workshop on the Physics and Technology of Innovative Nuclear

Energy Systems for Sustainable Development

E&T Activity

7 - 9 Nov First Meeting of FR17 International Scientific Programme Committee 550 Abstracts Accepted;

Review Started

14-15 Nov Sixth Joint IAEA-GIF Technical Meeting/Workshop on the Safety of Sodium-Cooled

Fast Reactors

Review of GIF SDG

Report

16-18 Nov Technical Meeting on In-Service Inspection and Under Liquid Metal Viewing in Fast

Reactors

Postponed to 2018

07-09 Dec Technical Meeting on Status of IAEA Fast Reactor Knowledge Preservation Initiative Postponed to 2017/18

Oct 2016 CM for the preparation of the detailed proposal of MONJU TT CRP: Vienna, October

2016 (TBC)

Cancelled

Dec 2016 Annual meeting of FRKP Initiative: 1st/2nd week of Dec. 2016 and 2017 Postponed to 2018



2017-2018: Meetings Date Title Major Output/Outcome

8-10

Feb

Consultancy Meeting for the development of NES technical report on

"Passive Shutdown Systems for fast Neutron Systems"

First Draft of NES

Document

3 - 5

April

Second Meeting of FR17 International Scientific Programme

Committee

460 Papers Accepted;

Programme Finalized

15-18

May

50th Meeting of the Technical Working Group on Fast Reactors (TWG-

FR)

Planning & Actions

12-14

June

4th Research Coordination Meeting on Sodium Properties and Safe

Operation of Experimental Facilities in Support of the Development

and Deployment of Sodium-cooled Fast Reactors (NAPRO)

Drafts of two TECDOCs

26-29

June

International Conferences on Fast Reactors and Related Fuel Cycles

in Yekaterinburg

~800 Participants from

33 MSs

7 - 9

Nov

Consultant's Meeting on the Preparation of a new CRP on CEFR

Physics start-up tests

Detailed Tech. Spec.

14-17

Nov

2nd

RCM on Radioactive Release from the Prototype Fast Breeder

Reactor under Severe Accident Conditions (IGCAR, Kalpakkam,

India)

First Results of

Benchmark Simulations

May

2018

51st Meeting of TWG-FR (China, Romania) Planning & Actions

2018 1st RCM on CEFR Physics start-up tests CRP



Modelling and Simulations, Technology

Support



CRP:

Coordinated Research Projects

CRPs on Fast Reactors Technology

CRP recently completed

CRP currently on-going

CRP planned

BN-600 MOX Core Benchmark

Analytical and Experimental

Benchmark Analysis of ADS

PHENIX – EOL Tests

MONJU – Na Natural Convection

EBR-II Shutdown Heat Removal

Tests

NAPRO – Na Properties and

Safe Operations of Exp Facilities

PSFR Source Term –

Radioactive Release Under

Severe Accident Conditions

MONJU – Turbine Trip Test

CEFR – Benchmark Analysis on

reactor physics start-up tests

FFTF – Unprotected Loss of

Flow Test

16



“Benchmark Analyses of an EBR-II Shutdown Heat Removal Test”

Participants

China (CIAE, XJU, NCEPU) France (IRSN)

Germany (KIT, HZDR) Italy (ENEA, UNIPI, POLITO)

India (IGCAR) Japan (JAEA, FU, KU)

Korea (KAERI, KINS) Netherlands (NRG)

Russian Federation (IPPE) Switzerland (PSI)

USA (ANL, TerraPower)

CRP on Benchmark Analysis of an EBR-II

Shutdown Heat Removal Test (launched in 2012)

1st RCM: Argonne, 18-19 June 2012

2nd RCM: Vienna, 5-7 November 2013

3rd RCM: Bologna, 23-27 March 2015

4th RCM: Vienna, April 2016

Publication of final TECDOC: May 2017

Presentation of final CRP results: Special session at FR17

• A very productive verification and

validation exercise accomplished.

