NEA NUCLEAR SAFETY RESEARCH JOINT PROJECTS WEEK:
Success Stories and Opportunities for Future Developments
9-13 January 2023

NEA NUCLEAR SAFETY RESEARCH JOINT PROJECTS WEEK:
Success Stories and Opportunities for Future Developments
9-13 January 2023

WelcomeDay 4 – Thursday 12 January

NEA NUCLEAR SAFETY RESEARCH JOINT PROJECTS WEEK:
Success Stories and Opportunities for Future Developments
9-13 January 2023

Questions: Questions, feedback and suggestions
Event public page: Nuclear Energy Agency (NEA) - NEA Nuclear Safety
Research Joint Projects Week: Success Stories and Opportunities for
Future Developments (oecd-nea.org)

Form: Questions, feedback and suggestions link

available in the registration confirmation email

Session 4

Joint Projects for Safety in Accidental Situations,Learnings and Perspectives

SESSION MODERATORDr Hideo NAKAMURA
Technical Associate, Japan Atomic Energy Agency(JAEA), JapanSESSION 4: Joint Projects for Safety in Accidental Situations, Learnings and Perspectives

SESSION 4: Joint Projects for Safety in Accidental Situations, Learnings and Perspectives

Session 4
Joint Projects for Safety in Accidental Situations,Learnings and Perspectives► Examples of Containment Thermal-Hydraulics,
Mitigation Systems and Hydrogen Risk Management
Projects

SESSION 4: Joint Projects for Safety in Accidental Situations, Learnings and Perspectives

THAI/THEMISDr Sanjeev GUPTA,
Deputy General Manager, Head of Reactor Safety &Engineering, Becker Technologies, Germany

SESSION 4: Joint Projects for Safety in Accidental Situations, Learnings and Perspectives

Examples of Containment Thermal-Hydraulics, Mitigation
Systems and Hydrogen Risk Management Projects–THAI/THEMIS –Dr. Sanjeev Gupta
Becker Technologies GmbH, Germany
January 12, 2023

Overview of THAI/THEMIS project Experimental research to investigate specific issues for LWR containment under severe accident
conditions: to provide data for validation and further improvement of safety analyses tools,
 to support in SAM analyses.
 Area of experimental research:-

Thermal hydraulics and hydrodynamics of water pools,-

Hydrogen (combustible gases) distribution, combustion and recombination, and-Aerosol and Iodine (Fission product) behavior.

 Performance testing of active and passive mitigation systems, e.g. Passive Autocatalytic
Recombiners (PARs), Pressure suppression pool, Spray, Filtered Containment Venting System

S. Gupta | Nuclear Safety Research Joint Projects Week | 12. January 2023 |12

Overview of THAI/THEMIS project

OECD/NEA THAI/THEMIS projects
 Ongoing since 2007
 Current THEMIS project phase (2020 - 2024)

THAI National project Ongoing since 1998
 Current project phase (2021 - 2023)

 includes tests on safety of LW-SMRs

Highlights:
Data sharing: Selected data for analytical activities
from national projects shared with OECD/NEA
project partners
Facility upgrade: Generally done in national projectframe prior to proposing in OECD/NEA projects
S. Gupta | Nuclear Safety Research Joint Projects Week | 12. January 2023 |13

THAI+ – multi-compartment test facility
THAI+: Thermal-hydraulics, Hydrogen, Aerosols, Iodine, + Multi-compartment
THAI

PAD

Height

9.2 m

9.8 m

Diameter

3.2 m

1.6 m

Volume

60 m3

18 m3

1.4 MPa / 180°C

TTV

PAD

Upper and lower connecting pipes: DN 500
 Configurable sub-compartments
 Large top openings to install test components
 Pressure resistant for (slow) H2-deflagrations
 Licensed for use of radiotracer I123

Recent upgrades:- Extension to two-vessel system (+PAD) (2015)- Licensed to perform tests with Carbon Monoxide (2019)- Provision arrangements to perform first LW-SMR tests (2021)

TTV: THAI Test Vessel
PAD: Parallel Attachable Drum

S. Gupta | Nuclear Safety Research Joint Projects Week | 12. January 2023 |14

Experimental hardware – extrapolation to reactor scale
Focus of THAI experimental research- Generic “containment” research – e.g. PWR, BWR, PHWR-

Reactor typical “configurations”, “flow regimes”, etc.
Coupled-effect tests – “phenomena”, “mitigation systems”, etc.
Representative boundary conditions, e.g. P, T, gas composition & concentration, well-mixed/stratified conditions, etc.
Measurement systems for measuring test parameters of interest – application for code/model validation, mitigation
systems performance quantification, etc.

S. Gupta | Nuclear Safety Research Joint Projects Week | 12. January 2023 |15

Experimental hardware – project specific developments
Instrumentation
Test configurations

S. Gupta | Nuclear Safety Research Joint Projects Week | 12. January 2023 |16

Nuclear Safety Applications (1) Code Benchmarking

 Code benchmarking - highlights
 Majority of THAI code benchmarks consisted of both “blind” and “open” phases
 Specification reports prepared by OA (AWG) including details on initial and boundary conditions
 Project technical reports documenting comparison between experiment and codes results
 Open joint publications (conferences/journals) on code benchmark results and the remaining open issues

Benefits: New validation “common” database, modelling improvement and extension, reactor
applications and others.
S. Gupta | Nuclear Safety Research Joint Projects Week | 12. January 2023 |17

Nuclear Safety Applications (2) Use of project results by partners (selection)
Organization
GRS (Germany)

THAI results
Hydrogen distribution and
PAR tests

Basis for development of nodalization guidelines for LP code uses forstratified gas atmosphere in containments
Re-evaluation of PAR concept in German PWRs with revised PAR model
Development and validation of aerosol washdown from surfaces ofcontainment walls under accident conditions (AC2/COCOSYS)

Aerosol washdown

UJV (Czech Republic)

Hydrogen distribution and
PAR tests

To support in designing a PARs based mitigation system installation in theTemelin NPP containment (MELCOR code)

IRSN (France)








Fission product reentrainment (with andwithout impurities) tests
PAR tests
Iodine flashingAssessment of aerosol re-entrainment impact on 137Cs source term of the
Fukushima Daiichi accident (ASTEC code)
Extension of PSA studies and accident modelling by including PARinduced ignition behaviour results (SPARK/ASTEC)
Identification of lack of validation of existing iodine chemical models in
the aqueous phase – high temperature chemistry (ASTEC)JAEA (Japan)

Iodine/Aerosols interaction

Estimation of gaseous iodine adsorption velocity on aerosols derived
based on tests data for application in BWR SA analysis (ART code)

