Ryodai Nakai - My portal

Profile Information

Affiliation: Japan Atomic Energy Agency

J-GLOBAL ID: 202101002357854993
researchmap Member ID: R000017438

Research Areas

Energy / Nuclear engineering /

Papers

Study on In-Vessel Retention (IVR) of unprotected accident for fast reactor, 1; Overview of IVR evaluation in Anticipated Transient without Scram (ATWS)

Suzuki Toru, Sogabe Joji, Tobita Yoshiharu, Sakai Takaaki*, Nakai Ryodai

Nippon Kikai Gakkai Rombunshu (Internet), 83(848) 16-00395\_1-16-00395\_9, Apr, 2017 Peer-reviewed
Evaluation of recriticality behavior in the material-relocation phase for Japan sodium-cooled fast reactor

Suzuki Toru, Tobita Yoshiharu, Nakai Ryodai

Journal of Nuclear Science and Technology, 52(11) 1448-1459, Nov, 2015 Peer-reviewed
A Scenario of core disruptive accident for Japan sodium-cooled fast reactor to achieve in-vessel retention

Suzuki Toru, Kamiyama Kenji, Yamano Hidemasa, Kubo Shigenobu, Tobita Yoshiharu, Nakai Ryodai, Koyama Kazuya*

Journal of Nuclear Science and Technology, 51(4) 493-513, Apr, 2014 Peer-reviewed
Development of safety design criteria for the Generation-IV Sodium-cooled Fast Reactor

Nakai Ryodai, Okano Yasushi, Kubo Shigenobu

Proceedings of 8th Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS-8) (USB Flash Drive), 5, Dec, 2012 Peer-reviewed
Improved safety approach for general safety designs of the next generation sodium-cooled fast reactor systems

Okano Yasushi, Yamano Hidemasa, Fujita Satoshi, Kubo Shigenobu, Sakai Takaaki, Nakai Ryodai

Proceedings of 8th Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS-8) (USB Flash Drive), 9, Dec, 2012 Peer-reviewed
Evaluation of core disruptive accident for sodium-cooled fast reactors to achieve in-vessel retention

Suzuki Toru, Kamiyama Kenji, Yamano Hidemasa, Kubo Shigenobu, Tobita Yoshiharu, Nakai Ryodai, Koyama Kazuya*

Proceedings of 8th Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS-8) (USB Flash Drive), 10, Dec, 2012 Peer-reviewed
Development of Level 2 PSA methodology for sodium-cooled fast reactors; Overview of evaluation technology development

Suzuki Toru, Nakai Ryodai, Kamiyama Kenji, Seino Hiroshi, Koyama Kazuya*, Morita Koji*

NEA/CSNI/R(2012)2, 381-391, Jul, 2012 Peer-reviewed
Design and assessment approach on advanced SFR safety with emphasis on the core disruptive accident issue

Nakai Ryodai

Proceedings of International Conference on Fast Reactors and Related Fuel Cycles (FR 2009), 207-220, Jan, 2012 Peer-reviewed
Safety principles and safety approaches for next generation sodium-cooled fast reactor

Okano Yasushi, Sakai Takaaki, Nakai Ryodai

Proceedings of 2011 International Congress on Advances in Nuclear Power Plants (ICAPP '11) (CD-ROM), 719-727, May, 2011 Peer-reviewed
Safety strategy of JSFR eliminating severe recriticality events and establishing in-vessel retention in the core disruptive accident

Sato Ikken, Tobita Yoshiharu, Konishi Kensuke, Kamiyama Kenji, Toyooka Junichi, Nakai Ryodai, Kubo Shigenobu*, Kotake Shoji*, Koyama Kazuya*, Vassiliev Y. S.* …

Journal of Nuclear Science and Technology, 48(4) 556-566, Mar, 2011 Peer-reviewed
Development of system based code, 1; Reliability target derivation of structures and components

Kurisaka Kenichi, Nakai Ryodai, Asayama Tai, Takaya Shigeru

Journal of Power and Energy Systems (Internet), 5(1) 19-32, Jan, 2011 Peer-reviewed
Development of level 2 PSA methodology for sodium-cooled fast reactors, 1; Overview of evaluation technology development

Nakai Ryodai, Suzuki Toru, Kamiyama Kenji, Seino Hiroshi, Koyama Kazuya*, Morita Koji*

Proceedings of 8th International Topical Meeting on Nuclear Thermal-Hydraulics, Operation and Safety (NUTHOS-8) (CD-ROM), 12, Oct, 2010 Peer-reviewed
Development of system based code, 1; Reliability target derivation of structures and components

Kurisaka Kenichi, Nakai Ryodai, Asayama Tai, Takaya Shigeru

Proceedings of 18th International Conference on Nuclear Engineering (ICONE-18) (CD-ROM), 10, May, 2010 Peer-reviewed
Current status and future direction of INPRO (International Project on Innovative Nuclear Reactors and Fuel Cycles)

Omoto Akira*, Moriwaki Masanao*, Sugimoto Jun, Nakai Ryodai

Nihon Genshiryoku Gakkai-Shi, 49(2) 89-111, Feb, 2007 Peer-reviewed
Current status and future direction of INPRO (International Project on Innovative Nuclear Reactors and Fuel Cycles)

Omoto Akira*, Moriwaki Masanao*, Sugimoto Jun, Nakai Ryodai

Nihon Genshiryoku Gakkai-Shi, 49(2) 89-111, Feb, 2007 Peer-reviewed

Misc.

The Safety design guideline development for Generation-IV SFR systems

Nakai Ryodai

Proceedings of International Conference on Fast Reactors and Related Fuel Cycles; Next Generation Nuclear Systems for Sustainable Development (FR-17) (USB Flash Drive), 10, Jun, 2017
Study on In-Vessel Retention (IVR) of unprotected accident for fast reactor, 1; Overview of IVR evaluation in Anticipated Transient without Scram (ATWS)

Suzuki Toru, Sogabe Joji, Tobita Yoshiharu, Sakai Takaaki*, Nakai Ryodai

Dai-21-Kai Doryoku, Enerugi Gijutsu Shimpojiumu Koen Rombunshu (USB Flash Drive), 4, Jun, 2016
Safety design criteria for generation IV sodium-cooled fast reactor system

Nakai Ryodai, Sofu T.*

GIF Symposium Proceedings/2012 Annual Report of NEA, No.7141, 35-43, Jan, 2013
Safety design approach of Japan sodium-cooled fast reactor

Nakai Ryodai, Sakai Takaaki, Okano Yasushi

Proceedings of International Conference on Toward and Over the Fukushima Daiichi Accident (GLOBAL 2011) (CD-ROM), 7, Dec, 2011
Recent status and trend of domestic and international fast reactor development

Nakai Ryodai

Nihon Genshiryoku Gakkai-Shi ATOMO$\Sigma$, 50(5) 318-323, May, 2008
History and current status regarding the research and development of minor actinide recycling

Nagaoki Yoshihiro, Nakai Ryodai

Genshiryoku eye, 53(1) 58-61, Jan, 2007
Requirements and their realization measures for commercialized FBR cycle systems

Nakai Ryodai

Dai-38-Kai Genshiryoku Anzen Kenkyu Sogo Happyokai Koen Rombunshu, 33-42, Jan, 2006
Reduction of Environmental Impact by FR Cycle Deployment

Kato Atsushi, Nakai Ryodai

JNC-TN1400 2004-016, 37, Mar, 2005
None

Ono Katsumi, masato ando, Kotake Shoji, Nagaoki Yoshihiro, Namba Takashi, Kato Atsushi, Nakai Ryodai, Negishi Hitoshi

Nihon Genshiryoku Gakkai-Shi, 46(10) 685, Oct, 2004
None

Ono Katsumi, masato ando, Kotake Shoji, Nagaoki Yoshihiro, Namba Takashi, Kato Atsushi, Nakai Ryodai, Negishi Hitoshi

Nippon Genshiryoku Gakkai-Shi, 46(10) 685, Oct, 2004
Sodium Combustion Analysis (II) for the Secondary Heat Transport System of Prototype Fast Breeder Reactor MONJU

Okabe Ayao, Ohno Shuji, Nakai Ryodai, Ebashi Masaaki

JNC TN2400 2003-002, 49, Feb, 2004
The Development and Application of Overheating Failure Model of FBR Steam Generator Tubes (IV)

Miyake Osamu, Hamada Hirotsugu, Tanabe Hiromi, Wada Yusaku, Miyakawa Akira, Okabe Ayao, Nakai Ryodai, Hiroi Hiroshi

JNC TN2400 2003-003, 225, Feb, 2004
None

Negishi Hitoshi, Sagayama Yutaka, Sato Kazujiro, Nakai Ryodai, Ieda Yoshiaki

Saikuru Kiko Giho, (20), Jan, 2003
The Development and Application of overheating failure model of FBR steam generator Tubes (III)

Miyake Osamu, Hamada Hirotsugu, Tanabe Hiromi, Miyakawa Akira, Okabe Ayao

JNC TN9400 2001-130, 235, Mar, 2002
Sodium combustion analysis for the secondary heat transport system of prototype fast breeder reactor MONJU

Ohno Shuji

JNC TN2400 2000-006, 56, Dec, 2000
Lessons learned from MONJU sodium leak accident

Proceedings of International Conference on Probabilistic Safety Assessment and Management (PSAM5), Jan, 2000
Study of rationalized safety design based on the seismic PSA for an LMFBR

Nakai Ryodai, Yamaguchi Akira

Reliability Engineering \& System Safety, 62(3) 221-234, Jan, 1998
Study on the safety of an large scale fast breeder reactor (II)

Miyake Osamu

PNC TN9410 93-068, 81, Mar, 1993
Study on the safety of an large scale fast breeder reactor

Miyake Osamu

PNC TN9410 92-068, 73, Mar, 1992
Reliability assessment on systems and components of FBR

Nakai Ryodai, Hioki Kazumasa, Sakuma Takashi, Kani Yoshio

PNC TN9410 91-335, 62, Oct, 1991

Presentations

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
International review on safety requirements for Monju

Nakai Ryodai, Saito Shinzo, Yamaguchi Akira*, Okamoto Koji*, Kani Yoshio*

日本原子力学会2016年春の年会
Study on In-Vessel Retention (IVR) of unprotected accident for fast reactor, 1; Overview of IVR evaluation in Anticipated Transient without Scram (ATWS)

Suzuki Toru, Tobita Yoshiharu, Sakai Takaaki, Nakai Ryodai

日本原子力学会2016年春の年会
Studies on the safety design guidelines of Generation-IV Sodium-cooled Fast Reactors, 6; Focal points of safety design guideline for structures, systems and components

Okano Yasushi, Kubo Shigenobu, Nakai Ryodai

日本原子力学会2016年春の年会
Peer review on the safety requirements for the prototype fast breeder reactor "Monju", 1; Overview of safety requirement and domestic/international review

Nakai Ryodai

日本原子力学会2015年秋の大会
Safety design criteria for Generation-IV Sodium-cooled Fast Reactor system

Nakai Ryodai, Tanju S.*

23rd International Conference on Nuclear Engineering (ICONE-23)
International reviews on safety design criteria and development of safety design guidelines for Generation-IV Sodium-cooled Fast Reactor

Okano Yasushi, Nakai Ryodai, Kubo Shigenobu

9th Korea-Japan Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS-9)
Studies on the safety design guidelines of Generation-IV Sodium-cooled Fast Reactors, 2; Study on the safety design guideline of safety approach and design condition

Kubo Shigenobu, Okano Yasushi, Yamano Hidemasa, Nakai Ryodai

日本原子力学会2014年春の年会
Studies on the safety design guidelines of Generation-IV Sodium-cooled Fast Reactors, 1; Orientations and scope of safety design guideline development

Okano Yasushi, Kubo Shigenobu, Sakai Takaaki, Nakai Ryodai

日本原子力学会2014年春の年会
Studies on the safety design criteria of Generation-IV Sodium-cooled Fast Reactors, 2; Safety design criteria for SFR specific structures, systems and components

Fujita Satoshi, Hosoya Takusaburo*, Kubo Shigenobu, Okano Yasushi, Sakai Takaaki, Nakai Ryodai

日本原子力学会2012年秋の大会
Studies on the safety design criteria of Generation-IV Sodium-cooled Fast Reactors, 1; