Yoshitaka Fukano - My portal

Profile Information

Affiliation: Japan Atomic Energy Agency

Degree: 博士（工学）(Mar, 2010, 東京大学大学院)

J-GLOBAL ID: 202101000871032061
researchmap Member ID: R000017456

Research Areas

Energy / Nuclear engineering /

Education

Apr, 1991 - Mar, 1993

原子力工学科, 工学部, 東京大学
Apr, 1989 - Mar, 1991

理科一類, 東京大学
Apr, 1986 - Mar, 1989

下関西高校

Awards

Papers

Study on safety characteristics of a sodium-cooled fast reactor with negative void reactivity during initiating phase in severe accident

Ishida Shinya, Fukano Yoshitaka, Tobita Yoshiharu, Okano Yasushi

Proceedings of 2023 International Congress on Advanced in Nuclear Power Plants (ICAPP 2023) (Internet), 8, Apr, 2023 Peer-reviewed
Numerical study of initiating phase of core disruptive accident in small sodium-cooled fast reactors with negative void reactivity

Ishida Shinya, Fukano Yoshitaka, Tobita Yoshiharu, Okano Yasushi

Journal of Nuclear Science and Technology, 13, Jan, 2023 Peer-reviewed
Sodium-cooled Fast Reactors

Ohshima Hiroyuki, Morishita Masaki*, Aizawa Kosuke, Ando Masanori, Ashida Takashi, Chikazawa Yoshitaka, Doda Norihiro, Enuma Yasuhiro, Ezure Toshiki, Fukano Yoshitaka …

Sodium-cooled Fast Reactors; JSME Series in Thermal and Nuclear Power Generation, Vol.3, 631, Jul, 2022 Peer-reviewed
Study on initiating phase of core disruptive accident (Validation study of SAS4A code for the unprotected transient overpower accident)

Ishida Shinya, Fukano Yoshitaka

Nihon Kikai Gakkai Rombunshu (Internet), 88(911) 21-00304\_1-21-00304\_11, Jul, 2022 Peer-reviewed
Validation study of SAS4A code for the unprotected loss-of-flow accident in an SFR

Ishida Shinya, Kawada Kenichi, Fukano Yoshitaka

Mechanical Engineering Journal (Internet), 7(3) 19-00523\_1-19-00523\_17, Jun, 2020 Peer-reviewed
Validation study of initiating phase evaluation method for the core disruptive accident in an SFR

Ishida Shinya, Kawada Kenichi, Fukano Yoshitaka

Proceedings of 27th International Conference on Nuclear Engineering (ICONE-27) (Internet), 10, May, 2019 Peer-reviewed
Development and validation of SAS4A code and its application to analyses on severe flow blockage accidents in a sodium-cooled fast reactor

Fukano Yoshitaka

Journal of Nuclear Engineering and Radiation Science, 5(1) 011001\_1-011001\_13, Jan, 2019 Peer-reviewed
Development of LORL evaluation method and its application to a loop-type sodium-cooled fast reactor

Imaizumi Yuya, Yamada Fumiaki, Arikawa Mitsuhiro*, Yada Hiroki, Fukano Yoshitaka

Mechanical Engineering Journal (Internet), 5(4) 18-00083\_1-18-00083\_11, Aug, 2018 Peer-reviewed
Updating of local blockage frequency in the reactor core of SFR and PRA on consequent severe accident in Monju

Nishimura Masahiro, Fukano Yoshitaka, Kurisaka Kenichi, Naruto Kenichi*

Journal of Nuclear Science and Technology, 54(11) 1178-1189, Nov, 2017 Peer-reviewed
Development of the severe accident evaluation method on second coolant leakages from the PHTS in a loop-type sodium-cooled fast reactor

Yamada Fumiaki, Imaizumi Yuya, Nishimura Masahiro, Fukano Yoshitaka, Arikawa Mitsuhiro*

Proceedings of 25th International Conference on Nuclear Engineering (ICONE-25) (CD-ROM), 10, Jul, 2017 Peer-reviewed
Development and validation of evaluation method on hypothetical total instantaneous flow blockage in sodium-cooled fast reactors and its application to a middle size SFR

