Name: Technical Meeting on the Safety Approach for Liquid Metal Cooled Fast Reactors and the Analysis and Modelling of Severe Accidents
Start: 2023-03-13T09:00:00+01:00
End: 2023-03-17T17:00:00+01:00
Location: IAEA

Technical Meeting on the Safety Approach for Liquid Metal Cooled Fast Reactors and the Analysis and Modelling of Severe Accidents

from Monday 13 March 2023 (09:00) to Friday 17 March 2023 (17:00)

Monday 13 March 2023
10:00
10:00 - 10:50
Room: CR4
Contributions

10:00 IAEA Welcome Remarks - Ana Gomez Cobo (IAEA, SH-SAS)

10:15 Objective of the Meeting - Simone Massara (IAEA, SAS) Vladimir Kriventsev (IAEA, NPTDS)

10:30 Administrative Remarks - Gaeul Choi (IAEA, SAS) Lara PEGUERO (IAEA, SAS) Nikoleta MORELOVA (IAEA, NPTDS)
10:50
10:50 - 11:15
Room: CR4
Contributions

10:50 Consideration of Non-Water Cooled Reactors and SMR Safety in the IAEA Safety Standards - Ana Gomez Cobo (IAEA, SH-SAS)
11:15

11:15 - 11:40
Room: CR4
11:40
11:40 - 12:40
Room: CR4
Contributions

11:40 IAEA activities in the field of fast reactor technology - Vladimir Kriventsev (IAEA, NPTDS)

12:10 Development of Safety Design Criteria and Safety Design Guidelines for the Sodium cooled Fast Reactor within the Generation IV International Forum - Shigenobu Kubo (JAEA, Japan)
12:40

12:40 - 14:00
Room: CR4
14:00
14:00 - 15:30
Room: CR4
Contributions

14:00 Prevention and Mitigation Measures for Severe Accidents of China Fast Reactor - Fangyuan Xue (CIAE, China) Zhang Xisi (CIAE, China)

14:30 Consideration of severe accidents in the past French SFR program - David Settimo (EDF, France)

15:00 ARC-100 Commercial Demonstration Unit Optimizations for Decay Heat Removal Systems to Accommodate Accident Scenarios - Nicholas McTiernan (ARC Clean Technology, Canada)
15:30

15:30 - 16:00
Room: CR4
16:00
16:00 - 17:00
Room: CR4
Contributions

16:00 Sodium Fast Reactor Severe Accident Prevention and Mitigation Strategy: U.S. Perspective - Matthew Bucknor (ANL, USA)
17:00

17:00 - 17:15
Room: CR4
Tuesday 14 March 2023
09:30
09:30 - 10:30
Room: CR4
Contributions

09:30 Consideration on safety design approach for future SFRs in Japan, featuring prevention and mitigation of a severe accident - Shigenobu Kubo (JAEA, Japan)

10:00 Mitigation of severe accident by design: strategy and study approach - Frédéric Bertrand (CEA, France)
10:30

10:30 - 10:45
Room: CR4

10:45

10:45 - 11:15
Room: CR4
11:15
11:15 - 12:30
Room: CR4
Contributions

11:15 Towards an integrated French software platform for severe accident simulation in SFR - Pierre Gubernatis (CEA, France)

12:00 CEA Experimental Roadmap for Sodium Fast Reactor Severe Accident R&D - Christophe Journeau (CEA, France)
12:30

12:30 - 13:45
Room: CR4
13:45
13:45 - 15:45
Room: CR4
Contributions

13:45 Development of analysis methods for SFR severe accidents in JAEA and assessment of applicability to safety analysis - Yoshiharu Tobita (JAEA, Japan)

14:15 3D Thermalhydraulics-neutronics simulation of SFR core degradation with the SEASON French Platform - Emmanuelle Dufour (CEA, France)

14:45 The Simplified Radionuclide Transport (SRT) Code for the Source Term Assessment of Pool-Type Metal Fuel Sodium Fast Reactor Severe Accidents - Matthew Bucknor (ANL, USA)

15:15 SFRs severe accident transient study with new particle flow model in SIMMER-V - Andrea Bachrata (CEA, France)
15:45

15:45 - 16:15
Room: CR4

16:15

16:15 - 17:30
Room: CR4

17:30

17:30 - 17:35
Room: CR4
Wednesday 15 March 2023
09:30
09:30 - 11:30
Room: CR4
Contributions

09:30 Safety approach of the Westinghouse lead fast reactor - Jun Liao (Westinghouse Electric Company, USA)

10:00 An introduction to NewCleo LFR design and initial safety considerations - Andrea Barbarino (NewCleo, Italy)

10:30 ENEA contribution to the development of GIF Safety Design Criteria for LFR - Mattia Massone (ENEA, Italy)

11:00 MYRRHA Pre-licensing Nuclear Safety Approach - Irina Sanda (SCK CEN, Belgium)
11:30

