JAEA-Conf
2024-001
DOI:10.11484/jaea-conf-2024-001

Proceedings of the 12th International Conference on
Nuclear Criticality Safety (ICNC2023)
October 1-6, 2023,
Sendai International Center, Sendai, Miyagi, Japan(Eds.) Kenya SUYAMA, Satoshi GUNJI, Tomoaki WATANABE, Shohei ARAKI
Kodai FUKUDA, Kazuya SHIMADA, Tatsuya FUJITA, Taro UEKI
and Hoang Hai NGUYEN

Fuel Cycle Safety Research Division
Nuclear Safety Research Center
Sector of Nuclear Safety Research and Emergency Preparedness

July 2024
Japan Atomic Energy Agency

日本原子力研究開発機構

本レポートは国立研究開発法人日本原子力研究開発機構が不定期に発行する成果報告書です。
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は、下記までお問い合わせ下さい。
なお、本レポートの全文は日本原子力研究開発機構ウェブサイト（https://www.jaea.go.jp）
より発信されています。
国立研究開発法人日本原子力研究開発機構〒 319-1112

研究開発推進部

科学技術情報課

茨城県那珂郡東海村大字村松 4 番地 49

E-mail: ird-support@jaea.go.jp
This report is issued irregularly by Japan Atomic Energy Agency.
Reuse and reproduction of this report (including data) is required permission.
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E-mail: ird-support@jaea.go.jp© Japan Atomic Energy Agency, 2024

JAEA-Conf 2024-001

Proceedings of the 12th International Conference on Nuclear Criticality Safety (ICNC2023)
October 1-6, 2023,
Sendai International Center, Sendai, Miyagi, Japan(Eds.) Kenya SUYAMA+, Satoshi GUNJI, Tomoaki WATANABE, Shohei ARAKI,
Kodai FUKUDA, Kazuya SHIMADA, Tatsuya FUJITA, Taro UEKI and Hoang Hai NGUYEN※
Fuel Cycle Safety Research Division, Nuclear Safety Research Center,
Sector of Nuclear Safety Research and Emergency Preparedness,
Japan Atomic Energy Agency
Tokai-mura, Naka-gun, Ibaraki-ken(Received May 1, 2024)
The 12th International Conference on Nuclear Criticality Safety (ICNC2023) was held from
October 1 to October 6, 2023, at the Sendai International Center (Aobayama, Aoba-ku, Sendai,
Miyagi-prefecture 980-0856, Japan), organized by Japan Atomic Energy Agency (JAEA) andco-organized by the Reactor Physics Division of the Atomic Energy Society of Japan (AESJ) and the
Nuclear Energy Agency of the Organisation for Economic Co-operation and Development(OECD/NEA). 224 presentations passed peer review and 273 technical session registrations, bringing
the total number of registered participants to 289, including accompanying persons. Technical tours
were also conducted to i) Fukushima Daiichi Nuclear Power Station of TEPCO holdings and Interim
Storage Facility Information Center, ii) Nuclear Science Research Institute of JAEA (STACY
Renewable Reactor and FCA), iii) NanoTerasu of Tohoku University (synchrotron radiation facility)
and Onagawa Nuclear Power Station of Tohoku Electric Power Co., Inc. This report summarizes theconference and compiles the papers that were presented and agreed to be published in the Proceedings.

Keywords: Criticality Safety, International Conference, ICNC, AESJ Reactor Physics Division,
OECD/NEA+Nuclear Safety Research Center※Post-Doctoral Fellowi

JAEA-Conf 2024-001

第 12 回臨界安全性国際会議予稿集
2023 年 10 月 1 日～6 日
宮城県仙台市 仙台国際センター
日本原子力研究開発機構

安全研究・防災支援部門 安全研究センター

燃料サイクル安全研究ディビジョン
（編）須山

賢也+、郡司
藤田

智、渡邉

友章、荒木

祥平、福田

達也、植木

太郎、Hoang Hai Nguyen

航大、島田

和弥、

※

（2024 年 5 月 1 日受理）
第 12 回臨界安全性国際会議（ICNC2023）は 2023 年 10 月 1 日から 10 月 6 日に仙台国際センター（〒980-0856 宮城県仙台市青葉区青葉山）において、日本原子力研究開発機構（原子力機構）の主催、日本原子力学会炉物理部会と経済協力開発機構原子力機関（OECD/NEA）の共催によって開催された。最終的に査読を通過した 224 件の発表と 273 名のテクニカルセッション
参加登録があり、同伴者を含めた総登録数は 289 名であった。テクニカルツアーも i) 東京電力
福島第一原 子力発電所 及び中間貯 蔵工事情報 センター、ii) 原子力機 構原子力科 学研究所
（STACY 更新炉及び FCA）、iii) 東北大学ナノテラス（放射光施設）及び東北電力女川原子力発電所の 3 コースで実施された。会議の概要とともに、発表された論文で予稿集掲載に合意されたものを本報告書に取り纏めた。

原子力科学研究所：〒319-1195 茨城県那珂郡東海村大字白方 2 番地 4
+安全研究センター※博士研究員ii

JAEA-Conf 2024-001

Contents
1.

Introduction ------------------------------------------------------------------------------------------------------ 1

2.

Organizing Committee ----------------------------------------------------------------------------------------- 2

3.

International Scientific Advisory Committee ----------------------------------------------------------------- 3

4.

Technical Program Committee ---------------------------------------------------------------------------------- 4

5.

Track Leaders ----------------------------------------------------------------------------------------------------- 5

6.

List of Reviewers ------------------------------------------------------------------------------------------------- 7

7.

Management Board --------------------------------------------------------------------------------------------- 11

8.

General Program ------------------------------------------------------------------------------------------------ 12

9.

Technical Tours ------------------------------------------------------------------------------------------------- 15

10. NEA Workshop -------------------------------------------------------------------------------------------------- 17
11. Technical Program; day by day -------------------------------------------------------------------------------- 18
12. Technical Program in Detail ----------------------------------------------------------------------------------- 20
13. Poster Evaluation ------------------------------------------------------------------------------------------------ 35
14. Summary of Submission and Participation ------------------------------------------------------------------ 36
15. Sponsors ---------------------------------------------------------------------------------------------------------- 37
16. Full Papers in Appendix ---------------------------------------------------------------------------------------- 39
Acknowledgements -------------------------------------------------------------------------------------------------- 40iii

JAEA-Conf 2024-001

目

次

1.

序論 --------------------------------------------------------------------------------------------------------------- 1

2.

組織委員会 ------------------------------------------------------------------------------------------------------ 2

3.

国際科学助言委員会 -------------------------------------------------------------------------------------------- 3

4.

技術プログラム委員会 ----------------------------------------------------------------------------------------- 4

5.

トラックリーダー ----------------------------------------------------------------------------------------------- 5

6.

査読者リスト ----------------------------------------------------------------------------------------------------- 7

7.

企画運営部会 --------------------------------------------------------------------------------------------------- 118.

全体プログラム ------------------------------------------------------------------------------------------------ 12

9.

テクニカルツアー --------------------------------------------------------------------------------------------- 15

10. 原子力機関ワークショップ --------------------------------------------------------------------------------- 17
11. 各日の技術プログラム --------------------------------------------------------------------------------------- 18
12. 詳細な技術プログラム --------------------------------------------------------------------------------------- 20
13. ポスター発表の評価 ------------------------------------------------------------------------------------------ 35
14. 投稿と参加の状況 --------------------------------------------------------------------------------------------- 36
15. 協賛 --------------------------------------------------------------------------------------------------------------- 37
16. 付録に含まれる論文 ------------------------------------------------------------------------------------------ 39
謝辞 -------------------------------------------------------------------------------------------------------------------- 40iv

JAEA-Conf 2024-001

1. Introduction
As Table 1 shows, the International Conference on Criticality Safety (ICNC) is organized every four
years in the US, European countries, and Japan.
Table 1: History of the International Conference on Criticality Safety (ICNC)
Year

Venue

Host Country

1981

Los Alamos

USA

1983

Dijon

France

1987

Tokyo

Japan

1991

OxfordUK

1995

Albuquerque

USA

1999

Versailles

France2003

Tokai-mura

Japan

2007

St Petersburg

Russia2011

Edinburgh

UK

2015

Charlotte

USA

2019

Paris

FranceThe 12th ICNC (ICNC2023), the third round of ICNC organized in Japan, was held from October 1 to
October 6, 2023, at the Sendai International Center (Aobayama, Aoba-ku, Sendai, Miyagi-prefecture
980-0856, Japan), organized by JAEA and co-organized by the Reactor Physics Division of the Atomic
Energy Society of Japan (AESJ) and the Nuclear Energy Agency of the Organisation for Economic
Co-operation and Development (OECD/NEA). 224 presentations passed peer review and 273 technicalsession registrations, bringing the total number of registered participants to 289, including
accompanying persons. Technical tours were also conducted to i) Fukushima Daiichi Nuclear Power
Station of TEPCO holdings and Interim Storage Facility Information Center, ii) Nuclear Science
Research Institute of JAEA (Modified STACY and FCA), iii) NanoTerasu of Tohoku University(synchrotron radiation facility) and Onagawa Nuclear Power Station of Tohoku Electric Power Co., Inc.
This report is a summary of the ICNC2023 and a compilation of the papers that were presented andagreed to be published in the Proceedings.

-1-

JAEA-Conf 2024-001

2. Organizing Committee

Chair
Ken NAKAJIMA

Kyoto University*

Members
Go CHIBA

Hokkaido University

Naoto AIZAWA

Tohoku University

Toru OBARA

Tokyo Institute of Technology

Tomohiro ENDO

Nagoya University

Takanori KITADA

Osaka University

Cheol Ho PYEON

Kyoto University

Nozomu FUJIMOTO

Kyushu University

Keisuke YAMAUCHITEPCO Holdings

Yoshiaki TSURUTATEPCO Holdings

Daiichiro ITO

Nuclear Fuel Transport Co., Ltd.

Satoru HAYAMI

Japan Nuclear Fuel Limited

Yasushi NAUCHI

Central Research Institute of Electric Power Industry

Yamato HAYASHI

Toshiba Energy Systems & Solutions Corporation

Yuichi MORIMOTO

Hitachi GE Nuclear Energy

Yasuhiro HARADA

Mitsubishi Heavy Industries, Ltd.

Hiroaki NAGANO

Nuclear Fuel Industries, Ltd.

Shigeaki AOKI

Mitsubishi Nuclear Fuel, Co., Ltd.

Kenya SUYAMAJapan Atomic Energy Agency

Taro UEKI

Japan Atomic Energy Agency

Yuichi YAMANE

Japan Atomic Energy Agency

Hiroshi OKUNOJapan Atomic Energy Agency

Kazuhiko IZAWA

Japan Atomic Energy Agency

Tomoaki WATANABE

Japan Atomic Energy Agency

Shouhei ARAKI

Japan Atomic Energy Agency

Kodai FUKUDA

Japan Atomic Energy Agency

Satoshi GUNJI

Japan Atomic Energy Agency

The late Satoshi SAKURAI

Japan Atomic Energy Agency*Retired in 2023

-2-

JAEA-Conf 2024-001

3. International Scientific Advisory Committee
Gert VAN DEN EYNDE

SCK-CEN (BELGIUM)

Vladimir KHOTYLEV

Canadian Nuclear Safety Commission (CANADA)

Anssu RANTA-AHO

Teollisuuden Voima Oyj (FINLAND)

Karin RANTAMAKI

Radiation and Nuclear Safety Authority (FINLAND)

Aurélie BARDELAY

IRSN(FRANCE)

Coralie CARMOUZECEA Cadarache (FRANCE)

Axel HOEFER

Framatome GmbH (GERMANY)

Robert KILGER

Gesellschaft für Anlagen- und Reaktorsicherheit (GRS)
mbH(GERMANY)

Dirk SCHULZE GRACHTRUP

Bundesamt für die Sicherheit der
nuklearen Entsorgung (BASE)(GERMANY)

Maik STUKEBGZ Gesellschaft für Zwischenlagerung (GERMANY)

Gabor HORDOSY

Centre for Energy Research (HUNGARY)

Agnieszka BOETTCHER

National Centre for Nuclear Research (POLAND)Maria Consuelo ALEJANO MONGE

Consejo de Seguridad Nuclear (SPAIN)

Dennis MENNERDAHL

E. Mennerdahl Systems (SWEDEN)

Stefano CARUSO

Kernkraftwerk Gösgen-Däniken AG(NPP)(SWITZERLAND)

Alexander VASILIEVPaul Scherrer Institut (SWITZERLAND)

Sonny GANSELLAFIELD LTD. (UNITED KINGDOM)

Gregory O'CONNOR

Office for Nuclear Regulation (UNITED KINGDOM)

Catherine PERCHER

Lawrence Livermore National Laboratory (UNITEDSTATES)

Doug BOWEN

Oak Ridge National Laboratory (UNITED STATES)

William MARSHALL

Oak Ridge National Laboratory (UNITED STATES)

Julie-Fiona MARTIN

OECD Nuclear Energy Agency

Tatiana IVANOVAOECD Nuclear Energy Agency

Takanori KITADA

Osaka University (JAPAN)

Kazufumi TSUJIMOTO

Japan Atomic Energy Agency (JAPAN)

Satoshi GUNJI

Japan Atomic Energy Agency (JAPAN)-3-

JAEA-Conf 2024-001

4. Technical Program Committee

Chair
Tomohiro ENDO

Nagoya University

Members
Kenichi TADA

Japan Atomic Energy Agency

Go CHIBA

Hokkaido University

Satoshi TAKEDA

Osaka University

Masahiro FUKUSHIMA

Japan Atomic Energy Agency

Tatsuya FUJITA

Nuclear Regulation Authority

Kento YAMAMOTO

Nuclear Fuel Industries

Yasuhiro HARADA

Mitsubishi Heavy Industries

Yuichi YAMANE

Japan Atomic Energy Agency

Cheol Ho PYEON

Kyoto University

Hiroki TAKEZAWA

Nagaoka University of Technology

Naoto AIZAWA

Tohoku University, Japan

Yasushi NAUCHI

Central Research Institute of Electric Power Industry

Masahiro TATSUMI

Nuclear Engineering

Taro UEKI

Japan Atomic Energy Agency

Tomoaki WATANABE

Japan Atomic Energy Agency

Shouhei ARAKI

Japan Atomic Energy Agency

Kodai FUKUDA

Japan Atomic Energy Agency

Satoshi GUNJI

Japan Atomic Energy Agency-4-

JAEA-Conf 2024-001

5. Track Leaders
Track 1: Codes and Other Calculation Methods
Andrea ZOIA (CEA, France)
Taro UEKI (JAEA, Japan)
Track 2: Nuclear Data
Coralie CARMOUZE (CEA, France)
Kenichi TADA (JAEA, Japan)
Track 3: Uncertainty and Sensitivity Analysis
Axel HOEFER (Framatome GmbH, Germany)
Go CHIBA (Hokkaido Univ., Japan)
Satoshi TAKEDA (Osaka Univ., Japan)
Track 4: Measurements, Experiments, and Benchmarks
Catherine PERCHER (LLNL, USA)
Masahiro FUKUSHIMA (JAEA, Japan)
Track 5: Standards, Assessment Methodology, and Regulations
Gregory O’CONNOR (ONR, UK)
Tatsuya FUJITA (Nuclear Regulation Authority, Japan)
Track 6: Operational Practices and Safety Cases
Mark DEHART (INL, USA)
Kento YAMAMOTO (Nuclear Fuel Industries, Japan)
Track 7: Storage, Transport, and Disposal Issues
Dimitri ROCHMAN (PSI, Switzerland)
Yasuhiro HARADA (Mitsubishi Heavy Industries, Japan)
Track 8: Criticality Accidents and Incidents
Matthew EATON (Imperial College London, UK)
Yuichi YAMANE (JAEA, Japan)-5-

JAEA-Conf 2024-001

Track 9: Professional Development Issues and Training
John MILLER (SNL, USA)
Pyeon Cheol Ho (Kyoto Univ., Japan)
Hiroki TAKEZAWA (Nagaoka Univ. of Tech., Japan)
Track 10: Future Challenges
Julie-Fiona MARTIN (OECD/NEA, International org.)
Naoto AIZAWA (Tohoku Univ., Japan)
Special Session 1: Fukushima Dai-ichi NPS
Aurélie BARDELAY (IRSN, France)
Yasushi NAUCHI (CRIEPI, Japan)
Special Session 2: Machine Learning, Deep Learning
Alexander VASILIEV (PSI, Switzerland)
Masahiro TATSUMI (Nuclear Engineering, Japan)-6-

JAEA-Conf 2024-001

6. List of Reviewers
Eric ABOUD
Naoto AIZAWA
Thomas ALBERT
Kelly E ALDRICH
Kelsey AMUNDSON
Shigeaki AOKI
Shouhei ARAKI
Kaushik BANERJEE
Aurelie BARDELAY
John Darrell BESS
Agnieszka BOETTCHER
Douglas G. BOWEN
Mariya BROVCHENKODavid BROWN
Andrew Charles BUCHAN
Gregory CAPLIN
Coralie CARMOUZEAngela CHAMBERS
Yuting CHENG
Pyeon CHEOL HO
Go CHIBA
Laurent CHOLVY
Katrina CHRISTAKI
Justin CLARITY
Theresa CUTLER
Sam DARBYCharlotte DAVISMark DEHART
Aurelien DORVAL
Matthieu DULUC
Mathieu DUPONT
Matthew EATON
Tomohiro ENDO
Luca FIORITO
Eoin FLANNERY
Nozomu FUJIMOTO
Tatsuya FUJITA
Kodai FUKUDA
Masahiro FUKUSHIMA
Travis GREENE
Satoshi GUNJI
Yasuhiro HARADA
Stewart HAY

LLNL
Tohoku University
Framatome
LANL
LANL
MNF
JAEA
PNNL
IRSN
JFoster & Associates, LLC
National Centre for Nuclear Research
ORNL
IRSN
BNL
AWE Plc
ORANO
CEA
NNSA
CIAE
Kyoto University
Hokkaido University
CEA
Cerberus Nuclear
PNNL
LANL
ONR
Nuclear Transport Solutions
INL
CEA
IRSN
ORNL
Imperial College London
Nagoya University
SCK CEN
ONR
Kyushu University
NRA
JAEA
JAEA
ORNL
JAEA
MHI
Cerberus Nuclear-7-

JAEA-Conf 2024-001

Yamato HAYASHIDavid P. HEINRICHS
Maik HENNEBACH
Deborah HILL
Tetsushi HINO
Axel HOEFER
Jesson D HUTCHINSON
Germina ILAS
Daiichiro ITO
Hiroki IWAMOTO
Kazuhiko IZAWA
Ryota KATANO
Gregory J. KEEFER
Robert KILGER
Rei KIMURA
Bernd KLUVER
Ryoichi KONDO
Georgios KYRIAZIDISMichael LAGET
Dale LANCASTER
Luiz LEAL
Yi-Kang LEE
Peng Hong LIEM
Clement LOPEZ
Marat MARGULISWilliam B.J. MARSHALL
Julie-Fiona MARTIN
Shuhei MARUYAMA
George E. MCKENZIE
Walid METWALLY
Rick MIGLIORE
John MILLER
Yuichi MORIMOTO
Jeremy MUNSON
Hiroaki NAGANO
Yasunobu NAGAYA
Makoto NAKANOPrakash NARAYANAN
Toshihiro NATSUME
Yasushi NAUCHIHai Hoang NGUYEN
Tangi NICOL
Kenji NISHIHARA
Gilles NOGUERE
Jesse NORRISDavid NOYELLES

Toshiba ESS
LLNL
Orano NCS GmbH
UKNNL
HitachiFramatome GmbH
LANL
ORNL
Nuclear Fuel Transport Co., Ltd.
JAEA
JAEA
JAEA
LLNL
GRS
Toshiba ESS
TUV NORD EnSys GmbH & Co. KG
JAEA
CEA
CEA
Nuclear Consultants
IRSN
CEA-Saclay
NAIS
CEA
School of Computer Science andEngineering
ORNL
OECD/NEA
JAEA
LANL
ORNL
ORANO
SNL
Hitachi GE Nuclear Energy
U.S. NRC
NFI
JAEA
MHI
ORANO, TN
MHI NS engineering
CRIEPI
JAEA
CEA
JAEA
CEA
LLNL
CEA

-8-

Electronic

JAEA-Conf 2024-001

Michelle NUTTALL
Gregory O’CONNOR
Akito OIZUMI
Shoichiro OKITA
Hiroshi OKUNO
Pedro M ORTEGO
Tom PAGE
Liam PAYNE
Imre PAZSIT
Yannick PENELIAU
Catherine PERCHER
Patrick PIN
Michael PRIGNIAU
Susanne PUDOLLEK
Derek PUTLEY
Olivier RAVATKristina REED
Simon David RICHARDS
Michael Evan RISING
Dimitri ROCHMAN
Benjamin RUPRECHT
Mark SAVAGE
Peter SCHILLEBEECKXIRWAN LIAPTO SIMANULLANG
Kenya SUYAMA
Motomu SUZUKI
Kenichi TADA
Satoshi TAKEDA
Hiroki TAKEZAWA
Aaron TAMASHIRO
Masahiro TATSUMI
Kotaro TONOIKE
Kazufumi TSUJIMOTO
Kosuke TSUJITA
Toby TYASTaro UEKI
Timothy VALENTINE
Gert VAN DEN EYNDE
Steven C. VAN DER MARCK
Alexander VASILIEVJack VENNER
Satoshi WADA
Tomoaki WATANABE
Stuart WATSON
Ben WEBBORN
Robert Allen WELDON

Sellafield Ltd
ONR
JAEA
JAEA
JAEA
Science Engineering Associates
Cerberus Nuclear
Nuclear Waste Services
Chalmers University of Technology
CEA
LLNL
Orano Recyclage
CEA
Nagra
Independent Criticality Consultant
ORANO
ORNL
JacobsLANL
PSI
Federal Office for the Safety of Nuclear Waste
Management
Urenco UK Limited
European Commission
Kyushu University
JAEA
CRIEPI
JAEA
Osaka University
Nagaoka University of Technology
LLNL
NEL
JAEA
JAEA
Nuclear Engineering, Ltd.
Cerberus Nuclear
JAEA
ORNL
SCK CEN
Nuclear Research and Consultancy GroupPSINCS Risk Management
Toshiba ESS
JAEA
3T Safety Consultants
Webborn Nuclear Safety Consultants Limited
LANL

-9-

JAEA-Conf 2024-001

Larry L WETZEL
Dominic WINSTANLEY
Akio YAMAMOTO
Kento YAMAMOTO
Toshihiro YAMAMOTO
Yuichi YAMANE
Kenji YOKOYAMA
Kenichi YOSHIOKA
Michael Leigh ZERKLE
Andrea ZOIA

BWXT
Sellafield Ltd
Nagoya University
NFI
Kyoto University
JAEA
JAEA
Toshiba ESS
Naval Nuclear Laboratory
CEA- 10 -

JAEA-Conf 2024-001

7. Management Board
Ken NAKAJIMA

Kyoto University*

Naoto AIZAWA

Tohoku University

Yasushi NAUCHI

Central Research Institute of Electric Power Industry

Satoshi GUNJI

Japan Atomic Energy Agency

Taro UEKI

Japan Atomic Energy Agency

Tomoaki WATANABE

Japan Atomic Energy Agency

Shouhei ARAKI

Japan Atomic Energy Agency

Kodai FUKUDA

Japan Atomic Energy Agency

Kazuya SHIMADA

Japan Atomic Energy Agency

Yuichi YAMANE

Japan Atomic Energy Agency

Kazuhiko IZAWA

Japan Atomic Energy Agency

Kenya SUYAMAJapan Atomic Energy Agency*Retired in 2023

- 11 -

JAEA-Conf 2024-001

8. General Program
OPENING PLENARY
8:30-10:45, October 2, 2023

General remarks by management board of ICNC2023 organizing committee
Dr. Kenya SUYAMAHead of Fuel Cycle Safety Research Division, Head of Criticality Safety Research Group, Japan
Atomic Energy Agency

Welcome address by the chair of the organizing committee of ICNC2023
Dr. Ken NAKAJIMA
Professor Emeritus, Kyoto University

Welcome address by the chair of the technical program committee of ICNC2023
Dr. Tomohiro ENDO
Associate Professor, Nagoya University

Welcome address by the organizer of ICNC2023
Dr. Hiroyuki OIGAWA
Executive Director, Japan Atomic Energy Agency

Welcome address by the co-organizers
Dr. Ian HILL
Deputy Head of NEA Division of Nuclear Science and Education

Welcome address by the co-organizers
Dr. Takanori KITADA
Professor, Osaka University, Chair of Reactor Physics Division of Atomic Energy Society of Japan

Welcome message by host city, Sendai
Technical Presentations Chaired by Ken NAKAJIMA

Criticality Safety for Decommissioning of Fukushima Daiichi Nuclear Power Station
Dr. Yasunori YAMANAKA
Director of Nuclear Damage Compensation and Decommissioning Facilitation Corporation- 12 -

JAEA-Conf 2024-001

Study on the Basic Core Analysis of the New STACY
Dr. Satoshi GUNJI
Principal Researcher, Manager of Criticality Safety Research Laboratory of Japan Atomic Energy
AgencyThe NEA’s Working Party on Nuclear Criticality Safety: Tackling Global Challenges
through International Cooperation
Dr. Julie-Fiona Martin
Administrator, Secretariat of the Working Party on Nuclear Criticality Safety of the Organizationof Economic Cooperation and Development, Nuclear Energy Agency

OFFICIAL DINNER
October 3, 2023
Hotel Metropolitan Sendai

Opening remarks
Dr. Ken NAKAJIMA
Chair of the Organizing Committee of ICNC2023,
Professor Emeritus, Kyoto University

Welcome address
Dr. Yuichi NIIBORI
President of the Atomic Energy Society of Japan
Professor, Head of the Department of Quantum Science and Energy Engineering, Graduate Schoolof Engineering, Tohoku University

Kagami-Biraki
Provided by the Diamond Sponsor – IRSN, France

Official Speech - “Short Comment of Retired Old Boy”
Mr. Iwao KOBAYASHIFormer Director of the Nuclear Fuel Cycle Safety Research Division, Former Leader of Criticality
Safety Research Laboratory, Japan Atomic Energy Research Institute (JAERI)

CLOSING PLENARY
11:05-12:45, October 5, 2023

- 13 -

JAEA-Conf 2024-001

Report from the Track Leaders
Chaired by Dr. Tomohiro ENDO
Chair of the Technical Program Committee of ICNC2023,
Associate Professor, Nagoya University
Announcement from the local organizer
Dr. Kenya SUYAMAJapan Atomic Energy Agency
Closing Remarks
Dr. Catherine Percher
Lawrence Livermore National Laboratory
Announcement of the next ICNC, ICNC2027 in the United Kingdom
Dr. Deborah Hill
National Nuclear Laboratory
Dr. Greg O'Connor
Office for Nuclear Regulation- 14 -

JAEA-Conf 2024-001

9. Technical Tours
Ibaraki / JAEA Tokai Course
8:00

Departure from JR Sendai Station East Gate
Bus: Expressway (SENDAI-HIGASHI IC) – (HITACHI-MINAMI-OTA IC)

12:00-12:50

Lunch at restaurant

13:10-16:30

JAEA Facilities (STACY・FCA)【Visit】
Bus: Expressway (HITACHI-MINAMI-OTA IC) - (SENDAI-HIGASHI IC)

20:30

Arrive at JR Sendai Station East Exit

JAEA staff on the bus
Satoshi GUNJI, Kazuhiko IZAWA and Shouhei ARAKI
Fukushima / Fukushima Daiichi NPS
7:30

Departure from JR Sendai Station East Gate
Bus: Expressway (SENDAI-HIGASHI IC) – (OKUMA IC)

9:30-10:45

Interim Storage Facility Information Center 【Visit】(Takatsudo Screening Spot)

11:15-12:00

Lunch at restaurant

12:30-16:10

TEPCO Decommissioning Archive Center※By Local private car to and from 1F
Fukushima Daiichi Nuclear Power Station（1F）【Visit】※By Local private car to and from 1F
TEPCO Decommissioning Archive Center
Bus: Expressway (JOBAN-TOMIOKA IC) – (SENDAI-HIGASHI IC)

18:30

Arrive at JR Sendai Station East Exit

JAEA staff on the bus
Yuichi YAMANE, Tomoaki WATANABE, Kodai FUKUDA and Kotaro TONOIKE- 15 -

JAEA-Conf 2024-001

Miyagi / NanoTerasu and Onagawa NPS
8:30

Departure JR Sendai Station East Gate

9:30-10:10

NanoTerasu 【Visit】
Bus: Expressway (SENDAI-HIGASHI IC) - (ISHINOMAKI-ONAGAWA IC)

12:00-13:00

Lunch at restaurant

13:30-16:30

Onagawa Nuclear Power Station【Visit】
Bus: Expressway (ISHINOMAKI-ONAGAWA IC) – (SENDAI-HIGASHI IC）

18:30

Arrive at JR Sendai Station East Exit

JAEA staff on the bus
Kenya SUYAMA, Taro UEKI and Kazuya SHIMADA- 16 -

JAEA-Conf 2024-001

10. NEA Workshop
14:00-16:30, October 1, 2023
Room 2
Provide participants with an opportunity for a hands-on training course covering NEA software.
Participants will learn how to use the efficiency use the Database for ICSBEP (DICE), the how the
Nuclear Data Sensitivity Tool (NDsAT) can be used to estimate how integral benchmark predictions will
respond to changes in nuclear data.
Animators:

Ian Hill (NEA) and Julie-Fiona Martin (NEA)

Requirement:

Laptop computer (Win, Mac)

Fee:

Free of charge

Capacity:

20-30 people

How to apply:

Apply through the submission system (fully booked; August 25)- 17 -

JAEA-Conf 2024-001

11. Technical Program; day by day

Monday, October 2

8:30–11:00, Plenary
SessionExhibition Hall 2

11:00–11:30, Coffee
Exhibition Hall 1
11:30–12:45, Session 1
Room 1: Track 2,
Nuclear Data
Room 2: Track 8,
Criticality
Accidents andIncidents
Room 3: Track 6,
Operational
Practices andSafety Cases
Room 4: Special
Session 1,
Fukushima
Dai-IchiNuclearPower Plant

Tuesday, October 3

Wednesday, October 4

8:00–8:30, Coffee
Exhibition Hall 1
8:30–10:35, Session 4
8:30–10:35, Session 7
Room 1: Track 1, Codes
Room 1: Track 1, Codes
and Otherand Other
Calculation
Calculation
Methods
Methods
Room 2: Track 8,
Room 2: Track 7, Storage,
Criticality
Transport, andAccidents andDisposal Issues
Incidents
Room 3: Track 9,
Room 3: Track 6,
Professional
Operational
Development
Practices andIssues andSafety Cases
Training
Room 4: Track 5,
Room 4: Track 4,Standards,
Measurements,
Assessment
Experiments,
Methodology,
and Benchmarks
Regulations
10:35–11:05, Coffee
Exhibition Hall 1
11:05–12:45, Session 5
Room 1: Track 1, Codes
and Other
Calculation
Methods
Room 2: Track 7,
Storage,Transport, andDisposal Issues
Room 3: Track 4,
Measurements,
Experiments,
andBenchmarks
Room 4: Track 5,Standards,
Assessment
Methodology,
Regulations
12:45–14:00, Lunch
Exhibition Hall 1

11:05–12:45, Session 8
Room 1: Track 1, Codes
and Other
Calculation
Methods
Room 2: Track 7, Storage,
Transport, andDisposal Issues
Room 3: Track 9,
Professional
Development
Issues andTraining
Room 4: Track 4,
Measurements,
Experiments,
and Benchmarks- 18 -

Thursday,
October 5

8:30–10:35,
Session 11
Room 1: Track 3,
Uncertain
ty andSensitivity Analysis
Room 2: Track 7,
Storage,Transport, andDisposalIssuesRoom 3: Special
Session 2,
MachineLearning,
Deep
Learning

11:05–12:45,
Closing Session
Exhibition Hall 2

JAEA-Conf 2024-001

Monday, October 2

Tuesday, October 3

Wednesday, October 4

14:00–15:40, Session 2
Room 1: Track 2,
Nuclear Data
Room 2: Track 8,
Criticality
Accidents andIncidents
Room 3: Track 6,
Operational
Practices andSafety Cases
Room 4: Special
Session 1,
Fukushima
Dai-IchiNuclearPower Plant
15:40–16:10, Coffee
Exhibition Hall 1

14:00–16:05, Session 6
Room 1: Track 2,
Nuclear Data
Room 2: Track 7,
Storage,Transport, andDisposal Issues
Room 3: Track 6,
Operational
Practices andSafety Cases
Room 4: Track 4,
Measurements,
Experiments,
andBenchmarks

14:00–15:40, Session 9
Room 1: Track 3,
Uncertainty andSensitivity
Analysis
Room 2: Track 7, Storage,
Transport, andDisposal Issues
Room 3: Track 10, Future
Challenges
Room 4: Track 4,
Measurements,
Experiments,
and Benchmarks

16:10–17:50, Session 3
Room 1: Track 1, Codes
and Other
Calculation
Methods
Room 2: Track 8,
Criticality
Accidents andIncidents
Room 3: Track 6,
Operational
Practices andSafety Cases
Room 4: Special
Session 1,
Fukushima
Dai-IchiNuclearPower Plant

16:05–16:10, Coffee
Exhibition Hall 1
16:10–17:50, Poster
SessionExhibition Hall 1

15:40–16:10, Coffee
Exhibition Hall 1
16:10–17:50, Session 10
Room 1: Track 3,
Uncertainty andSensitivity
Analysis
Room 2: Track 7, Storage,
Transport, andDisposal Issues
Room 3: Track 10, Future
Challenges
Room 4: Track 4,
Measurements,
Experiments,
and Benchmarks- 19 -

JAEA-Conf 2024-001

12. Technical Program in Detail
Session 1: MONDAY, OCTOBER 2, 11:30 – 12:45
Room 1
Track 2NUCLEAR DATA

Room 2
Track 8CRITICALITY
ACCIDENTS AND
INCIDENTS
Chairs: Yuichi Yamane(JAEA)
Matthieu Duluc(Framatome)
Completion of the CEA
Guide for Criticality
Accident Studies
Michael Laget, Francis
BarbryRoom 3
Track 6OPERATIONAL
PRACTICES AND
SAFETY CASES
Chairs: Georgios
Kyriazidis (CEA),
Andrew Charles Buchan(AWE)
APM Reprocessing
Facility – Dismantling of
Hot Cells Dedicated to
Uranium and Plutonium
Purification – Criticality
Safety Case
Laurent Cholvy, FrédéricAntegnard, Koalyann
Nuon et al.

Room 4
Special Session 1
FUKUSHIMA DAI-ICHINUCLEAR POWER
PLANT
Chairs: Jesson Hutchinson(LANL),
Yasushi Nauchi (CRIEPI)

Molecular Dynamics
Analysis of Reactor
Graphite for Preparing
Thermal Neutron
Scattering Law
Shoichiro Okita, Minoru
Goto

More Critiques ofHistorical Criticality
Accidents through theLens tf Behavioral
Economics
Brittany Williamson

Strategic Characterisation
to Support theDevelopment of
Criticality Safety
Assessments for
Decommissioning
B. J. Greenhalgh, T. Page

Criticality Assessment
Assuming Spent Fuel
Failure at Fukushima
Daiichi Nuclear Power
Plant Unit 1
Takahiro Koide, Takashi
Yoshii, Keita Fukawa

Impact of Light Water
Covariance on Integral
Benchmarks
Chris W. Chapman, DoroWiarda, B.J. Marshall

The Nuclear Criticality
Accident in Japan,
Revisited
Hiroshi Okuno, Kenya
SuyamaPhenix – The
Neutronography Reactor
and Its Auxialiary Circuits– Criticality Safety Issues
Laurent Cholvy, Quentin
Simon, Nadine Bonny etal.

Features of Fukushima
Daiichi Nuclear Power
Plant Accident andInformation on Fuel
Debris Obtained fromPCV Internal
Kenji Owada, Masakuni
Kumeda, Takeshi Honda
et al.

Chairs: Shoichiro Okita(JAEA),
Michael L. Zerkle (Naval
Nuclear Lab.)
Thermal Neutron
Scattering Law of UBe13
and PuBe13
J.L. Wormald, M.L. Zerkle- 20 -

Impact on Criticality ofUsing Pure Water with
Coriumcoming from
Nuclear Reactor Core
MeltingAurélie Bardelay, Wilfried
Monange

JAEA-Conf 2024-001

Session 2: MONDAY, OCTOBER 2, 14:00 – 15:40
Room 1
Track 2NUCLEAR DATA
Chairs: Dimitri Alexandre
Rochman (PSI)
Tomoaki Watanabe(JAEA)
Automated, Reproducible
Data Processing,
Verification, andValidation at the NEA
Andrew Holcomb, Daniela
Foligno, Michael Fleming

Room 2
Track 8CRITICALITY
ACCIDENTS AND
INCIDENTS
Chairs: Hiroshi Okuno(JAEA)
Michael Laget (CEA)
A New Analysis of theWindscale Criticality
Accident Using
Monte-Carlo Code
MONK
Emma Sayce, Neil Harris,
Nathan Sayle

Room 3
Track 6OPERATIONAL
PRACTICES AND
SAFETY CASES
Chairs: Andrew B. Smiley(LANL)
Amy Elizabeth van der
Vyver (Sellafield)
JHR Fuel Storage Pool
Criticality Safety Analysis
Eric Fillastre, Georges
Kyriazidis, ManuelBergman et al.

Room 4
Special Session 1
FUKUSHIMA DAI-ICHINUCLEAR POWER
PLANT
Chairs: Aurélie Bardelay(IRSN)
Yasushi Nauchi (CRIEPI)
Criticality Control
Method for Fuel Debris
Retrieval in Fukushima
Daiichi NPP
Yasuhiro Harada, Makoto
Nakano, Yamato Hayashi
et al.

The TENDL Nuclear Data
Library: For Criticality
Calculations and MoreD. Rochman, A.J. Koning,
S.C. van der Marck

Multiphysics Analysis ofReactivity Changes due to
Solution Flow in the Past
Criticality Accident at
Windscale Works in 1970
Kodai Fukuda, Yuichi
YamaneProviding a Criticality
Warning System Omission
Case for a Legacy Reactor
Facility at AWE
Essam Mohammed, MarkA Roydhouse

Development of
Criticality Approach
Monitoring Method Using
Neutron Detectors for
Fuel Debris Retrieval in
Fukushima Dai-ichi NPP
Yamato Hayashi, Makoto
Nakano, Yuichi Morimoto

Comparison of Neutronic
Characteristics of BWR
Burnup Fuel between
JENDL-4.0 and JENDL-5
Tomoaki Watanabe,
Kenichi Tada, Tomohiro
Endo et al.

Preliminary analysis of
GODIVA supercriticaltransient behaviors byusing the Multi-region
Integral Kinetic code
including delayed neutron
effectHiroki Takezawa, Toru
Obara

Criticality Safety Analysisof the RECUMO Project
Gert Van den Eynde,
Mireille Gysemans,
Marijke Geerts et al.

Investigation of
Sub-criticality Monitoring
System Based on
Feynman-alpha Methodfor Large-Scale Fuel
DebrisSatoshi Wada, Makoto
Shimizu, Yamato Hayashi
et al.

Comparison of Calculated
Bare Critical Masses
between Two Versions of
the Japanese EvaluatedNuclear Data Library,
JENDL-5 and JENDL-4.0
Akito Oizumi

Sensitivity Analysis of theParameters inConsequence Analysis of
Postulated Fuel Debris
Criticality Accident inFukushima Dai-ichi NPP
Yuichi Yamane, Kenya
Suyama

EPEE: A Tool to Compare
the Moderating Efficiency
of a Material to the One of
Water
Aurélien Dorval, David
Noyelles, Michaël
Prigniau et al.

DetectorShielding-Moderator
Design Effect toEigenvalue Estimation
Results Based on
Feynman-a Method
Rei Kimura, Yamato
Hayashi, Makoto Shimizu- 21 -

JAEA-Conf 2024-001

Session 3: MONDAY, OCTOBER 2, 16:10 – 17:50
Room 1
Track 1CODES AND OTHERCALCULATIONMETHODS
Chairs: Michael Rising(LANL)
Yasunobu Nagaya (JAEA)
Novel Methods in MONK
for Criticality Modellingin Highly Disordered
Random HeterogeneousMedia
Jessica Fildes, Richard
Hiles, Brian Jones et al.

Room 2
Track 8CRITICALITY
ACCIDENTS AND
INCIDENTS
Chairs: Emma Louise
Sayce (UKNNL)
Kodai Fukuda (JAEA)
Generalized CAAS Probe
Positioning Methodology
for a Variety of Fissile
Material Processes
Adrien Gallozzi Ulmann,
Prosper Liu, Sasha
Philips et al.

Room 3
Track 6OPERATIONAL
PRACTICES AND
SAFETY CASES
Chairs: Tom Page
(Cerberus Nuclear)
Laurent Cholvy (CEA)
Review of the Facility
Criticality Safety Manager
Role at AWE
Andrew Buchan,
Christopher Hodkinson,
Paul Holloway et al.

Room 4
Special Session 1
FUKUSHIMA DAI-ICHINUCLEAR POWER
PLANT
Chairs: Catherine Percher(LLNL)
Yasushi Nauchi (CRIEPI)Development of the Fuel
Debris Criticality
Characteristics
Measurement System
Jun Nishiyama, Seiya
Manabe, Hideki Harano
et al.

Random Media Criticality
Analysis Methods inMonte Carlo Solver
SolomonTaro Ueki

Criticality Accident Alarm
System Modeling for the
Uranium Processing
Facility
M. Buttrey, S. Goluoglu,
K. Reynolds

Dealing with the Past andPresent – Criticality
Safety Considerations
Associated with Residues
Clean-up at the NNL
Preston Laboratory
Deborah Hill, Lauren
Flint, Martin Watson et al.

Estimation of 235U
Enrichment by Neutron
Induced Gamma Ray
Spectroscopy
Yasushi Nauchi, Shunsuke
Sato, Motomu Suzuki et al.

Overview of
NEA/WPNCS Activities
on Criticality Problems in
Random Media
Andrea Zoia, Jessica
Fildes, Brian Jones et al.

Using MCNP to Predict
Effects of a Postulated
Criticality Accident on
Personal Dosimetry
Mark N Neeley, Krista I
Kaiser, Matthew M.
Conrady

Criticality Control Flow
Diagram: Your NCS
Assessment in One
Diagram
Grégory Caplin, Raphaël
Reynaud, Gilles Neron de
Surgy

Critical Assemblies in
JAEA and the Role of the
New STACY
Hiroki Sono, Kazuhiko
Izawa, Tsutomu Yoritsune
et al.

Method for Criticality
Calculations andEstimation of the Fissile
Mass Based on the Theoryof Multiplicity Counting
Imre Pázsit, Victor Dykin,
Senada Avdič

Criticality Safety
Evaluation of HighRadioactive Liquid Waste
during the Evaporation to
Dryness Process at Tokai
Reprocessing Plant
Takatomo Miura, Atsunari
Kudo, Daisuke Koyama etal.

Criticality Safety Officer
Program at Technical Area
55 in Los Alamos
National Laboratory
Leah Berman, David
Kimball, James Bunsen

Debris-Simulated Core
Analysis under Fuel
Procurement Constraints
in New STACY
Experiments
Shouhei Araki, Satoshi
Gunji, Yu Arakaki et al.

- 22 -

JAEA-Conf 2024-001

Session 4: TUESDAY, OCTOBER 3, 8:30 – 10:35
Room 1
Track 1CODES AND OTHERCALCULATIONMETHODS

Room 2
Track 8CRITICALITY
ACCIDENTS AND
INCIDENTS

Room 3
Track 6OPERATIONAL
PRACTICES AND
SAFETY CASES

Chairs: Simon Richards(Jacobs)
Kenichi Yoshioka(Toshiba ESS)
Verification andValidation of the New
MCNP6.3 Criticality
Features
Michael E. Rising,Alexander R. Clark,
Jennifer L. Alwin

Chair: Mark N. Neeley(PNNL)
Hiroki Takezawa(Nagaoka Univ. of Tech.)
IRSN Progress on
Emergency Preparedness
and Response in Case of
Criticality Accident
Julien Rannou, Gaël
LoubertChairs: Essam
Mohammed (AWE)
Gert Van den Eynde (SCK
CEN)
Challenges in theDevelopment of the Metal
Purification Process at
Y-12
Benjamin Martin, Tom
Young, Chris Haught

Confirmation of ICSBEP
Benchmarking (LCT and
LST) Using MVP3 Code
Shigeaki Aoki

An Analysis of Criticality
Safety "Near Misses"
Fabien Duret, Matthieu
Duluc, Johann HerthDevelopment of Low
Enriched Uranium Plus
(LEU+) Enrichment
Capability and the
Associated Impacts on
Criticality Safety
Mark Savage, Charlotta
Sanders

Regulating Criticality
Safety in the UK:
Experience from Officefor Nuclear Regulation
Cross-sites Inspection
SeriesEoin Flannery, Clive
Ingram, Adam Nichols

Automating the
Production of Criticality
Handbook Curves
Sareena Hussain, Stuart
Watson, Monis Janjua etal.

Neutron Leakage, H/D,and Geometric Buckling
Changes in Containers
with Small H/D Ratios
Ashley R. Raster, Robert
D. Busch, John A. Miller

Development of a
Modular Storage of Non
Irradiated Mixed Oxide
Fuel
C. Jacques Gasnot, S.
Duquenne, G. Caplin

Strategies for Establishing
Adequate Subcritical
Margin for Cases
Involving Insufficient
Benchmark Data at
Enrichment and Fuel
Fabrication Facilities(HALEU Applications)
Jeremy W. Munson

Radiation Safety
Information
Computational Center: An
Information Analysis
Center for Nuclear
Criticality Safety
Timothy E. Valentine

Nuclear Criticality Safety
Lessons Learned from the
Rocky Flats Plant Fires
Patrick Huston, Kaelin
GloverNeutron Moderating
Materials Other than
Water: How, Why andWhen the Problems Arose
and the Solutions
Proposed by the CEA
Georgios Kyriazidis,
Aurelien Dorval
A Device Designed to
Detect Hydrogen inModeration Controlled
Wokshops
Olivier Ravat- 23 -

Room 4
Track 5
STANDARDS,ASSESSMENTMETHODOLOGY,REGULATIONS
Chairs: Alexander Lang(ORNL)David Noyelles (CEA)
A Competent Authority’s
View on Licensing andForeign Certificate
Validation of Transport
Packages for Fissile
Material
Dirk Schulze Grachtrup,
Benjamin Ruprecht

Assessment of a
Sophisticated PWR
Burn-up Credit
Application for a
Transport Cask Design
Benjamin Ruprecht, Dirk
Schulze Grachtrup
Development of a SKB
Burn-up Credit
Methodology for BWR
Fredrik Johansson, Jesper
Kierkegaard, John Loberg
et al.

JAEA-Conf 2024-001

Session 5: TUESDAY, OCTOBER 3, 11:05 – 12:45
Room 1
Track 1CODES AND OTHERCALCULATIONMETHODS

Room 2
Track 7
STORAGE,
TRANSPORT, ANDDISPOSAL ISSUES

Room 3
Track 4
MEASUREMENTS,
EXPERIMENTS, AND
BENCHMARKS

Chairs: Yi-Kang Lee(CEA)Kenya Suyama (JAEA)

Chairs: Michel Call
(USNRC)Tim Hicks (Galson
Sciences)
International Approaches
to Post-Closure Criticality
Safety : French Agency
Strategy
A. Feuerle

Chairs: Catherine Percher(LLNL)
Cheol Ho Pyeon (Kyoto
Univ.)
Status of the International
Criticality Safety
Benchmark Evaluation
Project
C. Percher, J.D. Bess, W.J.
Marshall et al.

Basis of 10CFR71.15(b)for Consideration into
SSR-6 Para. 417
Alexander Lang, Andrew
B. Barto, Douglas G.
Bowen

New Bateman Equation
Solvers in MENDEL
version 3.1
S. Lahaye, A. Anne, R.
Baron et al.

Comparison of Burn-up
Credit Methodologies for
Post-Closure Criticality
Safety Assessments Usinga Simplified Reference
Modelling Configuration
Jasdeep Bansal, Callum
Eldridge, Ahmed Shama etal.

The Case for and Against
a Gadolinium Bias in
SCALE: Round 2
W. J. Marshall, A. M.
Shaw, T. M. Greene et al.

International Standards
for Nuclear Criticality
SafetyBen Webborn, Douglas G.
Bowen, Grégory Caplin

Improvements of the
SCALE Testing
Framework
Shane W. D. Hart, Seth R.
Johnson, Robert A.
Lefebvre et al.

UK Perspective on
Post-Closure Criticality
Safety Assessments in the
Final Disposal of Higher
Activity Waste
Liam Payne, Stuart
Watson, Robert Mason etal.

Preliminary Model
Development in Support
of a New Criticality
Safety Benchmark for
HEU Metal Annuli and
Cylinders with Reflectorsof Three- to
Nineteen-Inch Thickness
Kathryn Worrell, Gabriel
Lentchner, John Mihalczo
et al.

New CEA Handbooks for
Criticality Safety
Assessment
Demonstrations
David Noyelles, Aurélien
Dorval, Michaël Prigniau

The CRISTAL Criticality
Package: from 2.0 towards
2.1 Version
Arnaud Entringer, Aurélie
Bardelay, Sébastien
Lahaye et al.

Swiss Perspective on
Post-Closure Criticality
Safety Assessments in the
Final Disposal of
High-Level Waste
Madalina Wittel, Susanne
Pudollek

A High-Fidelity
Benchmark of theAGN-201M Reactor at the
University of New
MexicoRowdy Davis, Christopher
M. Perfetti, Larry L.
Wetzel et al.

Evaluation of the
Sum-of-Fractions
Methodology for Water
and Polyethylene
Moderated Systems
Travis J. Zipperer, Andrew
W. Prichard, Travis M.
Greene et al.

Recent Developments to
MONK® and Visual
Workshop for Criticality
Safety Applications
Simon Richards, Adam
Bird, Andrew Cox et al.

- 24 -

Room 4
Track 5
STANDARDS,ASSESSMENTMETHODOLOGY,REGULATIONS
Chairs: Dirk Schulze
Grachtrup (BASE)
Eoin Flannery (ONR)JAEA-Conf 2024-001

Session 6: TUESDAY, OCTOBER 3, 14:00 – 16:05
Room 1
Track 2NUCLEAR DATA
Chairs: Coralie Carmouze(CEA)
Kenichi Tada (JAEA)

Room 2
Track 7
STORAGE,
TRANSPORT, ANDDISPOSAL ISSUES
Chairs: Adrien Feuerle(ANDRA)
Madalina Wittel (Nagra)

Room 3
Track 6OPERATIONAL
PRACTICES AND
SAFETY CASES
Chairs: Aurélien Dorval(CEA)
Deborah Ann Hill
(UKNNL)
Altering the Requirement
to Assay Waste Drums
containing Plutonium
Contaminated Material at
Sellafield Ltd.
Amy van der Vyver,
Michael Hobson

Room 4
Track 4
MEASUREMENTS,
EXPERIMENTS, AND
BENCHMARKS
Chairs: Jesson Hutchinson(LANL)
Shouhei Araki (JAEA)FP Concentrations
Evaluation With FPY Data
Considering Fission Rate
Spectrum
Kohei Matsuo, Takanori
Kitada, Satoshi Takeda etal.

A Criticality Analysis for
Disposal Canister
Considering Fuel Burnup
and Iron Corrosion EffectShin Sung Oh, Kyu Jung
Choi, Ser Gi Hong

Consistent Nuclear Data
Evaluations for Criticality
SafetyI. Stetcu, T. Kawano, A. E.
Lovell et al.

The United States
Perspective on
Post-Closure Criticality
Safety Assessments in the
Final Disposal of
High-Level Waste
Laura Price, Kaushik
Banerjee

Burnup Credit Criticality
Safety Case for AGR
Spent Fuel Storage
James Ryan, Albrecht
Kyrieleis, Jennifer
Bateman et al.

Criticality Experiments to
Reduce Compensating
Errors in Plutonium
Nuclear Data
J. Hutchinson, J. Alwin, B.
Bell et al.

Nuclear Data for Neutron
Criticality Applications at
GELINA
P. Schillebeeckx, C.
Camouze, S. Kopecky etal.

Refinement of the
Loading Curve
Determination
Methodology andModeling for Swiss PWR
Spent Fuel Final Disposal
Canisters
M. Frankl, A. Vasiliev, D.
Rochman et al.

Criticality Safety of Orano
La Hague Dissolver
Rinsing Operations
Y. Blin, C. Quenault, R.
Vassieux et al.

The EUCLID Experimentand Nuclear Data LibraryComparisons
Nicholas W. Thompson,
Jesson Hutchinson,
Jennifer Alwin et al.

Inter- Codes and Nuclear
Data Comparison under
Collaboration Works
between IRSN and JAEA
Satoshi Gunji, Shouhei
Araki, Tomoaki Watanabe
et al.

Criticality Safety for UK
Spent Fuel Disposal in the
Post-Closure Phase of a
Geological Disposal
Facility
Robert Mason, Albrecht
Kyrieleis, Lynn Grindrod
et al.

Lessons Learned From
Ventilation and Glovebox
Flooding Via Overfillingof the Wet Vacuum
System in a Plutonium
Facility
Andrew Smiley, Amanda
Bowles Tomaszewski,
Michael Corum

Reactivity Coefficient
Measurements to Aid in
Reducing Compensating
Errors in Plutonium
Nuclear Data
T. Cutler, J. Alwin, M.
Grosskopf et al.

Dependence of the
Average Total Kinetic
Energy of Fission
Fragments on Incident
Neutron Energy Studied
by a 4D Langevin Model
Kazuya Shimada, Chikako
Ishizuka, Satoshi Chiba

Criticality Safety for UK
Spent Fuel Disposal in the
Pre-Closure Phase of a
Geological Disposal
Facility
Liam Payne, Andrew
Price, Steven Lonsdale etal.

- 25 -

Optimization Algorithm
for Criticality Experiment
Design Using Whisper
Cole Kostelac, Ayodeji
Alajo, Nicholas Thompson

JAEA-Conf 2024-001

Session 7: WEDNESDAY, OCTOBER 4, 8:30 – 10:35
Room 1
Track 1CODES AND OTHERCALCULATIONMETHODS
Chairs: Shane W. D. Hart
(ORNL)
Shigeaki Aoki (MNF)
Application of an
Empirical Density Law
via Python for Aqueous
Plutonium Chloride
Systems in MCNP6
Riley Bulso, Jennifer
Alwin, Christopher
Perfetti et al.
Application of a Density
Law via Python for
Aqueous Plutonium
Nitrate Systems in
MCNP6
Tara Robertson, Jennifer
Alwin, Christopher
Perfetti et al.
Criticality Calculations of
Spent Fuel Storage Poolwith Water Holes
S. Duquenne, Y. Blin, B.
Checiak et al.

Method and CodeDevelopment for the
Nuclide Composition
Evaluation of Commercial
PWR Spent Fuel
Assembly
Liangzhi Cao, Senhan
Yang, Yunzhao Li

Room 2
Track 7
STORAGE,
TRANSPORT, ANDDISPOSAL ISSUES
Chairs: Jérémy Bez(IRSN)
Liam Payne (Nuclear
Waste Services)
GMIT: A Tool to Support
Post-Closure Criticality
Safety Assessments
E. Adam Paxton, Jiejie
Wu, Tim Hicks et al.

Room 3
Track 9
PROFESSIONAL
DEVELOPMENT
ISSUES AND TRAINING
Chairs: Cheol Ho Pyeon(Kyoto Univ.)
Dominic Winstanley(Sellafield)
Collaboration of Nuclear
Criticality Safety and
Accident Dosimetry inPlanning and Exercise
Development
Matthew M. Conrady

Revision of the Dounreay
Low Level Waste
Disposal Facilities
Operational andPost-Closure Criticality
Safety Assessment
Tamara Baldwin, Tim
Hicks, Emily
Swain-Phipps et al.
German Perspective on
Post-Closure Criticality
Safety Assessments in the
Final Disposal of
High-Level Waste
Christian Herold, Florian
Voigts, Sabine Unger

Development of Two
Educational Calculation
Codes Monte Carlo
Calculation Code S-Monteand Diffusion Calculation
Code S-Dif
Tetsuo Matsumura,
Takanori Kameyama

Gamma-ray
Measurements from
Pulsed-Neutron Die-Away
Experiments (PNDA)
Ruby Araj, DanielSiefman, Lee Bernstein etal.

Implementation of
CARTA into Criticality
Training Programmes
Katrina Christaki, Stewart
Hay, Toby Tyas

Thermal Pulsed Neutron
Die Away Experiments in
Salt Water
Valeria Raffuzzi, DanielSiefman, Lee Bernstein

Initial Considerations on
Potential Optimisation
Options of Spent Fuel
Disposal Canisters Taking
into Account Post-Closure
Criticality Safety
Madalina Wittel, Valentyn
Bykov, Maksym Chernykh
et al.

In Silico Versus in Situ theChallenging Landscape of
Nuclear Criticality Safety
Training
David K. Hayes

Inherently Safe
Subcritical Assembly Lite
Samuel T. Varghese,
William Zywiec

Nagra’s Approach to
Post-Closure Criticality
Safety Case Development
within the High-Level
Waste Repository
Programme Roadmap
Madalina Wittel, Susanne
Pudollek

Overview and Current
Progress of the
DOE/NNSA Nuclear
Criticality Safety Program
Training and Education
Program
Douglas G. Bowen

Fast Spectrum Reactivity
Worth Measurements in
STEK
Steven van der Marck,
Arjan Koning- 26 -

Room 4
Track 4
MEASUREMENTS,
EXPERIMENTS, AND
BENCHMARKS
Chairs: Steven C. van derMarck (NRG)
Kenichi Tada (JAEA)
High Multiplication
Neutron Noise
Measurements Using theSeven Percent Critical
Experiment 7uPCX
Nicholas Whitman, Tanner
Heatherly, Jesson
Hutchinson et al.

JAEA-Conf 2024-001

Session 8: WEDNESDAY, OCTOBER 4, 11:05 – 12:45
Room 1
Track 1CODES AND OTHERCALCULATIONMETHODS

Room 2
Track 7
STORAGE,
TRANSPORT, ANDDISPOSAL ISSUES

Room 3
Track 9
PROFESSIONAL
DEVELOPMENT
ISSUES AND TRAINING

Chairs: TBD
Taro Ueki (JAEA)

Chairs: Tamara Baldwin(Galson Sciences)
Pedro Ortego (SEA)

Adapting CLUTCH
Methodology toMultigroup
TSUNAMI-3D for
Eigenvalue Sensitivity
Calculations
K. B. Bekar, W. J.
Marshall

Exotic Fuels Transport
Challenge
Albrecht Kyrieleis,Andrew Thallon, Ahmed
Aslam

Chairs: Shauntay Coleman(LLNL)
Hiroki Takezawa(Nagaoka Univ. of Tech)
A Guide for Criticality
Safety Training andAwareness of Personnel
Working in Nuclear
Installations
Clement Lopez, Fleur
Lespinasse, Laurent
Cholvy et al.

Verification and
Performance Impact of the
New Parallel MCNP6.3
Particle Track Output
Capability for Subcritical
Multiplication
Simulations
Michael E. Rising,Nicholas H. Whitman,
Jesson D. Hutchinson

Criticality Risk
Associated with the Bulk
Deployment of Powder
Extinguishants
Jennifer Bateman, Holly
Pearson, Dan Johnson

Development of Nuclear
Criticality Staff at PacificNorthwest National
Laboratory
Krista I Kaiser

Methods to Determine
Burst Repeatability for
Godiva IV
Joetta Goda, Robert Allen
Weldon Jr, Travis Grove etal.

TRIPOLI-4® Neutron
Multiplication
Calculations for the
Subcritical Experimentsof the BeRP Ball
Reflected by Tungsten
Yi-Kang Lee,
François-Xavier Hugot

High Assay Low Enriched
Uranium Transportation
Packages Under 10 CFRPart 71 – U.S. NRC
Research and Certification
Activities
Andrew B. Barto, Michel
Call

Ensuring the
Sustainability of
Criticality Safety
Expertise
Dominic Winstanley

Quantifying Burst
Repeatability for Godiva
IV
Robert Allen Weldon Jr,
Joetta Goda, Travis Groveet al.

Use of SCALE MAVRIC
Radiation Transport
Calculations for the
Design of a Subcritical
Assembly at Oak Ridge
National Laboratory
M. N. Dupont, A. Lang, D.
Bowen

Increased Flexibility for
Reflectors Near Storage
Arrays of Fissionable
Items at Sandia
William M. Cook, Elijah
C. Lutz, Ashley R. Rasteret al.

A Look at a “Quid Pro
Quo” NCS Assessment
CultureJohn A. Miller, David P.
Heinrichs, Mark N.
Neeley et al.

Experiment Design andPreparation for a
Shielding Benchmark
Utilizing Godiva-IV
Garrett McMath, Tyler
Borgwardt, Riley
Cumberland et al.

- 27 -

Room 4
Track 4
MEASUREMENTS,
EXPERIMENTS, AND
BENCHMARKS—A Memory of GaryHarms—
Chairs: Mariya
Brovchenko (IRSN)
Akito Oizumi (JAEA)
Molybdenum SleeveExperiments in the Sandia
Critical Experiments
Facility
Gary A. Harms, David E.
Ames, Nicolas Leclaire etal.

JAEA-Conf 2024-001

Session 9: WEDNESDAY, OCTOBER 4, 14:00 – 15:40
Room 1
Track 3
UNCERTAINTY ANDSENSITIVITYANALYSIS
Chairs: Alexander
Vasiliev (PSI)
Shuhei Maruyama (JAEA)

Room 2
Track 7
STORAGE,
TRANSPORT, ANDDISPOSAL ISSUES
Chairs: John Bess (JFoster& Associates)
William M. Cook (SNL)

Room 3
Track 10
FUTURE CHALLENGES

Nuclear Data Sensitivity
Analysis of a Sodium
Shielding Experiment
Based on Generalized
Perturbation Theory for
Data Assimilation
Shuhei Maruyama,
Tomohiro Endo, Akio
Yamamoto

Assessment of Validationfor Burnup Credit
Calculations for LEU+
and High Burnup FuelM. N. Dupont, C. Celik, A.
Lang et al.

Sensitivity andUncertainty-Based
Techniques to Extend the
Database of Experimental
Validation Benchmarks:
Practical Example of“IEU” Slabs
T. Albert, Q. Vuyet, C.
Rechatin et al.

Criticality Safety
Recommendations for theTreatment of Extended
Enrichment and HighBurnup Fuel for Storage
and Transportation
Systems
Alex Shaw, Nicholas
Kucinski, Briana Hiscox

Effect of Nuclear Data
Library on Criticality andTransmutation
Characteristics in Fluoride
Molten Salt Reactor
Koji Fujikura, Naoto
AizawaFuture of the MUSiC
Experiment Data
George McKenzie, Flynn
Darby, Jesson Hutchinson
et al.

Efficient Uncertainty
Quantification Using
Deterministic Sampling
Method with Simplex
Ensemble and Scaling
MethodTomohiro Endo, Akio
Yamamoto

The Importance ofTransport Criticality
SafetyCharlotte Davis, Michelle
Nuttall

MCNP-6 Criticality
Comparison of Additive
Manufacturing Techniques
for the Fabrication ofMetallic Nuclear Fuels
Patrick J. Moo

Towards an Era of Low
Temperature Integral
Critical Experiments:
Surrogate Testing of
Low-Temperature TEX
Configurations
Eric Aboud, Paul
Yap-Chiongco, Jesse
Norris et al.

Uncertainty
Quantification of a and g
Emission Spectra
S. Lahaye, T.D. Huynh, A.
Tsilanizara

Consideration of
Agglomeration of Low
Enriched Fissile Materials
and the Detrimental Effecton Package Payloads/CSI
Michelle Nuttall,Charlotte Davis

Chairs: Rei Kimura(Toshiba ESS)
Dominic Winstanley(Sellafield)
Preliminary Study of
Burnup Measurement andRelative PowerDistribution in the HTTR
Using Gamma-Ray
Measurement
Irwan L. Simanullang,
Shohei Kawaguchi,
Nozomu Fujimoto et al.

- 28 -

Room 4
Track 4
MEASUREMENTS,
EXPERIMENTS, AND
BENCHMARKS
Chairs: Rene G. Sanchez(LANL)
Masahiro Fukushima(JAEA)
MUSiC: Critical
Experiment with Bare
Highly Enriched Uranium
Shells Benchmark
Rene Sanchez, George
McKenzie, Alexander
McSpaden

Neutronic Characteristicsof the Low-Temperature
TEX Design and Proposed
Configurations
Jesse Norris, Catherine
Percher, Eric Aboud et al.

JAEA-Conf 2024-001

Session 10: WEDNESDAY, OCTOBER 4, 16:10 – 17:50
Room 1
Track 3
UNCERTAINTY ANDSENSITIVITYANALYSIS
Chairs: Axel Hoefer(Framatome)
Tangi Nicol (CEA)

Room 2
Track 7
STORAGE,
TRANSPORT, ANDDISPOSAL ISSUES
Chairs: Charlotte Davis(NTS)
Matthias Frankl (PSI)

Experimental Correlation
Estimation and Their Role
in Transposition Method
Tangi NICOL, Alexandre
DEPLORTE, Julien
PIETRI

Impact of Recent ENDF
Nuclear Data on Burnup
Credit Criticality Safety
AnalysesW. A. Metwally, M. N.
Dupont, W. J. Marshall etal.

Validating Mixtures ofU, 235U, and 239Pu for
the Sum-Offractions
MethodT. M. Greene, A. Lang, W.
J. Marshall

The Modelling of LEU
Heterogeneous Systems as
Tetrahedral Arrays in
MONK®, SCALE andMCNP® and the Impact ofHeterogeneity on Runtime
Stuart Watson, Simon
Richards, Monis Janjua

Towards a Direct
Comparison of Practical
CSE with BUC
Approaches: Benchmark
Proposal for a
Pseudo-application Casewith User-defined NCS
Criteria
A. Vasiliev, M. Frankl, D.
Rochman et al.

TEX-HEU & TEX-Hf:
Critical Assemblies with
Highly Enriched Uranium,
Polyethylene, andHafnium
Jesse Norris, Catherine
Percher, David Heinrichs
et al.

Impact of Correlations
Between Experiments on
the Evaluation of Bias due
to Nuclear Data by
Assimilation
Methodologies
Frédéric Fernex, Nicolas
Leclaire, Aurélie Bardelay
et al.

Evaluation of the
ARIANE Samples
Irradiated in Gösgen
Reactor
Pedro Ortego

Criticality Analyses of the
PWR Core with Accident
Tolerant Fuel
Agnieszka Boettcher,
Zuzanna Marcinkowska

Verification andValidation of Monte Carlo
Simulations Using SwissPWR HZP Data
L. Berry, A. Vasiliev, M.
Hursin et al.

Bias and Correlated Data,
Comparison of Methods
A. Hoefer, M. Stuke, H. S.
Abdel-Khalik et al.

Impact of Low
Temperatures on
Criticality Safety
Assessments for Fissile
Material Transportation
Jeremy Bez, Marcel Tardy,
Aurélie Bardelay et al.

233

Room 3
Track 10
FUTURE CHALLENGES
Chairs: Naoto Aizawa(Tohoku Univ.)
Irwan Liapto Simanullang(Kyusyu Univ.)
IRSN Review ofExperimental Needs for
Nuclear Criticality Safety
Aurélie Bardelay,
Jean-Baptiste Clavel,
Wilfried Monange et al.

- 29 -

Room 4
Track 4
MEASUREMENTS,
EXPERIMENTS, AND
BENCHMARKS
Chairs: Jesse D. Norris(LLNL)
Kotaro Tonoike (JAEA)
Experiments to Measure
the Effect of Tantalum on
Critical Systems
David E. Ames, Gary A.
Harms, Elijah Lutz et al.

Plutonium Chloride
Solution Characterization:
Impacts on Density fromPu Oxidation States andSaturation Effects
Kelly E. Aldrich, Kimberly
B. Muscarella, Justin N.
Cross et al.

JAEA-Conf 2024-001

Session 11: THURSDAY, OCTOBER 5, 8:30 – 10:35
Room 1Room 2
Track 3
Track 7
UNCERTAINTY AND
STORAGE,SENSITIVITY
TRANSPORT, AND
ANALYSISDISPOSAL ISSUES
Chairs: Jun-Shuang FAN
Chairs: W. A. Metwally(Hokkaido Univ.)(ORNL)
Travis Greene (ORNL)
Stuart Watson (3T Safety
Consultant)
Deterministic-Monte Carlo
Micro-SMR LEU+
Hybrid Methods forOnce-through Fuel Cycle
Eigenvalue Sensitivity
Spent Fuel Actinides
Coefficient Calculations
Characteristics
T. M. Greene, K. Bekar, W.
Verification
J. MarshallJohn Bess, Gray Chang,
Mie Hiruta et al.

Room 3Special Session 2
MACHINE LEARNING,
DEEP LEARNING
Chairs: Justin Clarity(PNNL)
Arnau Albà Jacas (PSI)
Uncertainty
Quantification on Spent
Nuclear Fuel with LMC
Arnau Albà, Andreas
Adelmann, Dimitri
Rochman

Overview of Spent Nuclear
Fuel Inventory Results for
the ARIANE GU3 Sample
C. Carmouze, R. Ichou, G.
Ilas et al.

Criticality of Poisoned
Cells for Underwater
Spent Fuel Storage
B. Checiak, G. Caplin, Y.
Blin et al.

Applicability of Machine
Learning to Criticality
Charpentier-Süter Alexis,
Gaudin Gérald, ArphantNicolas et al.

A Study of Model
Dependence in Burnup
Credit Criticality Safety
Analysis
Axel Hoefer, Stefan
Glaubrecht

Decay Heat Calculation
for Efficient Storage of
Spent Nuclear FuelShunsuke Sato, Yasushi
Nauchi

Progress Toward theDevelopment of an
Artificial Neutral Network
for Rapid Post-Closure
Reactivity Analysis
Justin Clarity, Harish
Gadey, Peter Stefanovic etal.

Investigating Similarity
Differences forLight-Water Moderated
andPolyethylene-Moderated
Systems
T. M. Greene, W. J.
Marshall
Lost and Found
Opportunities Around the
Chlorine Worth Study
W. J. Marshall

Decay Heat of IrradiatedNuclear Fuels – A Status
Report from the NEA
WPNCS
D. Rochman, A. Algora,
Ø. Bremnes et al.

Criticality Experiment
Design for the Molten
Chloride Reactor
Experiment Facility
Michael Branco-Katcher,
Daniel Siefman, Todd S.
Palmer et al.

Comparative Study of the
Impact on the Nuclear
Criticality Safety of theBoron and Burnup Credit
in Pools of Spent Fuel
Assemblies from PWR
Nuclear Power Plants
Alberto Ottonello,Marie-Pierre Fontaine,
Nicolas Slosse

The Prediction of the
Critical Parameters of
Post-Processing
Non-uniform Conditions
based on Improved BP
Neural-Network
Liang Song, Sun Ming-ze,
Cheng Yu-ting et al.

- 30 -

Room 4

No presentations

JAEA-Conf 2024-001

Poster Session: TUESDAY, OCTOBER 3, 16:10 – 17:50, Exhibition Hall 1
Track 1: CODES AND OTHER CALCULATION METHODS
P-01 The Construction of a Quantitative Comparison of
Bobbi Riedel, Christopher
Upper Subcritical Methods for Novel Neutronic
Perfetti
Systems
P-02

Nuclear Criticality Safety Analogue “Tool” forApproximating Subcritical Equipment and Process
Designs and Operations Limits

Calvin M. Hopper, Megan
Pritchard, Cecil V. Parks

P-03

GRS Handbook on Criticality – Digital Version HBcrit

Fabian Sommer

P-04

A Burnup Calculation System Coupled with MCNP and
SCALE/ORIGEN

Kenichi Yoshioka, Satoshi
Wada, Shunichiro Omika

P-05

Temperature Reactivity Feedback Coefficient for the
MYRRHA Critical Core – Design Revision 1.8

L. Fiorito, A. Peñalosa, M.
Zanetti et al.

P-06

Stochastic Neutronics Simulations Using Deterministic
Transport With N-Forked Fission Branching
Approximations

Philippe Humbert

P-07

Cyclone – New Features for Criticality Safety Analyses

P-08

Solution to Random-Media Criticality Benchmarks witha Monte Carlo Solver Solomon

Stewart Hay, Carl Hughes,Peter Taylor
Yasunobu Nagaya

Track 2: NUCLEAR DATA
P-09 Linearization of Thermal Neutron Scattering Cross
Section to Optimize the Number of Energy Grid Points

Kenichi Tada

P-10

The First Core Criticality Analysis of the RSG GASMultipurpose Research Reactor using the Newly
Released JENDL-5 Nuclear Data Library

Peng Hong Liem, DonnyHartanto

P-11

Nuclear Data Sensitivity Analysis of Post-Irradiation
Examination Data with Fuel Depletion Calculation
Module CBZ/Burner

Yuya Inagaki, Go Chiba,
Keita Yoshikawa et al.

Track 3: UNCERTAINTY AND SENSITIVITY ANALYSIS
P-12 Adjustment of Uncertain Modeling Parameters throughAnalyses of Post-Irradiation Examination Data

Keita Yoshikawa, Go Chiba,
Yuya Inagaki et al.

P-13

On the PSI Routine Criticality Safety Evaluation
Methodology and its Validation Approach

A. Vasiliev, H. Lee, M. Frankl
et al.

P-14

A Method to Estimate Burnup Using Enrichment(IE),
Cooling Time(CT) and TNSI(Total Neutron Source
Intensity) in Spent Fuels : Apply to MCNP Neutron
Detection

Kwangheon Park, So hee
Cha

P-15

Data Assimilation Using Prompt Neutron Decay
Constant α for Water to Reduce Uncertainties due to
Thermal Neutron Scattering Law

Yoshinari Harada, Hibiki
Yamaguchi, Tomohiro Endoet al.

- 31 -

JAEA-Conf 2024-001

Track 4: MEASUREMENTS, EXPERIMENTS, AND BENCHMARKSP-16
AFRRI TRIGA Reactor Neutron and Gamma Dose
Aaron Sun Tamashiro, Philip
Characterization Preliminary Results
Angus, David Heinrichs et al.
P-17

Analysis of the MUSiC 3He Multiplicity Data

P-18

Canceled

P-19

Benchmark Analyses on Control Rod Worths of
TRIGA Reactor Modeled in the ICSBEP Handbook
Using Continuous-Energy Monte Carlo Code MVP
Version 3

Hiroshi Yanagisawa, Miki
Umeda, Yuiko Motome et al.

P-20

An Alternative to Solution Experiments for Nuclear
Data Validation & Training: Reflection and Interactionof Juxtaposed Uranium (RAIJU) Experiment Design

Kelsey Amundson, Nicholas
ThompsonP-21

Pu Oxalate Slurries – A Potential Bounding Condition
for Aqueous Chloride Processes

Kimberly B. Muscarella, Kelly
E. Aldrich, Dung M. Vu et al.

P-22

Design of TEX-MOX Critical Experiments Varying
Neutron Spectrum

M. Brovchenko, J. Bez, M.
Daury et al.

P-23

Nano Second Pulsed Die-Away Experiments for
Nuclear Data Validation

Valeria
Raffuzzi,
DanielSiefman, Lee Bernstein

P-24

Design of a UO2-BeO Critical Experiment at Sandia

William M. Cook, Elijah C.
Lutz, David E. Ames et al.

Alex
McSpaden,JessonHutchinson, George McKenzie
et al.

Track 5: STANDARDS, ASSESSMENT METHODOLOGY, REGULATIONS
P-25
Updates of the French Criticality Safety Analysis
Fabien Duret, Matthieu Duluc,
Guide And Event Database (LOGIC)
Aurélie Bardelay
P-26

LICORNE: A Useful Software for Criticality Safety
Reference Values

Track 6: OPERATIONAL PRACTICES AND SAFETY CASES
P-27
Criticality Assessment of Borosilicate Raschig Rings
Poisoned Tanks Dismantling- 32 -

Wilfried Monange,
BardelayAurélie

Laurent Zambelli, Patrick Pin,
Michaël Gal et al.

JAEA-Conf 2024-001

Track 7: STORAGE, TRANSPORT, AND DISPOSAL ISSUES
P-28 Investigation of the Specific keff Behaviour in Simplified
Corrosion Scenarios for a Potential PWR Final Disposal
Canister Design

M. Frankl, A. Vasiliev, L.
Berry et al.

P-29

Evaluation of the Fukushima Daini 2F2 8x8-4 Samples

Pedro Ortego

P-30

The Benefits of a Multiple Water Barrier Design Transport
Package

Michelle
Davis

Nuttall,Charlotte

P-31

Effects of Low Temperature on Transport Criticality Safety

Charlotte
Nuttall

Davis,

Michelle

P-32

Criticality Sensitivity Analysis for the Standard Waste
Transport Container 255 (SWTC-255)

Charlotte Davis, Michelle
Nuttall, Michael Hobson et al.

Track 8: CRITICALITY ACCIDENTS AND INCIDENTS
P-33 Comparison of Computational and Experimental Resultsfor Criticality Accident Alarm Placement
P-34

The CAAS-3S Criticality Accident Alarm System
Dose-Rate Feature

Alan J. Yamanaka, Soon S.
Kim, Shauntay Coleman
Sasha Philips, Adrien Gallozzi
Ulmann, Prosper Liu et al.

Track 9: PROFESSIONAL DEVELOPMENT ISSUES AND TRAINING
P-35 Interface of Criticality Safety with Other Transport
Charlotte
Disciplines
Nuttall

Davis,

Michelle

P-36

Professional Development of NCS Staff: Benefits of Going
beyond Technical and Regulations

John A. Miller, Robert D.
Busch, Ashley R. Raster et al.

P-37

Nuclear Criticality Safety through Training, Organizationaland Human Factors Integration and Feedback, at Orano
Recyclage Reprocessing Plant

Patrick
PIN,
Bérengère
MARTIN, Rémi VASSIEUX

P-38

Criticality Safety Evaluation Project Development for
University of California Berkeley Nuclear Criticality Safety
Pipeline Course

Shauntay
Coleman,
Alan
Yamanaka, William Zywiec

P-39

Problem-Based Learning Program of Reactor Physics
Experiment to Measure Subcriticality for an Unknown
SystemShunya Teratani, Yoshinari
Harada, Kaito Mori et al.

- 33 -

JAEA-Conf 2024-001

Special Session 1: FUKUSHIMA DAI-ICHI NUCLEAR POWER PLANT
P-40
Study on Criticality Safety Control of Fuel Debris for
Kenya Suyama, Taro Ueki,
Validation of Methodology Applied to the Safety
Satoshi Gunji et al.
Regulation
P-41

Progress of Modification Work of the Static
Experiment Critical Facility (STACY) and Preparation
for First Series of Critical Experiments under the New
Regulatory Standards of Japan

Kazuhiko Izawa, Junichi Ishii,
Masakazu Seki et al.

P-42

Status on the Development of the Fabrication andAnalysis Equipment of the Pseudo Fuel Debris

Fuyumi Kobayashi, Hiroyuki
Fukaya, Kazuhiko Izawa et al.

P-43

Planning of the Debris-Simulated Critical Experimentson the New STACY

Satoshi Gunji, Shouhei Araki,
Yu Arakaki et al.

P-44

Preliminary Analysis of Randomized Configuration
Patterns in Modified STACY Core

Shigeki Shiba, Daiki Iwahashi,
Tsuyoshi Okawa et al.

P-45

Preliminary Analyses of Modified STACY Core
Configuration Using Serpent With JENDL-5

Maho Kawaguchi, Shigeki
Shiba, Daiki Iwahashi et al.

Special Session 2: Machine Learning, Deep Learning
P-46
Missing Rods Pattern Optimization in LWR Fuel
Assembly Using a Genetic Algorithm Coupled with
Heterogeneous TRIPOLI-4® Monte Carlo Calculations

J. Dupas, D. Noyelles, M.
Prigniau- 34 -

JAEA-Conf 2024-001

13. Poster Evaluation
We had 45 posters in total. To facilitate the poster session, the local organizer managed the poster
evaluation presented in the closing plenary session, asking volunteers for online evaluation. Sum ofscores of three viewpoints: Technical value - 5, Quality of Poster - 5 and Quality of Presentation – 5 isused for over whole evaluation. Overall Average Score was 9.77. We selected +12 is exceptional posterand +11 is highly evaluated poster. Following is the seven selected posters.
Exceptional Posters

P-38 S. Coleman, A. Yamanaka, and W. Zywiec, “Criticality Safety Evaluation Project
Development for University of California Berkeley Nuclear Criticality Safety Pipeline Course
Most Interested.”

P-15 Y. Harada, H. Yamaguchi, T. Endo, and A. Yamamoto, “Data Assimilation Using Prompt
Neutron Decay Constant α for Water to Reduce Uncertainties due to Thermal Neutron Scattering
Law.”



P-37 P. Pin, B. Martin and R. Vassieux, “Nuclear criticality safety through training, organizationaland human factors integration and feedback, at Orano Recyclage La Hague reprocessing plant.”

Highly Evaluated Posters

P-22 M. Brovchenko, J. Bez, M. Daury and J.-C. Latche, “Design of TEX-MOX criticalexperiments varying neutron spectrum.”P-33 A. Yamanaka, S. Kim and S. Coleman, “Comparison of Computational and Experimental
Results for Criticality Accident Alarm Placement.”

P-36 J. A. Miller, R. D. Busch and A. R. Raster and J. Cole, “Professional Development of NCS
Staff: Benefits of going beyond technical and regulations.”P-45 M. Kawaguchi, S. Shiba, D. Iwahashi, T. Okawa, S. Gunji, K. Izawa and K. Suyama,“Preliminary Analyses of Modified Stacy Core Configuration using Serpent with JENDL-5.”- 35 -

JAEA-Conf 2024-001

14. Summary of Submission and Participation
Tables 2 and 3 show the status of paper submission and participation country by country.
Table 2: Submission; country by country (2003 means ICNC2003 in Tokai-mura)Country

2003

2023

Belgium

2

4

China

1

2

Czech

2

France38

GermanyCountry

2003

2023

Poland-1

Russia

18

-

Spain

-

2

39

Sweden-2

6

6

Switzerland

2

11

Hungary

2

-

UK

18

33

Indonesia

1-

Ukraine

3

-

Japan

41

46*

USA

18

74

Korea

3

2

IAEA

1

-

Netherlands

1

1

OECD

2

1*

Sum

159

224*

*including opening plenary
Table 3: Participants in Technical Session; country by country (2003 means ICNC2003 in Tokai-mura)County2003

2023

County2003

2023

County2003

2023

Austria

10Indonesia

10

Switzerland

2

8

Belgium

3

2

Japan

78

67

UK

16

33

Canada

0

3

Korea

3

17

Ukraine

1

0

China

2

2

Netherlands

1

1

USA

25

75

Czech

2

0

Poland01Vietnam10Finland0

2

Russia

8

0

IAEA

1

0

France33

39

South Africa

10OECD/NEA

1

3

Germany

6

9

Spain

2

1

Hungary20

Sweden

2

10

Sum

192

273

- 36 -

JAEA-Conf 2024-001

15. Sponsors
Diamond Sponsor

IRSN - Institut de Radioprotection et de Sûreté Nucléaire
31, avenue de la division Leclerc - 92260 Fontenay-aux-roses –Francehttps://en.irsn.fr/

Gold Sponsors

Framatome
Framatome head office 1 Place Jean Miller – Tour Areva 94200
Courbevoie, France
https://www.framatome.com/en/

Toshiba Energy Systems & Solutions Corporation
72-34, Horikawa-cho, Saiwai-ku, Kawasaki-shi, Kanagawa,
212-8585, Japan
https://www.global.toshiba/ww/company/energy.html

Hitachi-GE Nuclear Energy, Ltd.
1-1, 3-chome, Saiwai-cho, Hitachi-shi, Ibaraki, 317-0073, Japan
https://www.hitachi-hgne.co.jp/en/index.html

Mitsubishi Heavy Industries, Ltd.
2-3, Marunouchi 3-chome, Chiyoda-ku, Tokyo, 100-8332, Japan
https://www.mhi.com/- 37 -

JAEA-Conf 2024-001

Bronze Sponsors

Mitsubishi Nuclear Fuel (MNF)
622-1, Funaishikawa, Tokai-mura, Naka-gun, Ibaraki, 319-1197,
Japan
https://www.mhi.com/group/mnf/

Studsvik
SE-611 82 Nyköping, Sweden
https://www.studsvik.com/

Taylor & Francis Group
9th floor JHV Building, 1-54-4, Kanda Jimbocho, Chiyoda-ku,
Tokyo, Japan (Taylor & Francis (Japan) )https://taylorandfrancis.com/

Journal of Nuclear Science and Technology with
Taylor & Francis Group
Taylor & Francis Group 4 Park Square Milton Park Abingdon
OX14 4RN, UK
https://www.tandfonline.com/tnst20- 38 -

JAEA-Conf 2024-001

16. Full Papers in Appendix
All full papers were provided for conference participants via the Internet until the end of 2023. This
report contains 214 full papers in the appendix. This excludes the following ten papers from the full listof 224, of which the authors decided not to include their papers in this report.
[1] Satoshi Gunji et at., “Study on the Basic Core Analysis of the new STACY.” (OpeningPlenary)[2] Riley Bulso et at., “Application of an Empirical Density Law via Python for Aqueous Plutonium
Chloride Systems in MCNP6.” (T01_Oral/Session07_Oct4_T01)[3] Tara Robertson et at., “Application of a Density Law via Python for Aqueous Plutonium Nitrate
Systems in MCNP6.” (T01_Oral/Session07_Oct4_T01)[4] Tomoaki Watanabe et at., “Comparison of Neutronic Characteristics of BWR Burnup Fuel between
JENDL-4.0 and JENDL-55.” (T02_Oral/Session02_Oct2_T02)[5] Tomohiro Endo et at., “Efficient Uncertainty Quantification Using Deterministic Sampling Methodwith Simplex Ensemble and Scaling Method.” (T03_Oral/Session09_Oct4_T03)[6] Shuhei Maruyama et at., “Nuclear Data Sensitivity Analysis of a Sodium Shielding Experiment
Based on Generalized Perturbation Theory for Data Assimilation.” (T03_Oral/Session09_Oct4_T03)[7] Kodai Fukuda et at., “Multiphysics Analysis of Reactivity Changes due to Solution Flow in the
Past Criticality Accident at Windscale Works In 1970.” (T08_Oral/Session02_Oct2_T08)[8] Shunya Teratani et at., “Problem-Based Learning Program of Reactor Physics Experiment to
Measure Subcriticality for an Unknown Systems.” (T09_Poster)[9] Adrien Gallozzi Ulmann et at., “Generalized CAAS Probe Positioning Methodology for a Varietyof Fissile Material Processes.” (T08_Oral/Session03_Oct2_T08)[10] Michael Bronko-Katcne et at., “Criticality Experiment Design for the Molten Chloride Reactor
Experiment Facility.” (S2_Oral/Session11_Oct5_S2)
The full papers are saved as PDFs under the subfolders, which are identified by the track numbers,session numbers, and date.

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JAEA-Conf 2024-001

Acknowledgements
The authors, who are staff of the criticality safety laboratory of JAEA and who were the members of
the local organizer, thank all participants arriving in Sendai in October 2023. We hope this report isutilized and referred in the criticality safety research in the world and look forward to seeing you again
in Manchester, UK, in 2027. We also thank Ms. Rima OUCHI and Mr. Takeo KIKUCHI of thecriticality safety laboratory. They supported us for a long-time during preparation work. By our request,
Ms. OUCHI personally contributed to the conference by making a nice logo, and Mr. KIKUCHI
contributed to the network and server management for the conference preparation.

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