第40回原子力委員会
資料第3号

上坂原子力委員会委員長の海外出張について
令和４年１０月１１日

１．出張先
オーストリア共和国（ウィーン）
２．出張期間
令和４年１０月１６日（日）～２２日（土）３．渡航目的
ウィーンで開催されるＩＡＥＡのカンファレンス「２０２２International Conference on Topical Issues in Nuclear
Installation Safety:Strengthening Safety of Evolutionary andInnovative Reactor Designs」のパネルディスカッションに登壇するとともに、ＩＡＥＡの幹部との意見交換を行う。
４．主要日程１０月１６日（日）東京発
１７日（月）ヘルシンキ着ヘルシンキ発→ ウィーン着
１８日（火）～２１日（金）２０２２ＴＩＣ会合出席、バイ会談。
２１日（金）ウィーン発 →

パリ着

パリ発
２２日（土）東京着

以 上

INTERNATIONAL CONFERENCE ON TOPICAL ISSUES IN NUCLEAR
INSTALLATION SAFETY:
STRENGTHENING SAFETY OF EVOLUTIONARY AND INNOVATIVEREACTOR DESIGNS (TIC2022)
18 October 2022
11:00-13:00
Plenary session #1
Panel discussion“Towards harmonization of safety approaches: regulatory and industry perspectives”
Moderator
Ms Anna Bradford, DIR-NSNI, IAEA
Invited speakers
Speaker
Rumina VELSHI

Organisation
CNSC

Country
CanadaSylvie CADET-MERCIER
Mitsuru UESAKA

ASN
JAEC

FranceJapan

Jon BALL

GE-HITACHIUSA

Sama BILBAO Y LEÓNWNA

Session structure••••

Opening remarks (A. Bradford)
Brief speeches by invited speakers (7-10min)
Proposed questions for the panel discussion
Q&A session with the audience (if time allows)

Title of the speech
The CNSC and the Road to Harmonization: A
Plan in Action
EU Initiatives in SMR Licensing
Harmonized Power/Non-Power Applications of
Innovative Reactors
BWRX-300: Design, Licensing, and Commercial
Progress
Supporting a New Paradigm for Reactor Design
LicensingINTERNATIONAL CONFERENCE ON TOPICAL ISSUES IN NUCLEAR INSTALLATION SAFETY:
STRENGTHENING SAFETY OF EVOLUTIONARY AND INNOVATIVE REACTOR DESIGNS (TIC2022)
18–21 October 2022, Vienna

CONFERENCE PROGRAM (draft)
DATE

TIME
8:00 – 9:30
9:30 – 10:30

SESSIONS
Parallel Session 1
Registration of participants
Opening session

Parallel Session 2

Parallel Session 4

Coffee break
Plenary session #1:
Panel discussion “Towards harmonization: regulatory and industry perspectives”
Lunch break

10:30 – 11:00
11:00 – 13:00
13:00 - 14:00
Regulatory & Licensing

18 OCT 2022

Parallel Session 3

WENRA, Gisela Stoppa – WENRA safety objectives for Gen 3
plants and their applicability to SMRs
ID 197, Raoul Awad; Al Falahi Rashid (ARE) – Innovative
regulatory approach for licensing a new nuclear power plant
ID 111, Fidel Llizastigui (CUB) – Developing competence of
new regulators to tackle SMRs
14:00 – 15:30
ID 125, Badawy Elsheikh (EGY) – Regulatory challenges andlicensing efforts for innovative molten salt reactors

Design Safety Features

Safety Demonstration

Simulation & Modelling

ID 121, Jing Liu (CHN) – Research on heat pipe
conduction device of containment dome
ID 122, Maithah Alaleeli (ARE) – Material
performance metrics for accident tolerant fuelcladding in pressurised water reactors
ID 26, Evgeny Vlasenko (RUS) – Development of thefirst Russian research molten salt reactor fortechnology trial of minor actinides burning. Nuclear
safety features
ID 119, Kai Wang (CHN) – Application of passive cold
source system in nuclear power plant design

