Overview and Outcomes of the OECD/NEA Benchmark Study of the Accident at the Fukushima Daiichi NPS (BSAF) Phase 2—Results of Severe Accident Analyses for Unit 3

Terttaliisa Lind, Marco Pellegrini, Luis Enrique Herranz, Martin Sonnenkalb, Y. Nishi, H. Tamaki, F. Cousin, Leticia Fernandez-Moguel, Nathan Andrews, Tuomo Sevon

Research output: Chapter in Book/Report/Conference proceedingConference article in proceedingsScientificpeer-review

Abstract

The Phase 2 of the OECD/NEA Project “Benchmark Study of the Accident at the Fukushima Daiichi Nuclear Power Plant (BSAF)” was established in mid-2015. The objectives were similar to Phase 1 of the project but with an extended analysis period of 3 weeks from the occurrence of the earthquake, the main focus on fission product behavior and releases to the environment and the comparison to various data including radiological data and results of backwards calculations of the source term.

Eight organizations of five countries (CRIEPI, IAE, JAEA and NRA, Japan; IRSN France; PSI, Switzerland; SNL, USA; VTT, Finland) submitted results of their calculated severe accident scenarios for Unit 3 at the Fukushima Daiichi site using different severe accident codes (ASTEC, MAAP, MELCOR, SAMPSON, THALES).

The present paper for Unit 3 describes the findings of the comparison of the participants’ results against each other and against plant data, the evaluation of the accident progression and the final status inside the reactors. Special focus is on the status of the reactor pressure vessel, melt release and fission product release and transport. Unit 3 specific aspects will be highlighted and points of consensus as well as remaining uncertainties and data needs will be summarized. The results for Units 1 and 2, and an overall summary are presented in separate papers.
Original languageEnglish
Title of host publicationProceedings of the 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH-18
PublisherAmerican Nuclear Society ANS
ISBN (Electronic)978-0-89448-767-5
Publication statusPublished - 2019
MoE publication typeA4 Article in a conference publication
Event18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics - Portland, United States
Duration: 18 Aug 201923 Aug 2019

Conference

Conference18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics
Abbreviated titleNURETH-18
CountryUnited States
CityPortland
Period18/08/1923/08/19

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Accidents
Fission products
Pressure vessels
Nuclear power plants
Earthquakes

Cite this

Lind, T., Pellegrini, M., Herranz, L. E., Sonnenkalb, M., Nishi, Y., Tamaki, H., ... Sevon, T. (2019). Overview and Outcomes of the OECD/NEA Benchmark Study of the Accident at the Fukushima Daiichi NPS (BSAF) Phase 2—Results of Severe Accident Analyses for Unit 3. In Proceedings of the 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH-18 American Nuclear Society ANS.
Lind, Terttaliisa ; Pellegrini, Marco ; Herranz, Luis Enrique ; Sonnenkalb, Martin ; Nishi, Y. ; Tamaki, H. ; Cousin, F. ; Fernandez-Moguel, Leticia ; Andrews, Nathan ; Sevon, Tuomo. / Overview and Outcomes of the OECD/NEA Benchmark Study of the Accident at the Fukushima Daiichi NPS (BSAF) Phase 2—Results of Severe Accident Analyses for Unit 3. Proceedings of the 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH-18. American Nuclear Society ANS, 2019.
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title = "Overview and Outcomes of the OECD/NEA Benchmark Study of the Accident at the Fukushima Daiichi NPS (BSAF) Phase 2—Results of Severe Accident Analyses for Unit 3",
abstract = "The Phase 2 of the OECD/NEA Project “Benchmark Study of the Accident at the Fukushima Daiichi Nuclear Power Plant (BSAF)” was established in mid-2015. The objectives were similar to Phase 1 of the project but with an extended analysis period of 3 weeks from the occurrence of the earthquake, the main focus on fission product behavior and releases to the environment and the comparison to various data including radiological data and results of backwards calculations of the source term.Eight organizations of five countries (CRIEPI, IAE, JAEA and NRA, Japan; IRSN France; PSI, Switzerland; SNL, USA; VTT, Finland) submitted results of their calculated severe accident scenarios for Unit 3 at the Fukushima Daiichi site using different severe accident codes (ASTEC, MAAP, MELCOR, SAMPSON, THALES).The present paper for Unit 3 describes the findings of the comparison of the participants’ results against each other and against plant data, the evaluation of the accident progression and the final status inside the reactors. Special focus is on the status of the reactor pressure vessel, melt release and fission product release and transport. Unit 3 specific aspects will be highlighted and points of consensus as well as remaining uncertainties and data needs will be summarized. The results for Units 1 and 2, and an overall summary are presented in separate papers.",
author = "Terttaliisa Lind and Marco Pellegrini and Herranz, {Luis Enrique} and Martin Sonnenkalb and Y. Nishi and H. Tamaki and F. Cousin and Leticia Fernandez-Moguel and Nathan Andrews and Tuomo Sevon",
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Lind, T, Pellegrini, M, Herranz, LE, Sonnenkalb, M, Nishi, Y, Tamaki, H, Cousin, F, Fernandez-Moguel, L, Andrews, N & Sevon, T 2019, Overview and Outcomes of the OECD/NEA Benchmark Study of the Accident at the Fukushima Daiichi NPS (BSAF) Phase 2—Results of Severe Accident Analyses for Unit 3. in Proceedings of the 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH-18. American Nuclear Society ANS, 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Portland, United States, 18/08/19.