• 20 Organizations from 12 countries

• Final TECDOC is in publishing

17



CRP on Radioactive Release from the Prototype SFR under

Severe Accident Conditions (PSFR – Source Term)

Evaluation of:

Transport of fission products (FP), Na and other

radioactive materials from the melted core to the

cover gas

Ejection of FP, Na, fuel particles through the

penetrations of the top shield reactor structure

directly into the containment system and indirectly

through the argon cover gas system

Transport of fission products and other radioactive

materials through the different containment

compartments under various thermodynamics

conditions

First RCM: Vienna, 3-6 May 2016

2nd RCM: IGCAR, November 2017

CRP on “Radioactive Release from the PFBR

under Severe Accident Conditions”

Expressions of Interest

Canada, UOIT China, CIAE, NCEPU

France, IRSN & CEA Germany, KIT

India, IGCAR Korea, Republic of,

KAERI

Russian Federation,

IPPE

EC-JRC

Reference design for the safety analysis:

500 MWe pool type PFBR

Numerical simulation of core bubble expansions during a CDA (100 MJ)

i. 0 ms ii. 50 ms iii. 100 ms iv. 150 ms v. 200 ms

18



CRP on PSFR – Source Term: Timeline 2015-2016

2015 2016 2017 2018 2019 2020

Selecting participants and

awarding

contracts and agreements

X

Definition of the benchmark

specifications and preliminary

input data sets

X

Organization of the first RCM X

Final input data set for the three

phases/objectives of the CRP X

Model development for the three

phases/objectives of the CRP X

Preliminary simulations for the

three phases/objectives of the

CRP

X

Organization of the second RCM X



CRP on PSFR – Source Term: Timeline 2017-2020

2015 2016 2017 2018 2019 2020

Refined simulations of the three

phases/objectives, future R&D

needs… X

Organization of the third RCM X

Overall assessment: sensitivity and

uncertainty analyses, identification of

model/code/data weakness, future

R&D needs, etc.

X

CRP review after its third year X

Drafting of papers to be submitted to

international conferences/journals and

contributions to the IAEA TECDOC X

Organization of the fourth RCM X

Publication of results and organization

of a special technical session at an

international conference X



NAPRO CRP: Sodium properties and safe operation of experimental facilities in

support of the development and deployment of SFR

WP1: Collection and assessment of sodium properties:

international harmonization of data and correlations to be

published in the form of a handbook

WP2: Design rules and best practice for Na exp. facilities

WP3: Guidelines for the safe operation of Na exp. facilities

3rd RCM at CEA-Cadarache, France, 5-9 October 2015

4th RCM in Vienna, 12 -14 June 2017

First draft of Na Handbook (WP1): to be published in 2017

(two TECDOCs)

“Sodium properties and safe operation of experimental

facilities in support of the development and deployment of

SFR”

Argentina (CNEA) China (CIAE)

France (CEA) India (IGCAR)

Germany (KIT, HZDR) Japan (JAEA)

Korea, Republic of (KAERI) Netherlands (NRG)

Russian Federation (IPPE) USA (ANL)

21



NAPRO CRP: Plan & Progress Activity 2013 2014 2015 2016 2017 2018

Selecting participants and awarding contracts and

agreements X

Definition of the methodology and CRP Specifications X

Organizing the first RCM X

Assessment of available data on Na properties X

Assessment of data on Na experimental facilities X

Organizing the second RCM X

Critical re-evaluation of Na properties and gap analysis X

Development of recommendations for design and

operation of Na facilities > > X ?

Organizing the third RCM X

Review of the CRP after its third year X

Drafting of reports, papers and contributions to the

IAEA technical publications X X

External review of the IAEA reports X

Organization of the fourth RCM X

Evaluating the CRP and submitting evaluation report > >

Publication of results > X?



New CRPs Under Consideration

• Monju-TTT (Turbine Trip Test)

• CEFR: Expression of Interest: – 10 MSs; 12 Organizations; 6 months delay

• FFTF: proposed by ANL – postponed to P&B 2020-21 and at the moment on hold, waiting for DOE

decision regarding experimental data needed to carry out the benchmark exercise. It will be reconsidered at the next TWG-FR meeting. DOE/ANL confirmed OK in May 2017

• HLMT: Heavy-Liquid Metal Technology – New CRP on heavy liquid metal technology: Italy and Romania will

coordinate with other interested countries/organizations (e.g. NIKIET and INEST) in order to submit a first pre-proposal at the next TWG-FR meeting; Italy/Romania proposed for discussion; cancelled/delayed

• On Structural Materials Italy/Romania

• BN-800 ?