AERB (India)

PAR tests

Development of CFD code (FLUENT) for hydrogen risk analyses in PHWRs

S. Gupta | Nuclear Safety Research Joint Projects Week | 12. January 2023 |18

Nuclear Safety Application (3) Containment thermal-hydraulic Hydrogen Behaviour (Combustion, Mitigation and Generation)

 Aerosol and Fission Product Behaviour
 Iodine Chemistry Experiments

S. Gupta | Nuclear Safety Research Joint Projects Week | 12. January 2023 |19

Networking – common basis on safety issues
 Stakeholders (selection)
Research centres

Industry

Universities

PSI (Switzerland), CEA (France), KAERI (Korea),
Kurchatov Inst (Russia), CIEMAT, (Spain),
CNL (Canada), IBRAE (Russia), CIAE (China), UJV(Czech Republic), FZJ & KIT (Germany)
Central Research Institute of Electric Power
Industry (CRIEPI), JapanTSOs

EDF (France), Framatome (Germany), NISSiempelkamp (Germany), Rosatom (Russia),
KHNP (Korea), NPCIL (India), CNPE (China),
CNPRI (China)

IIT (India), University of Luxembourg, RUB(Germany), Uni. Stuttgart (Germany), UPM(Spain), VKI, (Belgium)

JAEA (Japan), IRSN (France), GRS, (Germany),
KINS (Korea), Bel-V (Belgium), BARC (India), VTT(Finland), SEC NRS, Russia

Regulators
CNSC (Canada), CSN (Spain), AERB ((India), ONR(UK), UJD (Slovak Republic), SSM (Sweden), STUK(Finland) Contribution in establishing common basis on safety issues
 Analytical activities performed by project partners: pre-test assessments, result evaluations,benchmarking of codes and extrapolation of results to reactor conditions
 Collaboration on development of experimental infrastructure in countries of project partners
S. Gupta | Nuclear Safety Research Joint Projects Week | 12. January 2023 |20

Networking – competence development & maintenance Experts hosting at Becker Tech., PhDs/Post-docs, Students training (selection)

THAI
THEMIS
project

Young Scientists/Experts Competence andexpertise maintenance

Korea Atomic Energy Research Institute (KAERI): Support in designof technical scale test facilities, instrumentation/measuring systems
Atomic Energy Research Board (AERB), India: Validation of CFD
tools for hydrogen mitigation strategy in Indian PHWRs
China Institute of Atomic Energy (CIAE): Uncertainty calibration ofaerosol measurement system

PhDs/Post-Docs
Hydrogen combustion (VKI/Bel-V), Spray/Aerosols interaction (Uni
Stuttgart), Fission product re-entrainment (RUB, Bochum), Hydrogen
combustion (RUB Bochum), Aerosol washdown (KIT), Fission
product re-entrainment (University Luxembourg), etc.

Internship/Training Université de Lorraine, France
S. Gupta | Nuclear Safety Research Joint Projects Week | 12. January 2023 |21

Values Dissemination of Major Outcomes

Data of concluded joint THAI projects transferred to NEA databank for further distribution as per NEA rulesProject summary reports (CSNI approved) published in public domain
Organization of the final project seminars - generally organized one year after the project end to discuss about“reactor application” of project results by the project partners:
 OECD/NEA THAI Seminar (6 – 7 October 2010, Paris)
 OECD/NEA THAI-2 Seminar (18 – 19 November 2014, Frankfurt)
 OECD/NEA THAI-3 Seminar (6 – 8 October, 2021, Online Meeting)Providing contribution in CSNI Status/SOAR reports, WS summary reports, e.g.:
H2 management status report (2014), Iodine WS (2015), Source Term WS (2019), H2/CO SOAR
(ongoing),

Several conference and journal papers by operating agent and project partners including joint papers on
project outcomes/code benchmark results (see Appendix)
S. Gupta | Nuclear Safety Research Joint Projects Week | 12. January 2023 |22

Future R&D Needs and Trends (1/2)
 A follow-up of ongoing THEMIS project is currently under discussion
 First “informal” technical exchange meeting held on 8th November 2022 (NEA Boulogne-Billancourt) Meeting organised s a dedicated session at the 4th THEMIS PRG meeting Focus on “Large- LWRs”
 Risk informed approach should be adopted
 Scaling (not only facility size but also boundary conditions to facilitate extrapolation of results to reactor
scale)

 Focus on “LW-SMRs”
 Strong interest on LW-SMRs mainly towards “safety assessment” (support to regulators)- DBA, DEC-A, DEC-B
 Support in code benchmarks for computer modelling, V&V for SMR designs (“code validation database”)

Anticipated co-operation beyond project consortium: e.g. counter-part test, link to OECD/NEA
NEST, organization of an international code benchmark, etc
S. Gupta | Nuclear Safety Research Joint Projects Week | 12. January 2023 |23

Future R&D Needs and Trends (2/2)
Future R&D programme utilizing the
THAI experimental infrastructure
LW-SMRs safety assessment related tests
part of the ongoing national THAI project Existing experimental infrastructure employed Heat removal in large water bodies (highRayleigh number flows) - see figure Natural convection of passive heatremoval systems

Proposal for extension of the THAI test
facility-

Proposal passed technical evaluation
Presently under discussion with responsible
THAI test: 9 m highnational authorities

Proposed test facility:
SMR facility coupledwith THAI facility

containment wall simulator

S. Gupta | Nuclear Safety Research Joint Projects Week | 12. January 2023 |24

Main challenges in establishing new joint projects
Continuous evolving scenarios of nuclear power Political decisions: continuation/reduction/end of operation of nuclear power reactors
 Operation extension of current fleet of reactors – Long Term Management
 Decision on selecting new technologies like LW-SMRs, AMRs (In progress)

 Advanced technologies (LW-SMRs) - timely identification of R&D needs
 Enhanced focus on deployment needs rather on identifying R&D issues to be tackled – DBA and DEC
 Lack of “design specific” data in public domain – need of commonly agreed “generic” phenomena/BCs
 Identification/prioritization of R&D needs is important to support timely “safety assessment“Diverse range of data needs - code development/validation
 Depending on maturity of codes/models and needs as per domestically available reactor designs
 International joint activities, like PIRT & code validation matrices could pave the way for identifying “common”
R&D needs

 Optimal utilization of existing and planned experimental infrastructure with overlap in their application
 Existing facilities – critical infrastructure and the associated competence needs to be maintained Recently constructed or planned facilities – complementary design features/operation details to be utilized
S. Gupta | Nuclear Safety Research Joint Projects Week | 12. January 2023 |25

Final remarks
 THAI programme Experimental database produced within joint nuclear safety THAI projects provide valuable support forvalidation and further improvement of safety analyses codes
 Opening to other research areas (e.g. SMRs) which could be adequately addressed in the THAI
facility with eventual development of new features
 Perspectives for nuclear safety research Global approach – execution of joint projects covering different topics as per test facilities design
features but linked to an umbrella topic of common interest (e.g. SMRs)
 Inclusion of counter-part tests in joint NEA projects to better utilize capability of different test facilities
towards producing database for reactor application (e.g. scaling, differing boundary conditions) - input
for ISPs
 Mobility programs should be encouraged (e.g. OECD/NEA NEST framework) - Young scientists andexperts
 Need of implementing an effective strategy at CSNI/WGAMA, CSNI and NEA level to provide a
guidance on research priorities and strategic research needs, e.g. periodic review of NEA activities(joint projects/WSs etc.) outcomes and publishing TOPs (shorter time period than other reports, e.g.
Status/SOAR) on strategic research needs (CSNI/WGAMA level); safety technical areas for global
approach (CSNI level); consolidation of priorities between various related committees (NEA level)
S. Gupta | Nuclear Safety Research Joint Projects Week | 12. January 2023 |26

ACKNOWLEDGMENT
 The financial support by the countries participating in the OECD/NEA THAI, THAI-2, THAI-3 and theongoing THEMIS project The financial support by the German Federal Ministry for the Environment, Nature Conservation,
Nuclear Safety and Consumer Protection (BMUV) to the THAI programme

S. Gupta | Nuclear Safety Research Joint Projects Week | 12. January 2023 |27

Appendix: Project publications (selection)
Operating AgentOECD/NEA THAI Project, “Hydrogen and fission product issues relevant for containment safety assessment under severe accident conditions”, Final report,
NEA/CSNI/R(2010)3, 2010.
OECD/NEA THAI-2 Project, “Aerosol and iodine issues, and hydrogen mitigation under accidental conditions in water cooled reactors - Thermal-hydraulics, Hydrogen,Aerosols and Iodine (THAI-2) Project” - Final Report, NEA/CSNI/R(2016)8, 2016.
OECD/NEA THAI-3, “Fission product behaviour, hydrogen mitigation, and hydrogen combustion in water cooled reactors under severe accident conditions. OECD/NEA
THAI-3 Project” – Final Report NEA/CSNI/R(2021)8
S. Gupta, M. Freitag, G. Poss, THAI experimental research on hydrogen risk and source term related safety systems, Frontiers in Energy, 2021.

Project partners






L. Lebel, Z. Liang, GOTHIC simulations of OECD/NEA THAI multi-vessel hydrogen deflagration tests, Annals of Nuclear Energy,Volume 150,2021,
T. Jankowski, M. Koch, Simulation of wet resuspension phenomena during venting operation in a large scale test vessel, Proceedings of NURETH-19 conference
C. Kaltenbach, E. Laurien, CFD Simulation of aerosol particle removal by water spray in the model containment THAI, Journal of Aerosol Science,Volume 120, 2018
H. S. Kang et al , CFD Analysis for H2 Flame Propagation during Spray Operation in the THAI Facility, Trans. Of KNS. Meeting, 2015.
J. Ishikawa, H. Itoh, Y. Maruyama, Influence of adsorption of molecular iodine onto aerosols on iodine source term in severe accident , ICONE-23, 2015.

Joint publications
S. Gupta et al, Main outcomes of OECD/NEA THAI-2 project and its use for code validation and containment safety assessment under accident conditions, in-preparation for
NURETH-20 conference.
M. Freitag et al., CFD and LP code benchmark evaluating the onset of par operation in case of extremely low oxygen concentration, Nuclear Engineering and Design, Volume
400, 2022
S. Gupta et al., Main outcomes and lessons learned from THAI passive autocatalytic recombiner experimental research and related model development work”, 17th
International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-17), Xi’an, China, September 3-8, 2017.
S. Schwarz et al., Benchmark on Hydrogen Distribution in a Containment Based on the OECD-NEA THAI HM-2 Experiment, Nuclear Technology, 2011,

S. Gupta | Nuclear Safety Research Joint Projects Week | 12. January 2023 |28

SESSION 4: Joint Projects for Safety in Accidental Situations, Learnings and Perspectives

HYMERES/PANDADr Domenico PALADINO
Leader, Experimental Thermal-Hydraulics Group, Paul
Scherrer Institute, Switzerland

SESSION 4: Joint Projects for Safety in Accidental Situations, Learnings and Perspectives

WIR SCHAFFEN WISSEN – HEUTE FÜR MORGEN

Examples of Containment Thermal-Hydraulics, Mitigation Systems andHydrogen Risk Management Projects

HYMERES and PANDA projects
Domenico Paladino

NUCLEAR SAFETY RESEARCH JOINT PROJECTS WEEK
Success Stories and Opportunities for Future Development
9-13 January 2023

Outline PANDA Facility
 Overview of PANDA projects
 The HYMERES and PANDA projects
 Facility upgrading (HYMERES-2)
 Benchmark activities
 Project deliverables and publications
 Nuclear Safety Applications
 Activities within the OECD/NEST framework Feedbacks and main challenges related to the Project Development
 Outlook for future research activities Conclusions and perspectives

Page 32

PANDA facility
The PANDA facility consists of 6 Vessels RPV (Reactor Pressure Vessel), GDCS
(Gravity Driven Cooling System), DW1-2 (Drywell), WW1-2 (Wetwell), 4
Condensers (3 PCC1-3 Passive Cooling Condenser, IC - Isolation Condenser),system lines e.g. MSL (Main Steam Line), PCC vent lines, VB (Vacuum Breaker)
lines, etc. and auxiliary system lines
ESBWR versus PANDA
25 m
IC Pool

PCC Pool

PPC PoolICLarge Scale:

IC Pool

PCC

Height: 25 m

1 x IC

3 x PCC

Drywell

GDCS
Pool

VB

VB

VB
VB

Suppression
Chamber

Suppression
Chamber

Suppression
Pool

Suppression
Pool

SC

0m

RPV

Suppr.
Pool

SC

Suppr.
Pool
Ele ctr.
He ate rs

ESBWR

PANDA

Volume: 515 m3

Drywell

Scaling:
Height ~ 1 : 1
Volume ~ 1 : 40
Power ~ 1 : 40

Power: 1.5 MW.
Specifications:0-10 barup to 200 oC

G. Yadigarouglu and J. Dreier, Passive Advanced Light Water Reactor Design and the ALPHA
Programme at the Paul Scherrer Institute Kerntechnik 63 1-2 pp. 39-46, (1998).
Page 33