ID 30, Wayne Boyes (ZAF) – A comprehensive thermohydraulic neutronic and safety analysis of a 100mwth
pebble bed reactor core
ID 112, Robert Youngblood (USA) – Application of
objectives-driven assurance cases to system development
in an evolving acquisition model
ID 115, Chen hui Wang (CHN) – Internal flooding safetyassessment of small reactor (ACP100) based on advanced
3D simulation software (CNIFA)ID 196, David Holcomb (USA) – Steps towards efficiently
demonstrating adequate MSR safety

ID 104, Walter Klein-Hessling (DEU) – Regulatory perspectives
on analytical codes and methods for advanced reactors
ID 35, Sanjeev Gupta, Ahmed Bentaib (DEU) – IAEA simulationand experimental analyses network information system(SANIS) database: severe accidents experimental facilities,
codes and education and training tools
ID 56, Sergey Shevchenko (RUS) – The Russian approach to theregulatory review of computer programs used for multiphysics modelling and safety analysis of innovative nuclear
installations
ID 28, Ahmed Bentaib (OECD, IRSN) – The OECD/NEA working
group on the analysis and management of accidents(WGAMA): Advances in codes and analyses to support safety
demonstration of nuclear technology innovations

Coffee break

15:30 – 16:00
International Collaboration & Harmonization
IAEA, Paula Calle-Vives (IAEA, NSNI) – NHSI update:
Regulatory track
IAEA, Stefano Monti (IAEA, NENP) – NHSI update: Industrytrack
ID 88, Donna Williams (USA) – U.S. and Canada cooperation
16:00 – 18:00 on advanced reactor technologies - progress and challenges
ID 109, Allan Carson (WNA) – Collaboration – the key tostreamlining nuclear regulation

Design Safety Features

Safety Demonstration

Simulation & Modelling

ID 29, Wayne Boyes (ZAF) – Advanced Micro Reactor(AMR)
ID 40, John Eldridge (GBR) - U-Battery enhancing
safety through innovative design
ID 131, Junichi Takeuchi (JPN) – Development of MHI
integrated small reactor
ID 144, Cory Stansbury (USA) – An Integrated design
approach to address safety of the Westinghouse LFR:
An Innovative pool-type, liquid lead-cooled fast
reactor

ID 124, Luca Ammirabile (E.C) – GIF integrated safetyassessment methodology (ISAM) and guidance for its
implementation for novel advanced reactors
ID 52, Sebastian Buchholz (DEU) – Potential gaps in safety
demonstration methods for LW-SMR identified in the
ELSMOR project
ID 73, Zoltan Hozer (OECD) – Advances in knowledge,
modelling and methods to support safety demonstrationof conventional and advanced nuclear fuels in the
OECD/NEA working group on fuel safety

IAEA, Nicole Virgili (IAEA, NPTDS) – New agency initiative on
fission-fusion technology interfaces
ID 160, Christina Dominguez (FRA) – State of the art of IRSN’sstudies regarding fuel behaviour during LOCA
ID 171, Russell Cipolla (USA) – Development of a structural
integrity model for the steam generator tubing of the
SMART100 small modular reactor
ID 154, Quoc Dung Tran (VNM) – Calculation of the neutron
parameters for the accelerator-driven subcritical reactor using
Pb and Pb-Bi mixtures as both target and coolant
ID 86, Armin Seubert (DEU) – The finite element neutronics
code FENNECS for the safety assessment of SMRs, micro
reactors and other innovative concepts

Legend:Topic 1. Applying safety approaches and standards for evolutionary and innovative reactor technologies
Topic 2. Enhancing safety by innovative design features
Topic 3. Supporting integrated decision making through safety/risk analyses
Topic 4. Accelerating innovations for safety assessment through the advanced simulation and modelling, and experimental programmes

DATE

TIME

SESSIONS
Parallel Session 1

Parallel Session 2
Parallel Session 3
Parallel Session 4
Plenary session #2:
Panel discussion “Safety Demonstrations for evolutionary and innovative reactors: challenges and path forward”
Coffee break