Overview and Outcomes of the OECD/NEA Benchmark Study of the Accident at the Fukushima Daiichi NPS (BSAF) Phase 2—Results of Severe Accident Analyses for Unit 3. / Lind, Terttaliisa; Pellegrini, Marco; Herranz, Luis Enrique; Sonnenkalb, Martin; Nishi, Y.; Tamaki, H.; Cousin, F.; Fernandez-Moguel, Leticia; Andrews, Nathan; Sevon, Tuomo.

Proceedings of the 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH-18. American Nuclear Society ANS, 2019.

Research output: Chapter in Book/Report/Conference proceedingConference article in proceedingsScientificpeer-review

TY - GEN

T1 - Overview and Outcomes of the OECD/NEA Benchmark Study of the Accident at the Fukushima Daiichi NPS (BSAF) Phase 2—Results of Severe Accident Analyses for Unit 3

AU - Lind, Terttaliisa

AU - Pellegrini, Marco

AU - Herranz, Luis Enrique

AU - Sonnenkalb, Martin

AU - Nishi, Y.

AU - Tamaki, H.

AU - Cousin, F.

AU - Fernandez-Moguel, Leticia

AU - Andrews, Nathan

AU - Sevon, Tuomo

PY - 2019

Y1 - 2019

N2 - The Phase 2 of the OECD/NEA Project “Benchmark Study of the Accident at the Fukushima Daiichi Nuclear Power Plant (BSAF)” was established in mid-2015. The objectives were similar to Phase 1 of the project but with an extended analysis period of 3 weeks from the occurrence of the earthquake, the main focus on fission product behavior and releases to the environment and the comparison to various data including radiological data and results of backwards calculations of the source term.Eight organizations of five countries (CRIEPI, IAE, JAEA and NRA, Japan; IRSN France; PSI, Switzerland; SNL, USA; VTT, Finland) submitted results of their calculated severe accident scenarios for Unit 3 at the Fukushima Daiichi site using different severe accident codes (ASTEC, MAAP, MELCOR, SAMPSON, THALES).The present paper for Unit 3 describes the findings of the comparison of the participants’ results against each other and against plant data, the evaluation of the accident progression and the final status inside the reactors. Special focus is on the status of the reactor pressure vessel, melt release and fission product release and transport. Unit 3 specific aspects will be highlighted and points of consensus as well as remaining uncertainties and data needs will be summarized. The results for Units 1 and 2, and an overall summary are presented in separate papers.

AB - The Phase 2 of the OECD/NEA Project “Benchmark Study of the Accident at the Fukushima Daiichi Nuclear Power Plant (BSAF)” was established in mid-2015. The objectives were similar to Phase 1 of the project but with an extended analysis period of 3 weeks from the occurrence of the earthquake, the main focus on fission product behavior and releases to the environment and the comparison to various data including radiological data and results of backwards calculations of the source term.Eight organizations of five countries (CRIEPI, IAE, JAEA and NRA, Japan; IRSN France; PSI, Switzerland; SNL, USA; VTT, Finland) submitted results of their calculated severe accident scenarios for Unit 3 at the Fukushima Daiichi site using different severe accident codes (ASTEC, MAAP, MELCOR, SAMPSON, THALES).The present paper for Unit 3 describes the findings of the comparison of the participants’ results against each other and against plant data, the evaluation of the accident progression and the final status inside the reactors. Special focus is on the status of the reactor pressure vessel, melt release and fission product release and transport. Unit 3 specific aspects will be highlighted and points of consensus as well as remaining uncertainties and data needs will be summarized. The results for Units 1 and 2, and an overall summary are presented in separate papers.

M3 - Conference article in proceedings

BT - Proceedings of the 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH-18

PB - American Nuclear Society ANS

ER -

Lind T, Pellegrini M, Herranz LE, Sonnenkalb M, Nishi Y, Tamaki H et al. Overview and Outcomes of the OECD/NEA Benchmark Study of the Accident at the Fukushima Daiichi NPS (BSAF) Phase 2—Results of Severe Accident Analyses for Unit 3. In Proceedings of the 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH-18. American Nuclear Society ANS. 2019