Fukano Yoshitaka

Proceedings of 25th International Conference on Nuclear Engineering (ICONE-25) (CD-ROM), 10, Jul, 2017 Peer-reviewed
Validation and applicability of reactor core modeling in a plant dynamics code during station blackout

Mori Takero, Ohira Hiroaki, Sotsu Masutake, Fukano Yoshitaka

Proceedings of 2017 International Congress on Advances in Nuclear Power Plants (ICAPP 2017) (CD-ROM), 9, Apr, 2017 Peer-reviewed
Analytical study on safety margins against significant core damage during loss-of-heat-removal-system events in a sodium-cooled fast reactor

Fukano Yoshitaka

Proceedings of 2017 International Congress on Advances in Nuclear Power Plants (ICAPP 2017) (CD-ROM), 9, Apr, 2017 Peer-reviewed
PRA on mixed foreign substances into core of Japanese prototype FBR

Nishimura Masahiro, Fukano Yoshitaka, Kurisaka Kenichi, Naruto Kenichi*

Proceedings of 13th Probabilistic Safety Assessment and Management Conference (PSAM-13) (USB Flash Drive), 12, Oct, 2016 Peer-reviewed
Analytical studies on fuel element failure propagation due to adventitious fuel pin failure in small to large size sodium-cooled fast reactors

Fukano Yoshitaka

Proceedings of 11th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Operation and Safety (NUTHOS-11) (USB Flash Drive), 12, Oct, 2016 Peer-reviewed
SAS4A analyses of CABRI in-pile experiments simulating unprotected-loss-of-flow accidents in SFRs

Imaizumi Yuya, Fukano Yoshitaka

Proceedings of 2016 International Congress on Advances in Nuclear Power Plants (ICAPP 2016) (CD-ROM), 357-363, Apr, 2016 Peer-reviewed
SAS4A analyses of SCARABEE in-pile experiments simulating hypothetical total instantaneous flow blockages in SFRs

Fukano Yoshitaka

Proceedings of 2016 International Congress on Advances in Nuclear Power Plants (ICAPP 2016) (CD-ROM), 347-356, Apr, 2016 Peer-reviewed
Updating of adventitious fuel pin failure frequency in sodium-cooled fast reactors and probabilistic risk assessment on consequent severe accident in Monju

Fukano Yoshitaka, Naruto Kenichi*, Kurisaka Kenichi, Nishimura Masahiro

Journal of Nuclear Science and Technology, 52(9) 1122-1132, Sep, 2015 Peer-reviewed
Safety margins after failure of fuel cladding during protected loss-of-heat-sink accidents in a sodium-cooled fast reactor

Fukano Yoshitaka, Nishimura Masahiro, Yamada Fumiaki

Proceedings of 16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-16) (USB Flash Drive), 5687-5698, Aug, 2015 Peer-reviewed
Validation of core cooling capability analysis in Monju during guillotine pipe break at primary heat transport system

Yamada Fumiaki, Arikawa Mitsuhiro*, Fukano Yoshitaka

Proceedings of 23rd International Conference on Nuclear Engineering (ICONE-23) (DVD-ROM), 7, May, 2015 Peer-reviewed

Misc.

Study on initiating phase of core disruptive accident; Identification of important phenomena in initiating phase of unprotected transient overpower accident

Ishida Shinya, Fukano Yoshitaka

Dai-25-Kai Doryoku, Enerugi Gijutsu Shimpojiumu Koen Rombunshu (Internet), 4, Jul, 2021
Probability of adventitious fuel pin failures in fast breeder reactors and event tree analysis on damage propagation up to severe accident in Monju

Fukano Yoshitaka, Naruto Kenichi*, Kurisaka Kenichi, Nishimura Masahiro

Proceedings of 12th Probabilistic Safety Assessment and Management Conference (PSAM-12) (USB Flash Drive), 12, Jun, 2014
Evaluation on coolability of the reactor core in Monju by natural circulation under earthquake and subsequent tsunami event

Yamada Fumiaki, Fukano Yoshitaka, Nishi Hiroshi, Konomura Mamoru

Proceedings of International Conference on Fast Reactors and Related Fuel Cycles; Safe Technologies and Sustainable Scenarios (FR-13) (USB Flash Drive), 10, Mar, 2013
CAFÉ experiments on the flow and freezing of metal fuel and cladding melts, 2; Results, analysis, and applications