9:00 – 10:30
10:30 – 11:00
Regulatory & Licensing

ID 82, Diego Fernández Lisbona (GBR) – Early assessment ofinnovative and advanced modular reactor (AMR) designs –regulatory process and insights from application to eight
designs in the UK
ID 156, Abel Julio Gonzalez (ARG) – A response to the
11:00 – 12:30 regulatory safety challenges for new reactor technologies
ID 192, Surik Bznuni (ARM) – Preliminary gap analysis of
Armenian regulatory basis for the licensing of SMR typereactors
ID 194, Tarek Tabikh (CAN) – Approach to small modular
and advanced reactor regulatory readiness

Defence in Depth by Design

Deterministic Safety Analysis

Simulation & Modelling

ID 152, Marcelo Gimenez (ARG) – CAREM25: An
integral methodological approach to coherently
internalize defence in depth in the design process
ID 103, Etienne Courtin (FRA) – Application of lines ofdefense (LoD) methodology for defense in depth
implementation in the design of Gen 4 reactors
ID 83, David Plummer (GBR) – Regulatory perspectiveon the application of the defence-in-depth concept toinnovative reactor technologies
ID 155, Artur Liubarskiy (RUS) – Design measures
aimed at eliminating cliff-edge effects as a necessary
condition for effectiveness of plant defence-in-depth

ID 3, Jozef Misak (CZE) – Issues and needs in applicationsof deterministic safety analysis for demonstrating safety of
nuclear power plants
ID 105, Michail Polevoy (RUS) – Determination oftemperature condition of absorbing elements for design
basic conditions and design extension conditions of nuclear
power plants
ID 114, Hidemasa Yamano (JPN) – Numerical analyses ofdesign extension conditions for sodium-cooled fast reactor
designed in Japan
ID 149, Aleksei Samokhin (RUS) – Integrated design
analyses of beyond-design-basis accidents at VVER-1200,
including fuel severe damage

ID 69, David Grabaskas (USA) – Using calibrated water data forpreliminary validation of the SRT code for advanced reactors
ID 106, Ronan Tanguy (WNA) – Harmonizing mechanical codes& standards for innovative reactors
ID 132, Fulvio Mascari (ITA) – Status of the independentvalidation of TRACE code for SMR safety analyses
ID 8, Mark Bedretdinov (RUS) – Thermal hydraulic codes
validation for spent fuel pool conditions

Lunch break

12:30 – 14:00

19 OCT 2022

Regulatory & Licensing
ID 42, Nasir Mughal (PAK) – Regulatory experiences inlicensing of advanced reactor technologies
ID 140, Simon Coenen (BEL) – Belgian approach for licensing
new innovative reactors
14:00 – 15:30 ID 163, Pablo Torano (ARG) – Argentine experience in thelicensing of CAREM 25 prototype reactor
ID 89, Rozbeh Vadi (IRN) – A review of the requirements of
the licensing procedure for the HTR-PM

Transportable NPP designs

PSA & Risk-Informed Decision Making

Simulation & Modelling

IAEA, Mikhail Lankin (IAEA, NSNI) – IAEA activities ondesign safety and security considerations for the TNPPID 169, Alexander Bychkov (IAEA, INPRO) – INPRO
studies on transportable nuclear power plants andmodules and key legal issues for their regulations
ID 100, Bernat Cirera (DNK) – Safety approaches for
the CMSR power barge
ID 147, Daria Doronkova (RUS) – Nuclear floating
power unit: Ensuring safety during transportation

ID 139, David Grabaskas (USA) – The ASME/ANS
probabilistic risk assessment standard for advanced nonlight water reactor nuclear power plants
ID 128, Jeffery Julius (USA) – Changes in PSA models to
support the licensing of advanced non-light water reactors
ID 98, Karthik Ravichandran (CHE) – Verification of SSC
safety classification according to IAEA SSG-30 functional
approach: Benefits of DSA and PSA integration
ID 126, Dennis Henneke (USA) – Natrium reactor SSC
classification using the licensing modernization project(LMP) process

ID 59, Taiju Shibata (JPN) – New test plan about safety featuresof HTGR by using HTTR in JAEA
ID 190, Daniel LaBrier (USA) – Revival of a practical sodium
safety culture through experiential training
ID 185, Amjad Farooq (PAK) – Experimental investigation ofiodine removal in a lab scale setup of filtered containment
venting system
ID 75, Plamen Petkov (BGR) – Experimental investigation ofliquid Tin surface property safety features for potential
application as a coolant in direct contact liquid metal fast
reactors (DCLMFR) heat removal

Coffee break

15:30 – 16:00
Safety Approach

Design Safety Features

PSA & Risk-Informed Decision Making

ID 60, Shigenobu Kubo (JPN) – Safety design
approaches for future SFRs in Japan
ID 118, Jingmei Zhu (CHN) – Standard study of thetechnology and safety performance evaluation on
emergency core cooling system strainer
ID 37, Mirela Nitoi (ROU) – Towards innovative
reactors licensing - ALFRED approach
ID 84, Jesse Seymour (USA) – Technology-inclusive
human-system considerations for advanced reactors

ID 193, Dennis Henneke (USA) – Risk-informed safety
strategy and fault evaluation for the GE Hitachi BWRX-300
advanced reactor
ID 202, Irina Kuzmina (RUS) – Insights on application ofsome probabilistic considerations for licensing of new
nuclear power plants
ID 85, Sayed Muhammad Waseen (PAK) – Application of
the Level-1 PSA model in various regulatory processes andchallenges faced during their execution
ID 41, Neil Harman (GBR) – Evolution in Level 3
probabilistic safety assessment methodology for the UKEPR
ID 164, Federic Jose Carlin Llorenete (ARG) – Regulatory
criteria proposal for the mission time of the sequences ofthe event trees of the L1 PSA for new nuclear powerreactors

PANEL DISCUSSION ON
ID 153, Noreddine Mesmous (CAN) – An innovative
methodology for designing and regulating small and modular
reactors
ID 76, Debbie Francis (FRA) – NUWARD safety approach,
implementing SMR specifics and preparing international
deployment
16:00 – 18:00 ID 107, Mariano Tarantino (E.C) – GIF LFR safety design
criteria
ID 127, Satoshi Futagami (JPN) – Development of safety
design criteria and safety design guidelines for Generation IV
sodium-cooled fast reactors
ID 99, Bernat Cirera (DNK) – Toward developing a novel
combined licensing & safety approach for advanced nuclear
reactors based on the international maritime and nuclear
safety framework. Case study of the CMSR power barge.

SIMULATION & MODELLINGMSCFP, Valeriia Skliarenko – Chinese supercritical water
reactor CSR-1000: Safety features and exploration of hydraulicresistance coefficient correlations
ID 92, Hiberto Sanchez-Mora (MEX) – BWR severe accident
uncertainty and sensitivity analysis in the framework of the
IAEA CRP I31033
ID 146, Nikolai Ryzhov (RUS) – Uncertainty and sensitivity
analysis of severe accidents simulations at VVER in theframework of the IAEA CRP I31033
ID 157, Pablo Hernan Ilardo (ARG) – Development of
uncertainty and sensitivity approaches for the analysis of severe
accidents in a small modular reactor

DATE

TIME

SESSIONS
Parallel Session 1

Parallel Session 2

Parallel Session 4

Plenary session #3:
Panel discussion “SMR and microreactors: Design challenges and safety implications”
Coffee break

9:00 – 10:30
10:30 – 11:00
Safety, Security and Safeguards Interfaces (3S)
IAEA, Jeremy Whitlock (IAEA, SGCP) – Safeguards by design
for SMRs
ID 70, Donald Kovacic (USA) – Considering internationalsafeguards during the design of advanced reactors andinterfaces with safety and security
11:00 – 12:30
ID 81, Duncan Barley (GBR) – Safety, security and safeguards
working together in the modernised generic design
assessment
ID 184, Adam Williams (USA) – Lessons learned from
exploring safety, security, and safeguards interfaces inadvanced and small modular reactor technologies

Severe Accident Management

PSA & Risk-Informed Decision Making

Simulation & Modelling

IAEA, Alexei Miassoedov (IAEA, NENP) – SAMG-D
toolkitID 46, Gaojian Dang (CHN) – The development andvalidation of the accident prevention and mitigation
strategy for the ACP100 modular small reactor
ID 172, Wei Wei (CHN) – Development and applicationof a severe accident management guidelines
verification and drilling platform at CNNP
ID 50, Ahmed Bentaib (ESP) – NUGENIA/TA2 recent
achievements in severe accidents research

ID 110, Anders Gilbertson (USA) – U.S. nuclear regulatorycommission guidance on the acceptability of probabilistic
risk assessment used in regulatory decision making for
non-light-water reactors
ID 93, Tanju Sofu (USA) – GIF framework for risk-informed
approach for design and licensing of novel advanced
reactors
ID 58, Stephan M Hess (USA) – Integrated RAMI for
advanced nuclear power plants
ID 175, Elisabeth Duvillard (FRA) – Incorporation of passive
system functional reliability in probabilistic safetyassessment

ID 45, Evgenii Soldatov (RUS) – System of design codes for thecomputational modeling of the lead-cooled fast reactors
ID 51, Sebastian Buchholz (DEU) – Recent improvements of
ATHLET models for passive safety features of LW-SMR
ID 27, Peter Lien (USA) – TRACE confirmatory analysis model
development and validation in NuScale design
ID 159, Michael Martin (GBR) – Enhanced safety of current andfuture nuclear plant using integrated mechanistic models anddata-centric assessment of risk

Lunch break

12:30 - 14:00
Safety, Security and Safeguards Interfaces (3S)

20 OCT 2022

Parallel Session 3

ID 173, Carolynn Scherer (IAEA) – Using INPRO methodology
for a holistic sustainability assessment in safety, safeguards
and security (3S)
ID 123, Luca Ammirabile (EC) – Application of the objective
provision tree tool for the safety-security interface
14:00 – 15:30 assessment
ID 25, Ismael Garcia (USA) – Impact of cyber security
features on digital instrumentation and control systems
important to safety at nuclear power plants – evaluation
framework
ID 24, Ismael Garcia (USA) – U.S.A. regulatory efforts forcybersecurity of small modular reactors/advanced reactors

Passive Systems

PSA & Risk-Informed Decision Making

Simulation & Modelling

ID 54, Aleksei Samokhin (RUS) – Evaluation of theinnovative steam generators passive heat removal
system efficiency for VVER-1200 power units inbeyond design basis accidents conditions
ID 133, Petr Vácha (CZE) – Innovative passive safety
features of the HeFASTo Reactor Concept
ID 199, Yidan Yuan (CHN) – An experimental programfor ACP100 passive containment air cooling system
ID 189, Chukwudi Azih (CAN) – Development ofexperimental and modelling capabilities and tools at
Canadian nuclear laboratories for investigations on
inherent and passive safety designs of advanced
reactor concepts

ID 36, Na Xue (CHN) – Application of probabilistic methodin the EPZ determination of SMR
ID 94, Shilp Vasavada (USA) – Insights for risk-informed
approaches to sizing emergency planning zones
ID 162, Luke Lebel (CAN) – Challenges in defining
emergency planning zones for small modular reactors andadvanced reactors: Review of Canadian practices andresearch at Canadian nuclear laboratories
ID 135, Eric Schrader (USA) – An alternative emergency
preparedness regulatory framework for small modular
reactors and other new technologies

ID 161, Christophe Herer (FRA) – Natural circulation HERO-2
experiment simulations in the EU funded PASTEL Project
ID 91, Shanlai Lu (USA) – Long term effects and numericalsimulation of radiolytic gas, non-condensable gas and borontransport for small modular light water reactors
ID 188, Krishna Podila (CAN) – Development of multiphysics
modelling capabilities for small modular reactors in Canada
ID 39, Victor Sanchez Espinoza (DEU) – Status of the H2020
McSAFER project-experimental and analytical investigations forthe safety evaluation of water-cooled SMRs

Coffee break

15:30 – 16:00
Passive Systems

PSA & Risk-Informed Decision Making

Simulation & Modelling

ID 57, Finis Southworth (USA) – The effect ofintermittent passive heat removal on HTGR
conduction cooldown performance
ID 148, Oleg Tiurikov (RUS) – Experimental andcomputational research of the containment passive
emergency pressure decrease system in the floating
NPP with reactor KLT-40S and universal nuclearpowered icebreaker with reactor RITM-200
ID 186, Federico Mezio (ARG) – Uncertainty
assessment of a CAREM 25 passive safety system:
Lifecycle management study case
ID 129, Muhammad Ilyas (PAK) – Thermal hydraulicanalysis of a novel concept for a passive containment
cooling system
MSCFP, Nurberk Sungur – Assessment of VVER-1200(V-491) core cooling reliability during the operation ofpassive heat removal system via steam generator

ID 97, Karthik Ravichandran (CHE) – Synergizing
deterministic and probabilistic safety analyses - a holistic
approach to safety at Leibstadt NPP, Switzerland
ID 134, Yasushi Okano (JPN) – ARKADIA-Safety, an overallrisk assessment simulation tool for risk integrated andperformance based decision making
ID 168, Gueorgui Petkov (BGR) – Contextual integrated
risk-informed decision-making
ID 182, David Grabaskas (USA) – Markov decision
processes for intelligent, risk-informed asset-management
decision-making

ID 67, Yury Shmelkov (RUS) – Practical application of sensitivity
and uncertainty analyzes in the analysis of radiologicalconsequences for BDBA at modern NPPs with VVER
ID 137, Pavel Kanin (RUS) – Practical application of uncertainty
and sensitivity analysis methodologies for the analysis of severe
accidents in VVER reactors
ID 95, Kwang-il Ahn (KOR) – Uncertainty and sensitivity analysisof the PWR and SMR by means of severe accident codes in theframework of the IAEA CRP I31033
ID 33, Ashraf Aboshosha (EGY) – Computer aided design andsimulation of professional hybrid electrical energy backup system
for nuclear facilities

PANEL DISCUSSION ON

SAFETY, SECURITY AND SAFEGUARDS
INTERFACES AND CHALLENGES (3S)

16:00 – 18:00

21 OCT 2022

DATE

TIME

SESSIONS
Parallel Session 1

9:00 – 10:30

13:00

Parallel Session 3

Parallel Session 4External Hazards

Multi-unit & Multi-module Risk Analysis

Artificial Intelligence

IAEA, Laura Micewski (IAEA, NSNI) – External hazards
related issues in SMR siting and design
ID 64, Miguel Peinador (FRA) – Main lessons learned
from the clearinghouse topical operational
experience report (TOER) on external hazards andtheir possible use for the design of new reactors
ID 78, Karel Deknopper (BEL) – External hazard
challenges for evolutionary and innovative reactor
designs
ID 181, David Grabaskas (USA) – The regulatory
treatment of low frequency external events as part ofa risk-informed performance-based approach

IAEA, Shahen Poghosyan (IAEA, NSNI) – IAEA methodology
on multi-unit probabilistic safety assessment
ID 145, Dennis Henneke (USA) – Multi-module
probabilistic safety assessment (PSA) for the PRISM
sodium-cooled fast reactor
ID 66, Abdul Qavi (PAK) – Probabilistic safety assessmentof multi unit site of nuclear power plant
MSCFP, Yanfei Qiu – Neutronics design and modelling of a
NUSCALE-based small modular PWR

IAEA, Tatjana Jevremovic (IAEA, NENP) and Yun Goo Kim (IAEA,
NSNI) – IAEA activities on artificial intelligence (joint presentation
by IAEA NE and IAEA NS)
ID 63, Adolphus Lye (GBR) – Probabilistic AI for prediction ofmaterial properties in nuclear reactors
ID 170, Guoyang Ma (CHN) – The design and application of theintelligent accident analysis system for the nuclear power plant
ID 176, Samuele Meschini (ITA) – Machine learning applications
for nuclear safety: An overview

Coffee break

10:30 – 11:00
11:00 – 13:00

Parallel Session 2

Closing session
Adjourn