11:30 - 11:50
Room: CR4
11:50
11:50 - 13:05
Room: C0739
Contributions

11:50 Status of the SAS4A code metallic fuel models for the simulation of severe accidents in liquid metal cooled fast reactors - Adrian Tentner (ANL, USA)

12:35 Design features and safety assessment of a sodium-cooled fast reactor in Japan for mitigation of severe accidents - Hidemasa Yamano (JAEA, Japan)
11:50 - 12:50
Room: CR4
Contributions

11:50 Severe accidents investigations for lead fast reactors in Romania - Marin Constantin (RATEN ICN, Romania)

12:20 Modelling of the lead-cooled fast reactor accidents with the EUCLID/V2 multiphysics code - Dmitry Veprev (IBRAE RAS, Russian Federation)
13:05

13:05 - 14:15
Room: CR4
14:15
14:15 - 16:05
Room: C0739
Contributions

14:15 Status of numerical tool development for initiating phase in severe accidents of SFRs in Japan - Yoshitaka Fukano (JAEA, Japan)

14:45 Recent developments in modeling of severe accident analysis code PREDIS - Anuraj Vijayan Leela (IGCAR, India)

15:15 Development of fuel deformation module during Power and Flow Transient in Sodium Cooled Fast Reactor Core - Amandeep Singh (AERB, India)

15:45 Discussion & Session Wrap Up
14:15 - 16:15
Room: CR4
Contributions

14:15 Modeling of severe accidents for sodium and lead cooled reactors - Stanislava Senatorova (SEC NRS, Russian Federation)

14:45 Development of drift-flux correlations for vertical forward bubble column-type gas-liquid lead-bismuth two-phase flow - Di Wang (China Nuclear Power Technology Research Institute Co., Ltd.)

15:15 Experimental and Modelling and simulation activities supporting the development of LFR technology - Alessandro Bellomo (ENEA, Italy)

15:45 Heat Transfer Characteristics of liquid metal Fast reactors - Abdelfattah Ali (EAEA, Egypt)
16:15

16:15 - 16:40
Room: CR4

16:40

16:40 - 17:55
Room: CR4

17:55

17:55 - 18:00
Room: CR4

18:15 Social Event - Reception hosted by the IAEA
Social Event - Reception hosted by the IAEA
18:15 - 19:45
Room: Salon A - close to the VIC Cafeteria
Thursday 16 March 2023
09:30
09:30 - 11:15
Room: CR4
Contributions

09:30 Analysis of the remaining core material coolability in a SFR core - Joji Sogabe (JAEA, Japan)

10:00 Analysis methodologies for the evaluation of ATWS accident on SFR in JAEA - Mechanical consequences during expansion phase of the accident - - Yuichi Onoda (JAEA, Japan)

10:45 French research programs related to the severe accident phenomenology in the lower plenum of a SFR - Remi Clavier (CEA, France)
11:15

11:15 - 11:35
Room: CR4
11:35
11:35 - 12:05
Room: CR4
Contributions

11:35 Development of an evaluation method for in-place cooling of a degraded core in severe accidents of sodium-cooled fast reactors - Yuya Imaizumi (JAEA, Japan)
12:05

12:05 - 12:15
Room: CR4

12:15

12:15 - 13:30
Room: CR4
13:30
13:30 - 14:30
Room: CR4
Contributions

13:30 Safety review experience of PFBR and development of Safety Code on Design of FBRs - Ananya Mohanty (AERB, India)

14:00 Assessment of severe accident for SFR projects developed in France - Olivier Baudrand (IRSN, France)
14:30

14:30 - 14:45
Room: CR4

14:45

14:45 - 15:15
Room: CR4
15:15
15:15 - 17:15
Room: CR4
Contributions

15:15 ARDECO CEA-KIT cooperation on ASTRID safety studies and related code developments - Andrei Rineiski (KIT, Germany)

15:45 Design-oriented simulation tools in French SFR projects - Nathalie Seiler (CEA, France) FrÃ©dÃ©ric BERTRAND (CEA Cadarache)

16:15 Modern approaches to deterministic safety analysis for sodium fast reactors - Ruslan Chalyy (IBRAE RAS, Russian Federation)
16:45

16:45 - 17:00
Room: CR4

17:00

17:00 - 17:05
Room: CR4
Friday 17 March 2023
09:45
09:45 - 11:15
Room: CR4
Contributions

09:45 Technical Meeting Wrap-Up Facilitated by Session Chairs
11:15

11:15 - 11:35
Room: CR4
11:35
11:35 - 12:30
Room: CR4
Contributions

11:35 Outputs from the Technical Meeting and General Discussion - Simone Massara (IAEA, SAS) Vladimir Kriventsev (IAEA, NPTDS)

12:15 Closing Remarks by the IAEA - Aline DES CLOIZEAUX (IAEA, NENP Director) Tatjana JEVREMOVIC (IAEA)

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