Advanced search
Publication Cover
Nuclear Technology Volume 206, 2020 - Issue 9: Selected papers from the 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-18)
Submit an article Journal homepage
589
Views
39
CrossRef citations to date
0
Altmetric
Technical Papers

Main Findings, Remaining Uncertainties and Lessons Learned from the OECD/NEA BSAF Project

M. Pellegrinia The Institute of Applied Energy, JapanCorrespondence[email protected]
,
L. Herranzb Centre for Energy, Environment, and Technology, Spain
,
M. Sonnenkalbc Gesellschaft für Anlagen- und Reaktorsicherheit (GRS), Germany
,
T. Lindd Paul Scherrer Institute, Division of Nuclear Energy and Safety, Villigen, Switzerland, 5232
,
Y. Maruyamae Japan Atomic Energy Agency, Japan
,
R. Gaunttf Sandia National Laboratories, United States
,
N. Bixlerf Sandia National Laboratories, United States
,
A. Morrealeg Canadian Nuclear Laboratories, Canada
,
K. Dolganovh Nuclear Safety Institute (IBRAE), Russia
,
T. Sevoni VTT Technical Research Centre, Finland
,
D. Jacquemainj Institute for Radiological Protection and Nuclear Safety, France
,
C. Journeauk CEA, DEN, Cadarache, SMTA, LEAG, F-13108Saint-Paul-lez-Durance, FranceORCID Iconhttps://orcid.org/0000-0001-5880-355X
ORCID Icon,
J. H. Songl Korean Atomic Energy Research Institute, Korea
,
Y. Nishim Central Research Institute of Electrical Power Industry, Japan
&
S. Mizokamin Tokyo Electric Power Company, Inc., Japan
 show all
Pages 1449-1463 | Received 09 Dec 2019, Accepted 29 Jan 2020, Published online: 14 Apr 2020

Citations (39)

Keep up to date with the latest research on this topic with citation updates for this article.

Subscribe to citation updates

Read on this site (8)

Ryo Yokoyama, Masahiro Kondo, Shunichi Suzuki, Christophe Journeau, Marco Pellegrini & Koji Okamoto. (2024) Evaluation of Molten Corium Spreading and Sedimentation Behaviors Within Primary Containment Vessel in Unit 3 of Fukushima Daiichi Nuclear Power Plant Toward the Best Prediction of Fuel Debris Distribution. Nuclear Technology 210:5, pages 884-905.
Read now
L. E. Herranz, F. Sánchez & S. Gupta. (2023) Validation Matrix for Pool Scrubbing Models. Nuclear Technology 209:10, pages 1523-1536.
Read now
Kotaro Nanjo, Hiroyuki Shiotsu, Yu Maruyama, Tomoyuki Sugiyama & Koji Okamoto. (2023) Estimation for mass transfer coefficient under two-phase flow conditions using two gas components. Journal of Nuclear Science and Technology 60:7, pages 816-823.
Read now
Hiroshi Madokoro, Takuya Yamashita, Xiaoyang Gaus-Liu, Thomas Cron, Beatrix Fluhrer, Ikken Sato & Shinya Mizokami. (2023) The Experimental and Simulation Results of LIVE-J2 Test—Investigation on Heat Transfer in a Solid–Liquid Mixture Pool. Nuclear Technology 209:2, pages 144-168.
Read now
Kotaro Nanjo, Jun Ishikawa, Tomoyuki Sugiyama, Marco Pellegrini & Koji Okamoto. (2022) Revolatilization of iodine by bubbly flow in the suppression pool during an accident. Journal of Nuclear Science and Technology 59:11, pages 1407-1416.
Read now
Yuta Kumagai, Ryoji Kusaka, Masami Nakada, Masayuki Watanabe, Daisuke Akiyama, Akira Kirishima, Nobuaki Sato & Takayuki Sasaki. (2022) Uranium dissolution and uranyl peroxide formation by immersion of simulated fuel debris in aqueous H2O2 solution. Journal of Nuclear Science and Technology 59:8, pages 961-971.
Read now
Ayumi Itoh, Nathan C. Andrews, David L. Luxat, Randall O. Gauntt, Masaki Kurata & Yoshinao Kobayashi. (2021) Degradation mechanism of stainless steel by U-Zr-O molten mixture during core degradation of BWR severe accident. Journal of Nuclear Science and Technology 58:6, pages 676-689.
Read now
Ikken Sato, Yuta Arai & Shinji Yoshikawa. (2021) Evaluation of core material energy change during the in-vessel phase of Fukushima Daiichi Unit 3 based on observed pressure data utilizing GOTHIC code analysis. Journal of Nuclear Science and Technology 58:4, pages 434-460.
Read now

Articles from other publishers (31)

Ikken Sato, Shinji Yoshikawa, Takuya Yamashita, Kenta Shimomura, Michal Cibula & Shinya Mizokami. (2024) MAAP code analysis for the in-vessel phase of Fukushima-Daiichi Nuclear Power Station Unit 1 and comparison of the results among Units 1 to 3. Nuclear Engineering and Design 422, pages 113088.
Crossref
N. Seiler, A. Bachrata, B. Bigot, V. Bouyer, C. Brayer, F. Charollais, R. Chauvin, R. Clavier, A. Denoix, J. Delacroix, E. Dufour, J. Francescatto, P. Gubernatis, M. Johnson, C. Journeau, A. Lecoanet, R. Le Tellier, P. Piluso, K. Pons, L. Saas & L. Trotignon. (2024) Achievements of recent research on severe accidents at CEA/IRESNE in support of future nuclear fission technology. Nuclear Engineering and Design 421, pages 113055.
Crossref
Sidharth Paranjape, Ralf Kapulla, Pavel Kudinov, Myeong-Seon Chae & Domenico Paladino. (2024) Experimental results of thermocline evolution in a water pool under combined effect of steam venting and water injection. Nuclear Engineering and Design 419, pages 112914.
Crossref
JinHo Song & SungJoong Kim. (2024) A machine learning informed prediction of severe accident progressions in nuclear power plants. Nuclear Engineering and Technology.
Crossref
JinHo Song & SungJoong Kim. (2024) A machine learning diagnosis of the severe accident progression. Nuclear Engineering and Design 416, pages 112781.
Crossref
Kirill S. Dolganov. (2024) Integral simulation of the first 3 weeks of severe accident at Fukushima Daiichi Unit 1 with SOCRAT code. Part I – Qualification of model and simulation of the initial phase. Nuclear Engineering and Design 416, pages 112771.
Crossref
Anton Pshenichnikov & Yuji Nagae. (2023) The results of the CLADS-MADE-03 BWR bundle degradation test in steam under 1F Unit 1 postulated conditions. Nuclear Engineering and Design 415, pages 112729.
Crossref
Luis E. Herranz, Ahmed Bentaib, Fabrizio Gabrielli, Sanjeev Gupta, Ivo Kljenak, Sandro Paci & Pascal Piluso. (2023) Overview of key thermal–hydraulic phenomena in severe accident unfolding: Current knowledge and further needs. Nuclear Engineering and Design 407, pages 112256.
Crossref
Hugo Laffolley, Christophe Journeau, Sarah Thilliez & Bernd Grambow. (2023) Thermodynamics of aerosols during a molten core-concrete interaction at Fukushima Daiichi Unit 2 estimated conditions. Annals of Nuclear Energy 186, pages 109770.
Crossref
Ikken Sato, Shinji Yoshikawa, Takuya Yamashita, Michal Cibula & Shinya Mizokami. (2023) MAAP code analysis focusing on the fuel debris condition in the lower head of the pressure vessel in Fukushima-Daiichi Nuclear Power Station Unit 2. Nuclear Engineering and Design 404, pages 112205.
Crossref
JinHo Song, DongGun Son, JaeHyun Ham, JunHo Bae, SungWon Bae, Kwangsoon Ha, ByungJo Kim, Sun Hong Yoon, BubDong Chung, SoonHo Park, ChangHwan Park, JaeHwan Park & YuJung Choi. (2023) A comparative simulation of severe accident progressions by CINEMA and MAAP5. Nuclear Engineering and Design 404, pages 112181.
Crossref
Luis E. Herranz & Francisco Sánchez. (2023) New pool scrubbing correlations based on reliable data. Annals of Nuclear Energy 183, pages 109639.
Crossref
Tsuyoshi MATSUOKA. (2023) Verification of a new approach for clarification of Fukushima meltdown accident process東電福島炉心溶融事故進展解明（一考察）の検証. Transactions of the Atomic Energy Society of Japan 22:3, pages 108-111.
Crossref
. (2023) Survey on technical issues of fission products behavior for improvement of decommissioning work efficiency and source-term predicting accuracy福島第一原子力発電所廃炉作業効率化とソースターム予測精度向上への貢献に向けたFP挙動に関する技術調査. Journal of the Atomic Energy Society of Japan 65:11, pages 674-679.
Crossref
Heriberto Sánchez-Mora, Javier Ortiz-Villafuerte, Armando M. Gómez-Torres, Cesar Queral & Sergio Quezada-García. (2023) Mathematical model of the QUENCH-06 experiment with sensitivity and uncertainty analysis in hydrogen generation. International Journal of Heat and Mass Transfer 200, pages 123553.
Crossref
Takumi Sato, Yuji Nagae, Masaki Kurata, Andrea Quaini & Christine Guéneau. (2022) Thermodynamic analysis for solidification path of simulated ex-vessel corium. Calphad 79, pages 102481.
Crossref
Avadhesh Kumar Sharma, Marco Pellegrini, Koji Okamoto, Masahiro Furuya & Shinya Mizokami. (2022) Validation and application of numerical modeling for in-vessel melt retention in corium pools. International Journal of Heat and Mass Transfer 196, pages 123313.
Crossref
JinHo Song & KwangSoon Ha. (2022) A simulation and machine learning informed diagnosis of the severe accidents. Nuclear Engineering and Design 395, pages 111881.
Crossref
Jules Delacroix, Christophe Journeau & Pascal Piluso. (2022) High-Temperature Characterization of Melted Nuclear Core Materials: Investigating Corium Properties Through the Case Studies of In-Vessel and Ex-Vessel Retention. Frontiers in Energy Research 10.
Crossref
Takuya Yamashita, Hiroshi Madokoro & Ikken Sato. (2022) Post-Test Analyses of the CMMR-4 Test. Journal of Nuclear Engineering and Radiation Science 8:2.
Crossref
Jarmo Kalilainen & Terttaliisa Lind. (2022) Uncertainty quantification study on gas phase iodine release from Fukushima Daiichi accident in unit 3. Annals of Nuclear Energy 166, pages 108740.
Crossref
Hiroshi Madokoro & Yuji Nagae. (2022) Recent technology trends in severe accident simulations and experiments (2)シビアアクシデント解析・実験の最新技術動向. Journal of the Atomic Energy Society of Japan 64:9, pages 500-503.
Crossref
Ikken Sato. (2021) Analysis of Fukushima-Daiichi Nuclear Power Plant Unit 3 pressure data and obtained insights on accident progression behavior. Nuclear Engineering and Design 383, pages 111426.
Crossref
Jinho Song. (2021) Perspectives on a Severe Accident Consequences—10 Years after the Fukushima Accident. Journal of Nuclear Engineering 2:4, pages 398-411.
Crossref
Hiroshi Madokoro & Ikken Sato. (2021) Estimation of the core degradation and relocation at the Fukushima Daiichi Nuclear Power Station Unit 2 based on RELAP/SCDAPSIM analysis. Nuclear Engineering and Design 376, pages 111123.
Crossref
Sergii Nichenko, Jarmo Kalilainen, Leticia Fernandez Moguel & Terttaliisa Lind. (2021) Modelling of fission products release in VERDON-1 experiment with cGEMS: Coupling of severe accident code MELCOR with GEMS thermodynamic modelling package. Annals of Nuclear Energy 152, pages 107972.
Crossref
JinHo Song, ByungHee Lee, SungIl Kim & KwangSoon Ha. (2021) An analysis on the steam generator tube rupture events with core damage. Annals of Nuclear Energy 150, pages 107877.
Crossref
Xin Li, Ikken Sato, Akifumi Yamaji, Mariko Regalado & Jun Wang. (2021) Sensitivity analysis of core slumping and debris quenching behavior of Fukushima Daiichi Unit-3 accident. Annals of Nuclear Energy 150, pages 107819.
Crossref
Marco Pellegrini. 2021. Nuclear Power Plant Design and Analysis Codes. Nuclear Power Plant Design and Analysis Codes 397 416 .
Akira Nakayoshi, Joy L. Rempe, Marc Barrachin, David Bottomley, Didier Jacquemain, Christophe Journeau, Viktor Krasnov, Terttaliisa Lind, Richard Lee, Donald Marksberry, Shinya Mizokami, Andrew Morreale, Damian Peko, Marco Pellegrini & Jin Ho Song. (2020) Review of Fukushima Daiichi Nuclear Power Station debris endstate location in OECD/NEA preparatory study on analysis of fuel debris (PreADES) project. Nuclear Engineering and Design 369, pages 110857.
Crossref
M. Pellegrini & M. Naitoh. (2020) Three weeks analysis of the Fukushima Daiichi Unit 3 NPP by the SAMPSON code: Contribution to the BSAF-2 project. Nuclear Engineering and Design 366, pages 110747.
Crossref

Reprints and Corporate Permissions

Please note: Selecting permissions does not provide access to the full text of the article, please see our help page How do I view content?

To request a reprint or corporate permissions for this article, please click on the relevant link below:

Order Reprints Request Corporate Permissions

Academic Permissions

Please note: Selecting permissions does not provide access to the full text of the article, please see our help page How do I view content?

Obtain permissions instantly via Rightslink by clicking on the button below:

Request Academic Permissions

If you are unable to obtain permissions via Rightslink, please complete and submit this Permissions form. For more information, please visit our Permissions help page.

Related research

People also read lists articles that other readers of this article have read.

Recommended articles lists articles that we recommend and is powered by our AI driven recommendation engine.

Cited by lists all citing articles based on Crossref citations.
Articles with the Crossref icon will open in a new tab.