CRP on CEFR Start-Up Tests:

Proposals • Title:

– Benchmark Analysis on Physics Start-Up Experiments of CEFR

• Scientific Background:

– China Experimental Fast Reactor (CEFR), constructed and operated by CIAE, with a thermal

power of 65MW and an electric power of 20MW.

– During the physics start-up of CEFR, a series of experiments were carried out in four aspects,

i.e., fuel loading and first criticality, control rod worth measurements, reactivity coefficient

measurements, and foil activation measurements. A large amount of experiment data was

obtained in the process

• Scientific Scope:

– to collect and evaluate experiment data obtained from CEFR physics start-up experiments

– to establish a simplified model of the CEFR core and give the correction factors and associated

method

– to share the experiment data and the simplified core model with CRP participants for joint

calculations and analysis;

– to gather and analyze the calculation results, and

– to publish a benchmark analysis report.

– The overall objective is to establish a benchmark based on CEFR physics start-up experiments,

which is helpful for the validation and verification of code and data of the participants.




Expression of Interest Country Organization Contact

Belgium SCK•CEN Gert Van den Eynde

Russia IPPE Gennady Manturov

India IGCAR K. Velusamy

K. Devan (PI)

France CEA Alfredo Vasile

Pierre Sciora (technical contact person)

Japan JAEA H Ohira

H Ohshima

USA ANL Taek K. Kim

Germany GRS, HZDR, KIT Armin Seubert

Emil Fridman

Switzerland PSI Konstantin Mikityuk

Romania ICN/NUCLEAR Daniela Gugiu

Slovakia VUJE, a.s., TRNAVA Petr Darilek

Mexico ININ Armando Gomez

OECD NEA Tatiana Ivanova ?




Preparation Time Schedule

Action Responsible Deadline

Comments and suggestions to Mr Zhang on

the basis of draft pre-proposal distributed at the

49th TWG-FR meeting

All interested

organizations May 2016

Revised pre-proposal on the basis of

comments and suggestions Mr Zhang June August 2016

Distribution to TWG-FR of revised pre-proposal Mr Kriventsev July September 2016

Expression of interests to be sent to Mr Zhang

and Mr Kriventsev

Interested

organizations

September October

2016

May 2017

Submission of final pre-proposal to

NACA/CCRA Mr Kriventsev End 2016 Mid 2017

CM to develop detailed CRP proposal IAEA (Mr Kriventsev ) 1st Q 2017

7-9 November 2017

Endorsement of detailed proposal by TWG-FR

and submission to CCRA

TWG-FR +

Mr Kriventsev May December 2017

Kick-off Meeting (1st RCM) IAEA (Mr Kriventsev) 2018

Kick-off Meeting (1st RCM): 2018

CM on detailed proposals: 7-9 November 2017



Safety



GIF-IAEA Workshops on Safety of SFR

1st : June 2010 4th : June 2014

2nd : Dec 2011 5th : June 2015

3rd :Feb. 2013

6th GIF-IAEA Workshop on Safety of SFR:

14-15 November 2016

• Review of Recent GIF Report on Safety Design Guidelines on

Safety Approach & Design Conditions for GEN-IV SFRs

• Continuous in-depth discussions on the development of SFR

SDC/SDG

Passive Shutdown Systems for Fast Neutron Reactors

• NES document draft is under preparation

• SharePoint site ready for collaboration and knowledge preservation

• CM in February 2017: First Draft is Ready

28



Sixth Joint IAEA–GIF Workshop on

the Safety of Sodium Cooled Fast Reactors

• 14 – 15 November 2016, IAEA, Vienna

– 25 Participants from 8 Countries and IAEA

• Topics – Review and discuss the GIF report

• Safety Design Guidelines on Safety Approach and Design Conditions for

Generation IV SFR Systems

– Share information on the implementation of the Safety Design

Guidelines for SFRs by the designers of innovative SFR concepts

– Discuss the GIF’s response to the regulators’ comments on the GIF

report on Safety Design Criteria for SFRs, and review the updated

report

– Discuss the development of the draft GIF report on Safety Design

Guidelines for key structures, systems and components

29



IAEA Review of GIF Safety

Approach Report:

Conclusions

• GIF Report corresponds to the goals of the Task Force of

the GIF Policy group

• In SDG report, safety requirements and design

recommendations have been harmonized among GIF

designers

• GIF SDG Report provides comprehensive

recommendations for SFR design to assist reactor

developers

• Preliminary Detailed Comments have been reported, and

recommendations have been summarized

30



• NES document draft is under preparation

• SharePoint site ready for collaboration and knowledge preservation

• CM in February 2017: First Draft is Ready

31

PSS for Fast Neutron Reactors: TODO

Chapter reference Responsible Deadline Introduction (1.1 and 1.2) Staffan 28 February 2017

Introduction (1.3 and 1.5) Jeff + Damien + Olivier

1.4 Description of participating organizations All 28 February 2017

3.5 Fusible Link Latches Contact IPPE, if no response then cancel 28 February 2017

3.6 Thermal Volumetric Expansion Drives Damien, or cancel 28 February 2017

3.7 Flow Levitated Absorbers Daniela 28 February 2017

3.8 Cartesian Diver Daniela 28 February 2017

3.9 Levitated absorber particles Cancelled

3.10 Enhanced Thermal Elongation CR drive line Chirayu- contact prof Lee 28 February 2017

3.12 Periphery Channels for coolant voiding Branislav 28 February 2017

Chapter 4 Daniela, coordinator

4.2 BN 350 Daniela During the meeting



4.5 France Olivier, to be checked by for Phenix and EFR

4.6 Japan Daniela, check MONJU and JOYO

5.1.3 Other Systems If no idea then Cancelled 28 February 2017

5.2.2 Lithium Thermostat Module Staffan to contact Wood 28 February 2017

5.3 Curie point temperature actuated absorbers Evaldas 28 February 2017

5.5 Cancel 28 February 2017

Chapter 6 – French experience, JAEA Olivier, to confirm for French experience

Daniela and Vladimir for JAEA

28 February 2017

Chapter 8 Staffan After the draft



TM on Next Generation Reactors and Emergency

Preparedness and Response

Objectives

Present and share knowledge on next generation nuclear power reactors design and

safety features;

Present and share knowledge on current EPR international requirements;

Collectively examine the safety goals of next generation nuclear power reactors and

discuss how they could modify, if really met, the planning basis for emergency

preparedness and response arrangements; and

Discuss and make recommendations on how the current international EPR standards

would apply to next generation nuclear power reactors, including how they could affect

the design of these reactors

Organized by NS, in cooperation with NE Department

TM on 21-25 November 2016, Vienna

Main Discussion: Can be the need for off-site emergency response

eliminated for the next generation reactors?

32



Fast Reactor Knowledge Preservation:

FRKP Portal

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

1. EBR-II Shutdown Heat Removal Test Analysis

2. Monju_UPNC: Sodium Natural Convection in the Upper Plenum of the MONJU Reactor Vessel

3. Phenix_CRW: Control Rod Withdrawal Tests Performed During the PHENIX End-of-Life Experiments

4. 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 2015 and applied in the FRKP portal

34

https://nucleus.iaea.org/sites/lmfns





A comprehensive Catalogue providing detailed

information on experimental facilities currently

designed, under construction or operating

Facilities Designed to support the development

and deployment of innovative liquid metal-cooled

(sodium, lead and lead-bismuth) fast neutron

systems (LMFNS), both critical and subcritical

Identifies existing or future operational

experimental facilities able to support innovative

LMFNS

Expected to facilitate cooperation using existing

and planned experimental facilities for LMFNS,

and enhance their utilization by providing end-

users with detailed information

Encourages international collaborations

LMFNS Experimental Facilities Database Experimental Facilities in support of Development and Deployment of Liquid Metal

cooled Fast Neutron Systems

35



Funded by IAEA RB + MEXT-Japan + in-kind

contributions from other interested MSs

1st CM to finalize specs: January 2016

SFR Simulator

Final Detailed Technical Specifications

prepared by IAEA: Ready

Development of PC based SFR

Simulator for Educational Purposes

Requested by the TWG-FR to support

better understanding of fast reactor

physics and technology

“I hear and I forget.

I see and I remember.

I do and I understand ...”

- Confucius

37



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

“Preparing the next generation…”

38



International cooperation and Information

Exchange



FR09 >> FR13 >> FR17 Conferences

BN-800

IAEA International Conferences on

Fast Reactors and Related Fuel Cycles

560 Abstracts Submitted

460 Full Papers Accepted

40



0

20

40

60

80

100

120

140

160

180

7

1 1 2 4 4

1

34

1 2 2

77

10

4 6

10

50

2

17

28 32

1 1 1 1

176

4 1

3

8 6

2

56

FR17 Abstracts:

Distribution by Countries Country Abstracts

Russia 30.1%

France 14.3%

U.S.A. 11.0%

India 9.8%

China 6.7%

Korea 6.3%

Japan 5.3%

Italy 3.1%

Germany 1.6%

Sweden 1.6%

Argentina 1.4%

Belgium 0.8%

Brazil 0.8%

Slovakia 0.8%

Others 4.1%

GIF 0.6%

EC 0.4%

IAEA 1.6%

41



Background Information on

Previous Edition: Statistics FR09 FR13 FR17

Total Participants 622 642 (400 abstracts) 800 registered

464 papers

Officially

designated

569 612

Observer 53 30

Countries 20 27 30

International

organization

3 4 3 and IAEA

Presentations 150 (oral); 6 (opening); 3

(closing); 9 (panels); 11

(YGE)

208 (oral); 5 (opening); 7

(closing); 15(panels); 7

(YGE)

250(oral); 4 (opening);

11 (plenary keynotes);

10(panels); 6 (YGE)

Posters 154 157 210 (approx.)

YGE 1 1 1

Panel Discussion 2 2 3 2

Keynote Speakers 9 11

Invited Speakers 27 (China, France, India,

Japan, RoK, Russian

Federation, USA, EC,

OECD-NEA)

57 (Belgium, China, France,

Germany, India, Italy, Japan,

RoK, Russian Federation,

USA, EC, EC/JRC, IAEA,

OECD/NEA)

50 (max)

42



Plenary Sessions: Keynote Speakers

Country Speaker Title Day

China Donghui ZHANG Research, development and deployment of fast reactors and

related fuel cycle in China 26.06

India Arun Kumar

BHADURI

Indian Fast Reactor Programme : Status and R&D Achievements 26.06

Japan Yutaka

SAGAYAMA

Current status and future prospects of the fast reactor cycle

technology development in Japan 27.06

France Sylvestre PIVET Status of the French Fast Reactor Programme 27.06

Korea Jaewoon YOO

Status of Sodium Cooled Fast Reactor Development Program in

Korea 27.06

Russia Evgeny

ADAMOV

Closed Fuel Cycle Technologies Based on Fast Reactors as the

Corner Stone for Sustainable Development of Nuclear Power 26.06

Russia Alexander

TUZOV

Research and Pilot Fast Neutron Reactors in Russian Federation

as the Ground for Development of Worldwide Commercial

Technologies

27.06

IAEA Jon PHILLIPS INPRO: Fast Reactors and Enhanced Nuclear Energy

Sustainability 28.06

EC/JRC Maria BETTI

The European Commission contribution to the development of

Fast Reactors for sustainable development 28.06

OECD/NEA Tatiana IVANOVA Overview of NEA Activities Related to Fast Reactors 28.06

GIF Francois

GAUCHÉ

Overview of GEN-IV International Forum Activities. Status and

Prospects of Fast Reactors 28.06

43



Panels

• Development and standardization of Safety Design Criteria

(SDC) and Guidelines (SDG) for Sodium Cooled Fast

Reactors

• Discussion on small and medium sized fast reactors

• Integration With Renewable Energy Sources

(proposed by IAC)

• YGE Panel and Workshop

Special Session

• Benchmark Analysis of an EBR-II Shutdown Heat Removal Test (5 oral presentations and Poster Session)

44



Panel 1:

Development and standardization of Safety

Design Criteria (SDC) and Guidelines (SDG) for

Sodium Cooled Fast Reactors

45



Panel 2:

Small and Medium Sized Fast Reactors

46



FR17 Programme

https://conferences.iaea.org/indico/event/126/timetable



Welcome to Yekaterinburg

Beloyarsk Nuclear Power Plant

• BN-600:

• In operation since 1980

• BN-800

• Connected to the grid in December 2015

• 100 % Nominal Power in August

• BN-1200 (GIF SFR System)

• Starts in 2025 ?

BN-600

BN-1200

48



NPTDS-FR Team:

Major Outputs

FR 17

Conference FRKP portal SFR Simulator

EBR- II

Benchmark

Results

Handbook on

Sodium

Properties

49



Publications

8 Publications in 2017/2018

4 NES documents 4 TECDOCs TECDOCs and NES Reports:

• Analytical and Experimental Benchmark Analysis of ADS –

• In Publishing

• Catalogue of Experimental Facilities for Liquid Metal Cooled FNSs –

• In Publishing; Database is available online

• Benchmark Analyses of EBR-II Shutdown Heat Removal Tests

• In Publishing

• NAPRO CRP

• WP1: Handbook on Sodium Physical and Chemical Properties.

• final draft in June 2017

• WP1: Handbook on Thermal Hydraulics Correlations for Sodium-Cooled

Reactors

• final draft in June 2017

• WP2/3: Sodium Experimental Facilities - Two NES Reports

• in preparation

• Passive Shutdown Systems for Fast Neutron Reactors

• draft NES is in preparation; expected in mid 2017



Venue and Date of the Next

51st TWG-FR

At 49th TWG-FR, May 2016:

• In order to celebrate the 50th anniversary of the TWG-FR it was

agreed to held the next meeting in Vienna in the week 15-19 May

2017. TWG-FR members are invited to suggest specific actions to

the secretariat

• It was also agreed in principle to organize the 51st TWG-FR

meeting in China. INEST will host the meeting. Organization of this

meeting will start just after the next meeting

At 50th TWG-FR, May 2017:

• 51st in China/INEST ok? 21-25 May 2018?

• 2019? Open for proposals, TBD at 51st meeting



TWG-FR Website (Share Point)

Please create a personal account and request access!

nucleus.iaea.org/sites/FR17/frteam/twgfr



TWG-FR Members Proposals

Switzerland CEFR FFTF Digital Reactor Database USA FFTF OECD/NEA CEFR NEA TH data for VFD

China CEFR

51th meeting Germany CEFR Reactor data storage Netherlands FR leaflet every 4 years New CRPs Mixing jets flow multi-scale modeling (TH) Romania FR Seminar in Romania: 2018 postponed? MATFORCE project (materials foe energy - cross-cutting area) New CRP: HLMT



1) Structural Materials and their interaction with coolants

-thermo-mechanical testing;

- erosion/corrosion rates evaluation for various materials in various environments (coolants);

- testing under irradiation;

- materials characterization after testing;

- modeling and simulation ( from neutron interaction....up to defect propagation).

- GEMMA EU project (Italy).

2) Mitigation of erosion/corrosion processes

- methods and technologies - surface engineering

- new materials able to face the harsh environments of fast reactors

-. Testing and characterization

3) Nuclear fuels development/testing/characterization

- new fuels (including MA).

- fuel - coolants interaction ( fuel dispersion, fission products release, etc);

- fuel - cladding interaction

- modeling and simulation.

New study: Status of Structural Materials and Fuels

for Innovative Nuclear Systems (props by Romania/Italy)



Thank you for your attention!

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