Wright A. E.*, Bauer T. H.*, Kilsdonk D. J.*, Aeschlimann R. W.*, Fukano Yoshitaka, Kawada Kenichi, Sato Ikken

Proceedings of International Conference on Fast Reactors and Related Fuel Cycles (FR 2009) (CD-ROM), 9, Jan, 2012
CAFÉ experiments on the flow and freezing of metal fuel and cladding melts, 1; Test conditions and overview of the results

Fukano Yoshitaka, Kawada Kenichi, Sato Ikken, Wright A. E.*, Kilsdonk D. J.*, Aeschlimann R. W.*, Bauer T. H.*

Proceedings of International Conference on Fast Reactors and Related Fuel Cycles (FR 2009) (CD-ROM), 10, Jan, 2012
Analysis of ULOF accident in Monju reflecting the knowledge from CABRI in-pile experiments and others

Sato Ikken, Tobita Yoshiharu, Suzuki Toru, Kawada Kenichi, Fukano Yoshitaka, Fujita Satoshi, Kamiyama Kenji, Nonaka Nobuyuki, Ishikawa Makoto, Usami Shin

JAEA-Research 2007-055, 84, May, 2007
None

Nihon Genshiryoku Gakkai-Shi, 45(5) 30-31, Jan, 2003
The CEA-JNC Seminar on Simulation Code Development for Fast Reactor Cycle Technology

Iwata Koji

Saikuru Kiko Giho, (20) 95-98, Jan, 2003
None

Nihon Genshiryoku Gakkai-Shi, 45(5) 30-31, Jan, 2003
The Meeting for Reporting the Results of Safety Research in JFY2001 (in Power Reactor Field)

Fukano Yoshitaka

Saikuru Kiko Giho, (15) 135, Jan, 2002
None

Saikuru Kiko Giho, (17), Jan, 2002
Interpretation of the CABBI-RAFT LTX test up to pin failure based on detailed date evaluation and PAPAS-2S code analysis

JNC TN9400 2001-096, 45, Sep, 2001
Interpretation of the CABRI-RAFT RB1 and RB2 tests through detailed date evaluation and PAPAS-2S code analysis

JNC TN9400 2001-084, 59, Aug, 2001
Study on the neutron hodoscope system for the SERAPH in-pile experimental reactor

Konishi Kensuke

JNC TN9400 2001-035, 65, Feb, 2001
RB2 Pre-test Calculation using PAPAS-2S based on a Preliminary Post-test Calculation of the RB1 Test

PNC TN9410 98-058, 12, Jun, 1998
Fuel pin failure threshold under the slow TOP condition; Survey on the existing In-pile tests and investigation of the FCMI mitigation mechanism

PNC TN9410 98-057, 55, May, 1998

Presentations

Status of numerical tools development and experimental study supporting safety design and assessment of SFRs in Japan

Fukano Yoshitaka, Kubo Shigenobu

10th Joint IAEA-GIF Technical Meeting/Workshop on the Safety of Liquid Metal Cooled Fast Reactors
Development of detailed fuel pin model in SIMMER-V code, 1; Development of the prototype model and verification plan

Ishida Shinya, Tagami Hirotaka, Fukano Yoshitaka, Yamano Hidemasa, Kubo Shigenobu

日本原子力学会2021年秋の大会
Development of advanced reactor knowledge- and AI-aided design integration approach through the whole plant lifecycle, ARKADIA, 3; Development plan of safety evaluation tool, ARKADIA-Safety

Uchibori Akihiro, Takata Takashi, Fukano Yoshitaka, Yamano Hidemasa

日本原子力学会2021年春の年会
Study on validation of initiating phase analysis code for core disruptive accident in an SFR

Ishida Shinya, Kawada Kenichi, Fukano Yoshitaka

日本原子力学会2019年春の年会
Study on effectiveness evaluations of countermeasures against severe accidents in fast reactor, 9; Effectiveness evaluations of countermeasures against severe accidents for spent fuel

Mori Takero, Taninaka Hiroshi, Kurisaka Kenichi, Yamada Fumiaki, Nishimura Masahiro, Fukano Yoshitaka

日本原子力学会2018年春の年会
Study on effectiveness evaluations of countermeasures against severe accidents in fast reactor, 8; Effectiveness evaluations of countermeasures against severe accidents during reactor shutdown

Nishimura Masahiro, Yoshimura Kazuo, Taninaka Hiroshi, Yamada Fumiaki, Mori Takero, Nishino Hiroyuki, Fukano Yoshitaka

日本原子力学会2018年春の年会
Study on effectiveness evaluations of countermeasures against severe accidents in fast reactor, 6; Effectiveness evaluations of countermeasures against anticipated transient without scram

Imaizumi Yuya, Yamada Fumiaki, Nishimura Masahiro, Mori Takero, Fukano Yoshitaka

日本原子力学会2018年春の年会
Study on effectiveness evaluations of countermeasures against severe accidents in fast reactor, 7; Selecting the important accident sequences during reactor shutdown

Nishino Hiroyuki, Kurisaka Kenichi, Yoshimura Kazuo, Nishimura Masahiro, Fukano Yoshitaka

日本原子力学会2018年春の年会
Safety evaluations for MONJU during decommissioning phase, 2; Conservative thermal evaluations on fuel integrity

Mori Takero, Sotsu Masutake, Imaizumi Yuya, Yoshimura Kazuo, Fukano Yoshitaka

日本原子力学会2017年秋の大会
Safety evaluations for MONJU during decommissioning phase, 1; Approach to safety evaluations during decommissioning phase

Fukano Yoshitaka, Futagami Satoshi, Enuma Yasuhiro, Suzuki Takayuki, Nakai Ryodai, Ikeda Makinori

日本原子力学会2017年秋の大会
Study on effectiveness evaluations of countermeasures against severe accidents in fast reactor, 1; Prevention criteria proposal of significant core damage and their approach

Nishimura Masahiro, Fukano Yoshitaka, Onoda Yuichi, Yamada Fumiaki

日本原子力学会2017年春の年会
Study on effectiveness evaluations of countermeasures against severe accidents in fast reactor, 5; Validation of reactor analytical model for PLOHS events

Mori Takero, Ohira Hiroaki, Sotsu Masutake, Fukano Yoshitaka

日本原子力学会2017年春の年会
Study on effectiveness evaluations of countermeasures against severe accidents in fast reactor, 2; Bases of criteria on fuel

Fukano Yoshitaka, Nishimura Masahiro, Onoda Yuichi, Yamada Fumiaki

日本原子力学会2017年春の年会
Validation of an analysis code on initiating phase of core disruptive accident in sodium-cooled fast reactors by CABRI in-pile experiments

Imaizumi Yuya, Fukano Yoshitaka

原子力関係科学技術の基礎的研究の動向調査委員会
Evaluation on hypothetical total instantaneous flow blockage at the inlet of fuel subassembly in a sodium-cooled fast reactor

Fukano Yoshitaka

日本原子力学会2016年秋の大会
Analyses of in-pile experiments by an analysis code on initiating phase of core disruptive accident in sodium cooled fast reactors, 4 Analysis of EFM1 test

Imaizumi Yuya, Fukano Yoshitaka

日本原子力学会2016年春の年会
Analyses of in-pile experiments by an analysis code on initiating phase of core disruptive accident in sodium cooled fast reactors, 3 Analysis of LT4 test

Yoshioka Naonori*, Fukano Yoshitaka

日本原子力学会2016年春の年会
Analyses of in-pile experiments by an analysis code on initiating phase of core disruptive accident in sodium cooled fast reactors, 2; Analysis of LTX test

Akahori Hisashi*, Fukano Yoshitaka

日本原子力学会2016年春の年会
Analyses of in-pile experiments by an analysis code on initiating phase of core disruptive accident in sodium cooled fast reactors,1; Summary of SAS4A code and CABRI in-pile experiments

Fukano Yoshitaka, Imaizumi Yuya, Yoshioka Naonori*, Akahori Hisashi*

日本原子力学会2016年春の年会
Safety margins against significant core damage during protected loss-of-heat-sink accidents in a sodium-cooled fast reactor

Fukano Yoshitaka

日本原子力学会2015年秋の大会