Overview of PANDA projects (in grey NEA)
Program

IC/PCCS

Basic
phenomena

Investigations

1991-1995 EPRI/GE

Investigation of passive decay heat removal systems for SBWR

1996-1998 EC-4th FWP

European BWR-R&D-Cluster for Innovative Passive Safety Systems(i.e. SWR1000-KERENA tests) (IPPS Project) and ESBWR (TEPSS Project)

1998-2002 OECD/NEA
ISP-42

Passive Containment Cooling System (PCCS) performance in very challenging
situations, represented in six different phases (ISP-42)

1999-2004 EC-5th FWP

Effect of hydrogen distribution on passive systems (TEMPEST Project) andinvestigation of BWR natural circulation stability (NACUSP Project), ESBWR

2002-2006 OECD/NEA

Gas mixing and distribution in LWR containments (SETH Project)

2007-2010 OECD/NEA

Resolving LWR containment key computational issues (SETH-2 Project)

2010-2014 EU 7th FWP

Containment thermal-hydraulics of current and future LWRs for severe-accident
management (ERCOSAM-SAMARA Project)

2012-2013 Swissnuclear

Experimental program on Spent Fuel Pool

2012-2014 OECD/NEA

PANDA benchmark (CFD4NRS-5)

2013-2016 OECD/NEA

To resolve complex safety issues for the analysis and mitigation of a severe accident
leading to hydrogen release into a nuclear containment (HYMERES Phase 1 project)+pool

2017-2021 OECD/NEA+SMRs

2021-2025 OECD/NEA

To resolve complex safety relevant issues for the analysis and mitigation of asevere accident leading to hydrogen release into a nuclear plant containmentand suppression pressure pool system issues (HYMERES Phase 2 project)
PANDA experiments addressing complex safety issues for current water reactors
and small modular reactors (SMRs) (PANDA project)

The HYMERES and PANDA projects
OECD/NEA HYMERES (Phases 1 and 2) joint projects
The experiments addressed:
 Hydrogen distribution on
configuration with jet impacting plates
or grating platforms,
 Hydrogen distribution under theeffect of activation of safety
components e.g. spray, coolers, heatsources Thermal radiation effect onhydrogen distribution
 Pressure suppression pool
phenomena
PANDA rendering
Page 35

The HYMERES and PANDA projects (2)OECD/NEA PANDA project: PANDA experiments addressing complex safetyissues for current water reactors and small modular reactors
Topic 1: Extend the database at large scale on flow interacting withcontainment internal structures and on thermal radiation
Steam generator
compartment model

P1A1 Jets or plumes impacting complex compartments

Complex conditions
P1A2 Radiative heat transfer
Topic 2: Extend the database on activation of PWR containment spray system

Two steam generator
compartment

P1A3 Complex connected compartments and spray
Topic 3: Small Modular Reactor (SMR) system tests
P1A4 Passive Containment Cooling System (PCCS)
P1A5

System tests

PANDA tests addressing natural convection heat transfer (HT)from the external wall of the containment to the water pool

Natural convection atlarge scale

Topic 4: Extend the database on suppression pool of BWR(and IRWST of PWR )P1A6

Various scenarios with/without containment pressurization /depressurization and with/without the interplay of containment
compartments

Number of PANDA nominal tests:

Component andsystem tests

24

The HYMERES and PANDA projects (3) OECD/NEA PANDA project: PANDA experiments addressing complex
safety issues for current water reactors and small modular reactorsPeriod: July 2021-June 2025
Organizations: 12 Organizations from
9 Countries: Canada, Finland, France,
Germany, Korea, Spain, Sweden, USA,
Switzerland
Synergies:
 THAI experiments related to the
SMRs; EURATOM SASPAM-SA (Safety
Analyses of SMR with Passive
Mitigation strategies - Severe
Accident) Horizon Euratom Project; ATLAS-CUBE containment spray

3rd PRG and MB meeting was held at PSI on
the 2-3 November 2022
Page 37

Facility upgrading (HYMERES-2)
PANDA Upgrading: the main upgrading were related to:DAS, Control Systems, Instrumentation, new components:
 H2P1 series: Flow obstructions such as plates and grating platforms;
injection lines.
 H2P2, H2P5, H2P6 series: cover plate (10 bar specifications) to close
the Vessel 1-Vessel 2 interconnecting pipe.
 H2P2 series: new helium line and flow obstruction-flow diffuser.
Flow Obstruction

Flow velocities measured with PIV above theflow obstruction

Vessel 2

H2P1_1Page 38

Facility upgrading (HYMERES-2)
PANDA Upgrading: the main upgrading were related to:DAS, Control Systems, Instrumentation, new components:
 H2P3 series: sparger and sparger feeding pipe tolocate the sparger a different radial positions),
calibration targets for 2D/3D PIV.
 H2P4 series: sparger and sparger feeding pipes tolocate the sparger at different elevations; spraynozzle and spray feeding line; covering plate for
the Vessel 3 – Vessel 4 interconnecting pipes.

Vessel 1

Vessel 2

Vessel 3

Vessel 4

H2P3 and H2P4 series

Page 39

Facility upgrading (HYMERES-2)
PANDA Upgrading: the main upgrading were related to: H2P5 series: spray systems (one spray nozzle and nine spray nozzles configurations)and spray feeding line
 H2P6 series: cooler systems (one cooler and three coolers configurations) andcooler feeding/return lines.
Cooler arrays

Spray testing

3 D rendering

H2P5
series

H2P6 series
Page 40

Benchmark activities
 The analytical activities are carried out by the Operating Agent and by the Project
Participants:
 LP, CFD or CFD type codes are used, depending also by test characteristics
Scoping analyses (to design the experiments and to define instrumentation layouts, toidentify the test initial and boundary conditions (IBC))
Pre –test analyses (based on the final test configuration and nominal IBC
Post –test analyses (based on the actual IBC)
Benchmark analyses (blind and open phases to compare modeling, code and user effects)
Basic phenomena in an empty
multi-compartment containment
OECD/NEA SETH
buoyant Jet/plume;
Stratification build-up
Benchmark: Tests 9-17 (EU ECORA)

OECD/NEA SETH-2
Negative buoyant Jet/plume
Erosion of stratification
Benchmarks: ST1_7, CFD4NRS

Basic phenomena in a
multi-compartment containment with obstructions
OECD/NEA HYMERES phase 1
Horizontal/vertical plates
Benchmark: HP1_6

OECD/NEA HYMERES phase 2
Inclined grid
Benchmark: H2P1_10_2
Page 41

Project deliverables and publications
Re=10000 Project deliverables and publications:
The PANDA experimental data and technicalreports (project deliverables) are distributed to
the NEA and to the project participants Analytical workshops (AW) are organizedback to back with most of the PRG meetings,
the experiments are analyzed with a variety
of tools, e.g. LP, CFD (commercial; open
source solvers), NEK5000.
 Dissemination of Project Outcomes to the
Scientific Community:
The main outcomes from the experimental
program and from the analytical activities are
published by the Operating Agent and/or the
project participants in journal articles andconference papers

H2P1_17 and H2P1_15
Analyzed with NEK5000

Page 42

Nuclear Safety Applications
 The approach is first to assess and validate computational models against PANDA
experiments and then use the experience gained during the validation process toanalyze postulated accident scenario in real nuclear power plants
 Experiments/Analyses were made, e.g. related to two-room type containment,
and as well to other containment types
Example of PWR applications

Two-room type containment

OECD/NEA HYMERES phase 1 PANDA HP6 series
Page 43

Nuclear Safety Applications (2)Example of BWR applications
The PANDA experiments investigated the effect of thermal stratification phenomenain the suppression pool of BWRs on the containment pressurization
Test H2P4_2:
Sparger submergence: 1.2 m

Test H2P4_3:
Sparger submergence: 0.5 m

OECD/NEA HYMERES-2 project (H2P3 and H2P4 series)

Activities within the OECD/NEST framework
Nuclear Education, Skills and Technology (NEST) Framework
 NEST promotes the mobility of Fellows (MSc, PhD, Post-doctoral)
 Research activities are carried out by each Fellow in one or more Institutions

https://www.oecd-nea.org/jcms/pl_24321/nest-hymeres
 The objectives of the NEST Fellows activities are to: Contribute with computational analyses to the definition of PANDA tests and to
identify the optimal configurations to reach the objectives of the individual series
 Gain insight into the computational modelling needs to represent containment
phenomena in compartments or structures or also related to SMRs
 Develop methodologies for processing the experimental data which enhance theunderstanding of phenomena during specific tests
 Perform complementary experiments in small and medium scale facility (at PSI andalso in other Institutions) which provide a broader understanding of thephenomena investigated in the project

Page 45

Feedbacks and Main Challenges related to
the Project Development
To maintain large facility in operation ideally there should be time
continuity between project phases
The research topics for the new project should be identified one to
two years before the end of a running projectHowever, usually the research needs are identified as results of theresearch activities and therefore it is challenge to identify them
before the end of running projects
Project opportunities may come out of on-going WGAMA activities
Synergies with other projects (OECD/NEA) or projects in otherframeworks (National, EURATOM, IAEA) whenever possible, can leadto cross-activities of mutual interest (e.g. benchmarks, etc.)
Involvement of NEST Fellows in experimental and/or computational
activities are highly beneficial.
Page 46

Outlook for future research activities
Foreseen follow-up, i.e. OECD/NEA PANDA-2 (2025-2029):
Research investigations in PANDA for:
BWR: suppression pool phenomena, integral test, interaction ofsafety systems and compartments
PWR: containment safety systems (active and passive),
representation of steam generator towers
SMR: phenomena of interest for BWR and PWR SMRs, passive
safety systems and interaction of primary and secondary circuit
Experimental data to be suitable for CFD codes, LP and System
codes
Counter-part/complementary experiments in other experimental
facilities (scaling effects) at PSI and/or in other Institutions
Synergies for defining selected experiments and benchmarks withother OECD/NEA Joint projects and EURATOM projects
Page 47

Conclusions and perspectives
 PANDA projects within the OECD/NEA framework allowed the creationof unique experimental database on containment phenomena withsafety relevance The PANDA experiments have been analyzed over the years to assess avariety of computational tools and this has contributed to advance theknowledge on containment phenomena and on the modeling needs
 In perspective we foreseen that PANDA will be operated for system
and integral tests for BWRs, PWRs, SMRs, with configurations requiring
more compartments/vessels (RPV, DW, IC/PCC)

 Synergies and sharing information with other OECD/NEA joint projects
and with projects in other framework (i.e. EURATOM, IAEA), wheneverpossible, will be beneficial for defining the new experiments andcomputational analyses
Page 48

Wir schaffen Wissen – heute für morgen
PANDA

Page 49

Session 4
Joint Projects for Safety in Operation, Learnings andJoint Projects for Safety in Accidental Situations,Learnings and Perspectives► Example of an Accident Progression and Melt
Coolability In-Vessel and Ex-Vessel Project

SESSION 4: Joint Projects for Safety in Accidental Situations, Learnings and Perspectives

ROSAU

Dr Jeremy LICHT

Nuclear Engineer, Principal Investigator for the ROSAU Project,
Argonne National Laboratory, United States

SESSION 4: Joint Projects for Safety in Accidental Situations, Learnings and Perspectives

Example of an Accident Progression and Melt
Coolability In-Vessel and Ex-Vessel Project

ROSAU
erhtjhtyhy

JEREMY LICHT (jlicht@anl.gov)
Nuclear Science & Engineering Division
Argonne National laboratory

OUTLINE
1. Overview of ROSAU Project
2. Main Outcomes and Benefits
3. Feedback on Main Challenges
4. Insights on Future R&D
5. Conclusion

54

OVERVIEW OF ROSAU PROJECT (1/2)
OECD/NEA Reduction of Severe Accident Uncertainties (ROSAU)International Joint ProjectHigh level program objective:
 Reduce uncertainties in ex-vessel core melt progression
and melt coolability by providing data to validate codes,
aid in the Fukushima decommissioning efforts, andbetter inform severe accident management– Operating Agent: US NRC under the auspices of OECD/NEA– Performing Lab: Argonne National Laboratory– Participants: 20 Organizations from 8 countries– Duration: September 2019 - 2024

55

OVERVIEW OF ROSAU PROJECT (2/2)
Two test programs are being carried out to meet program objectives:
Melt spreading: Address uncertainties in Debris coolability: Fill data gaps regarding
the nature and extent of under water coolability and H2 production for prototypic
spreading of prototypic core debris and melts containing metal content for both inprovide data for validating severe vessel and ex-vessel conditions
accident codes

56

FACILITIES AND COMPETENCIES (1/2)

MST

The ROSAU project has provided the opportunity torefine existing experiment facilities and to develop new
experiment capabilities to address new phenomena
 The Melt Spreading Test (MST) facility
has been newly developed to, for the first time, investigate at large scale
the extent and nature of prototypic core debris spreading under water.
 The Debris Coolability and MCCI(DCAM) facility
has been ungraded to provide
measurements of hydrogen
evolution and aerosol scrubbing
during debris quench of prototypic
reactor materials.

Spreading
Channel

Heat

DCAM

Exchanger
HX

Condensation
Tank
CT

Reaction
RV
Vessel
Vent
Tank
VT

Reaction
Vessel57

FACILITIES AND COMPETENCIES (2/2)
Competencies developed among the project staff in theareas of design, fabrication, operation, datainterpretation, and modeling related to large-scale,
high-temperature prototypic corium compositions
 Thermite development and testing for high temperature
corium generation (containing UOx-ZrOx, Fe/Zr/Cr metals,
and concrete constituents)

 Development and experience with new measurement
techniques (hydrogen, aerosols, debris morphology, hightemperature melts)
 Code use and model development (e.g. COREQUENCH
and MELTSPREAD)
 Engaged university student in the development of tools forpost-test examination.

 Knowledge transfer among ANL staff and project partners
58

NUCLEAR SAFETY APPLICATIONS (1/2)
 Knowledge gaps exist in ex-vessel melt progression and coolability;
important gaps include lack of MCCI data with melt compositions
containing unoxidized metal and data on melt spreading under water Resulting uncertainties in debris cooling by water can be significant, andthe efficacy of current severe accident management actions may not beadequate
 ROSAU data will contribute to reduction of uncertainties in ex-vessel
melt coolability and enhancement of severe accident management
actions
59

NUCLEAR SAFETY APPLICATIONS (2/2)
 Results from ROSAU tests with prototypic metal-oxide melt compositions
would support in-vessel core recovery actions involving core reflood Results from ROSAU tests with concrete-rich melt compositions would
support investigation of long-term* debris coolability
 Existing melt spreading database is practically void of underwater
spreading of prototypic core melt; results from ROSAU melt spreading
tests would support development of improved melt spreading model(s)for incorporation into severe accident analysis codes*(hours to tens of hours)
60

NETWORKING (1/1)
 Various stakeholders are participating in the ROSAU project.
– Regulators: NRC (USA; also the project Operating Agent), NRA (Japan), SSM (Sweden)– TSO: Bel V (Belgium), IRSN (France), KINS (Korea)– Research Institutions/Labs: CNL (Canada), CEA (France), UJV (Czech Republic), KAERI (S.
Korea), JAEA & AdvanceSoft (Japan), KTH (Sweden), ANL (USA)– Industry: Tractebel (Belgium), EdF (France), KEPCO & KHNP (Korea), TEPCO (Japan), EPRI (USA) Method for establishing a common basis for test program definition and resolutionof safety issues– Active development of models for new phenomena and validation against test data.
– Pre- and posttest analysis activities conducted by project participants– Specifications for each test are arrived at by consensus decision from project participants.

 In-kind contributions among partners, for example:– Experiment and modeling work performed at KTH– Supporting analyses (e.g., thermodynamic database evaluations by UJV and IRSN)
61

VALUES (1/1)
 Transfer of Data to NEA Data Bank
– ROSAU project is nearly halfway in the project milestones;• Debris Coolability and MCCI (DCAM): 3 tests completed, 2 tests remaining;• Melt Spreading Tests (MST): 1 test completed (commissioning), 1 test immanent, 4 tests remaining– All information (reports, data, videos) currently archived at ANL• Discussions underway to define transfer to the NEA data bank by end of project Reporting of Project Outcomes– Prepared reports for all completed experiments; reports are disseminated to project partners throughdedicated OECD/NEA ROSAU website– Project outcomes reported at PRG meetings held every six months; presentations and otherdocumentations archived in the ROSAU website– Published a technical paper at the ANS Proceedings; present progress at the annual CSARP
technical meetings (Cooperative Severe Accident Research Program) Distribution of updated codes, such as MELTSPREAD and COREQUENCH
62

FEEDBACK ON MAIN CHALLENGES (1/2)
 Dynamic Nature of Project Scope– ROSAU included both the refurbishment of a previous experiment (DCAM) and development of a
new experiment (MST), which is not typical of other projects– ROSAU test matrices (for DCAM and MST) have been continually evolving throughout the project– Changes are the result of:• Competing needs and priorities of partner organizations, which are also evolutionary in nature• Lessons learned from the completed experiments and recalibrating the remaining experiments
accordingly• Ongoing discussions about what is or is not technically feasible from an experiment capability
perspective– These changes, whether implemented or not, can impact both schedule and budget; should be
accounted for before the project starts

 Partner engagement– More analyses by partners are needed to exercise data and identify modeling/code deficiencies,
including engagement on development of model improvements
63

FEEDBACK ON MAIN CHALLENGES (2/2)
 Budget and Schedule– Challenges of an OECD/NEA project:• Approved budget was less than funding needed to execute the full ROSAU scope(Late decision by some participants to not join project)• Discrepancy in the project start time (agreement signatures vs. funding available to start work)• Actual time for participant funds to reach performing lab can be significant• Differences/irregularities in participant funding cycles difficult to accommodate (including exchange
rate)– Challenges due to COVID-19:• The COVID-19 pandemic occurred ~9 months after the start of ROSAU• Time and effort needed to restart limited and normal operations at ANL• Fabrication delays as well as shop outages due to COVID-19 outbreaks• Acquisition of equipment and instrumentation significantly delayed• Project meetings held by remote video conferencing (typically 4 hrs in duration maximum) rather thanmultiple day, in-person interactions
64

INSIGHTS ON FUTURE R&D NEEDS & TRENDS (1/2)
 Trends in ROSAU– Valuable insights gained from the 4 completed MST and DCAM experiments and it should beassumed the same will be true for remaining 7 experiments.
– Already identified needs for model developments and improvements in both the MELTSPREAD and
COREQUENCH codes Trends in Future Reactor Designs– Advanced reactor concepts have gained considerable ground in recent years; among the leading
design candidates for commercialization are: LWR SMR varieties, LMRs and others– Some designs reportedly have the options of employing both conventional fuels and accident
tolerant fuels

65

INSIGHTS ON FUTURE R&D NEEDS & TRENDS (2/2)
 Future R&D Needs– For ROSAU, the number of DCAM and MST experiments that could contribute to reduction ofsevere accident uncertainties potentially far exceeds what is possible in the current ROSAU project– For advanced designs, coupled with advanced fuel types, these may require same or similar type ofconfirmatory investigations as required for the conventional designs and fuel types

 Role of ANL facility to meet the future R&D Needs– With minimal changes, ANL facilities can be utilized to perform:• Additional experiments related to scope identified in the current ROSAU project,• Perform new types of experiments related to advanced designs, e.g., investigating the SA
performance of FeCrAl type cladding materials– The ANL team and experimental facilities supporting ROSAU will be fully mature at the conclusionof the current program; preserving these capabilities will be beneficial to the SA community

66

CONCLUSIONS The ROSAU project is successful in developing / maintaining critical facilities andcompetencies of project partners and generating data needed for code development andvalidation useful to project partners in– Informing severe accident management and mitigation– Confirming needs for improved material properties data (e.g., TCOFF and proposed COPS projects)

 However, the budget shortfall, in combination with the COVID-19 pandemic, constrains thebenefits that could be realized for ROSAU project partners:– Reduced scope to accommodate budget shortfall and COVID-19 delays– Funding (magnitude and frequency) insufficient to cover ANL staff needed to perform this work and inadequate for
maximizing knowledge transfer opportunities With nuclear reactors being phased out in some countries, the burden to keep facilities andrelated expertise falls on fewer partners.
– However, with greater emphasis on reducing carbon footprint, there is a renewed interest in nuclear energy which
provides hope that a healthy research program will be maintained in the future

 Similar SA work related to advanced reactors yet to be realized at ANL
67

THANK YOU FOR LISTENING!

Session 4
Joint Projects for Safety in Operation, Learnings andJoint Projects for Safety in Accidental Situations,Learnings and Perspectives►

Example of a Source Term Project

SESSION 4: Joint Projects for Safety in Accidental Situations, Learnings and Perspectives

STEM/ESTERMr Christophe MARQUIE

Deputy Head of the Experimental Department, Institut deRadioprotection et de Sûreté Nucléaire (IRSN), FranceSESSION 4: Joint Projects for Safety in Accidental Situations, Learnings and Perspectives

CSNI STEM/ESTER PROJECTSIRSN/FRM-296 ind. 07

Nuclear Safety Research Joint Projects Week

Source Term R&D[ CONTEXT▌ Knowing radioactive releases during a Severe Accident is ofparamount importance to assess the consequences of such
accident and to support public authority decisions (population
displacements, distribution of stable iodine pills).
▌ At the end of 1980’s, IRSN launched the international PHEBUS

FP program to study the full sequence of a SA from the fueldegradation to fission products (FP) transport.
▌ Concerning FP, PHEBUS tests evidenced large discrepancies

between calculations and experimental results.
▌ A large international effort to better understand PHEBUS

results (and later Fuskushima Daiichi observations) with thesupport of OECD/NEA or EU : ISTP, PASSAM, BSAF, THAI, BIP,
STEM, ESTER… + expert meetings, PIRTs, workshops…
STEM/ESTER PROJECTS - OECD/NEA - NUCLEAR SAFETY RESEARCH JOINT PROJECTS WEEK73

STEM/STEM-2 Projects (Source Term Evaluation and Mitigation)[ IDENTITY CARD
▌ STEM : 2011-2015
 Operating Agent : IRSN Partners : CNL (Canada), UJV (Check Republic), VTT (Finland), EDF (France), GRS (Germany), KINS andKAERI (South Korea), NRC (USA) Budget : 3,5 M€
 Main Objective : iodine behavior (iodine/paint interactions) under radiation in containment +ruthenium chemistry and transport in RCS in oxidative conditions▌ STEM-2 : Follow-up of STEM (initiated after 2015 NEA iodine workshop)

 2016-2019
 Operating Agent : IRSN Partners : CNL (Canada), VTT (Finland), EDF (France), GRS (Germany), NRA (Japan), KINS and KAERI(South Korea), NNL (UK), SSM(Sweden), NRC (USA) Budget : 2,5 M€
 Main Objective : iodine behavior (paint ageing and iodine aerosol stability) under radiation incontainment + ruthenium chemistry and transport in RCS in oxidative conditions
STEM/ESTER PROJETS - OECD/NEA - NUCLEAR SAFETY RESEARCH JOINT PROJECTS WEEK74

STEM/STEM-2 Projects[ MAIN SCIENTIFIC OUTCOMES▌ Data for enhancing models calculating formation and transportation of iodine and ruthenium species▌ Data /models implemented in SA code (ASTEC) which result in better calculation of iodine volatile

fractions in experiments and release in real accidents▌ BUT :
▌ Still underestimation of I-Org formation by an order of magnitude for PHEBUS tests▌ Poor calculation of long-term Cs releases during the Fukushima Daiichi accident (BSAF-2 project)▌ Both justified the need of a new project: ESTER

STEM/ESTER PROJETS - OECD/NEA - NUCLEAR SAFETY RESEARCH JOINT PROJECTS WEEK75

ESTER Project (Experiments on Source Term for delayed Releases)[ IDENTITY CARD

▌ ESTER : 2020-2024 (initiated after 2020 NEA Source Term Workshop) Operating Agent : IRSN with some experiments performed by CEA
 Partners : VTT (Finland), CEA and EDF (France), GRS (Germany), NRA and JAEA (Japan), KINS (South

Korea), SSM (Sweden), NRC (USA) Budget : 3,14 M€
 Main objective : chemical remobilization of FP deposits in the RCS and other sources of formation oforganic iodides than interaction with paints

STEM/ESTER PROJETS - OECD/NEA - NUCLEAR SAFETY RESEARCH JOINT PROJECTS WEEK76

Status of ESTER Project▌ Concerning formation of organic iodides under radiation (5 tests performed – 2 remaining to be

performed in 2023), tests showed a limited influence of Volatile Organic Compounds
 A strong effect of carbon “pollution” of SS surfaces▌ Concerning revaporization of FPs deposits in the RCS

 PhD on analytical tests is completed: conditions of CsI, CdI2 and Te revaporization were identified
 1st semi-analytical tests planned in January 2023 : deposition phase (early stage of the accident) in

the primary circuit and then revaporization phase due to change of environmental conditions
planned Confirmatory tests with prototypic deposits planned in April 2023

STEM/ESTER PROJETS - OECD/NEA - NUCLEAR SAFETY RESEARCH JOINT PROJECTS WEEK

77

STEM/ESTER Projects[ SUPPORT TO DEVELOP, UPGRADE AND MAINTAIN UNIQUE EXPERIMENTAL PLATFORMCONSIDERED AS “STRATEGIC” FACILITIES BY OECD/NEA SESAR GROUP FOR NUCLEAR SAFETY RESEARCH▌ START TGT▌ EPICUR g-irradiator + LEAR hot-Lab

STEM/ESTER PROJETS - OECD/NEA - NUCLEAR SAFETY RESEARCH JOINT PROJECTS WEEK

78

STEM/ESTER Projects[ SUPPORT TO DEVELOP NUMERICAL CODE
▌ In each STEM/ESTER project, analytical activities were conducted in a dedicated working group :benchmarks with ASTEC (VTT/IRSN), COCSYS (GRS), RAIM (KINS), INSPAIR(NNL) codes▌ They allow to :

 develop and validate models

 to exchange “good practices” between partners
 To identify lack of knowledge/discrepancy with experiences (like PHEBUS FP tests) or real accident(like Fukushima-Daiichi) and then reorient experimentation and research effort▌ Common recommendations were reached with BIP-3 AWG

STEM/ESTER PROJETS - OECD/NEA - NUCLEAR SAFETY RESEARCH JOINT PROJECTS WEEK79

STEM/ESTER Projects[ SUPPORT TO COMMUNITY AND DISSEMINATION OF KNOWLEDGE▌ Project data are transferred to the NEA data bank at the end of the “embargo” (3 years) period andavailable to NEA members▌ In connection with other projects, workshop were organized to assess knowledge status and need for

new research like the NEA 2020 workshop on Source Term
▌ Journal and conference papers have been published based on projects results : at least 12 for STEM

and 13 for STEM-2

STEM/ESTER PROJETS - OECD/NEA - NUCLEAR SAFETY RESEARCH JOINT PROJECTS WEEK

80

Complementarity with other projects[ EXAMPLE : OECD/NEA THAI/THEMIS PROJECTS▌ THAI/THEMIS (Becker Technologies) projects have addressed hydrogen (PAR, mixing …) and ST issues▌ On ST topic, both facilities are complementary

 THAI facility (big containment) can cover some issues relative to aerosol physics, pool-scrubbing or

coupling H2 deflagration/iodine behaviour for instance CHROMIA IRSN platform is focused on high temperature PFs behaviour (RCS), radiation effects andchemical effects not depending on the scale effect.
 For instance, for iodine oxides, nucleation was studied in THAI and chemical stability in CHROMIA[ OTHER INTERNATIONAL PROJECTS : OECD/NEA BIP, EU PASSAM, ISTP...

STEM/ESTER PROJETS - OECD/NEA - NUCLEAR SAFETY RESEARCH JOINT PROJECTS WEEK

81

STEM/STEM-2/ESTER Projects[ MAIN CHALLENGES▌ Difficulties to find partners for ESTER project:

 Scientific interest is present (see 2020 NEA ST Workshop) but economic constraints from partners
 Geopolitical considerations : e.g. Russian participation was planned but stopped with war with

Ukraine reduced participation from former projects (STEM/STEM-2): hence a slight reduction of the program▌ Technical challenges linked to complex test devices : Retrofit of CHIP facility
 Preparation of tests on VERDON samples …
▌ Indirect geopolitics impact on the project: Russian war led to difficulties to import 60Co for the EPICUR

irradiator (solved)▌ OECD/NEA Agreement was rather a smooth process

STEM/ESTER PROJETS - OECD/NEA - NUCLEAR SAFETY RESEARCH JOINT PROJECTS WEEK

82

STEM/STEM-2/ESTER Projects[ CONCLUSIONS▌ Fruitful projects that lead to improve understanding, knowledge of source term in case of SA within aninternational frame▌ Development and validation of models in the ASTEC code – benchmarks within the AWGs
▌ “Closed” item : Ru transport under LWR SA conditions▌ Nearly “closed” item on Iodine behavior but still needs to understand/quantify different ways oforganic iodide formation and delayed FPs releases = aim of the ESTER project.

STEM/ESTER PROJETS - OECD/NEA - NUCLEAR SAFETY RESEARCH JOINT PROJECTS WEEK

83

STEM/STEM-2/ESTER Projects[ INSIGHT ON FUTURE R&D NEEDS AND TRENDS▌ No clear view today of a follow up to the ESTER project (still more than 2 years in the project)▌ General context toward a decrease of effort concerning SA research▌ Trends for IRSN with ST issue are focused mainly on (subject to be or under discussion with partners) : ATF fuel (impact of Cr…),
 SMR (specificities like impact of inert gas injection, larger ratio of metallic surfaces…)
 “liquid ST” (long term operations with lixiviation of corium and evolution of solution /decontamination of water) – a project will be proposed within next EU call (VTT lead) on Cs

STEM/ESTER PROJETS - OECD/NEA - NUCLEAR SAFETY RESEARCH JOINT PROJECTS WEEK84

Panel SESSION 4: Joint Projects for Safety in Accidental Situations, Learnings and Perspectives

Dr Sanjeev
GUPTA

Dr Domenico
PALADINO

Mr Christophe
MARQUIE

Deputy General
Manager, Head ofReactor Safety &Engineering, Becker
Technologies,
Germany

Leader,Experimental
Thermal-Hydraulics
Group, Paul
Scherrer Institute,
Switzerland

Deputy Head of the Nuclear Engineer,
Principal Investigator
Experimental
for the ROSAU
Department,
Project, Argonne
Institut deRadioprotection et National Laboratory,
United Statesde Sûreté
Nucléaire (IRSN),FranceDr Jeremy
LICHT

Dr Katharina
STUMMEYER

Dr Won-Pil
BAEK

Head of Division ProjectManagement Agency,
Gesellschaft für Anlagenund Reaktorsicherheit(GRS), Germany

Senior Research
Fellow, Korea
Atomic Energy
Research Institute(KAERI), Presidentof Korean Nuclear
Society, Korea

Panel SESSION 4: Joint Projects for Safety in Accidental Situations, Learnings and Perspectives

Dr Katharina STUMMEYER

Head of Division Project Management Agency, Gesellschaft für
Anlagen- und Reaktorsicherheit (GRS), Germany

Panel SESSION 4: Joint Projects for Safety in Accidental Situations, Learnings and Perspectives

Panel SESSION 4: Joint Projects for Safety in Accidental Situations, Learnings and Perspectives

Dr Won-Pil BAEK

Senior Research Fellow, Korea Atomic Energy Research Institute(KAERI), President of Korean Nuclear Society, Korea

Panel SESSION 4: Joint Projects for Safety in Accidental Situations, Learnings and Perspectives

NEA NUCLEAR SAFETY RESEARCH JOINT PROJECTS WEEK:
Success Stories and Opportunities for Future Developments
9-13 January 2023

Thank you for your participation today and see you all tomorrow!

Questions, feedback and suggestions
Event public page: Nuclear Energy Agency (NEA) - NEA Nuclear Safety Research Joint
Projects Week: Success Stories and Opportunities for Future Developments (oecdnea.org)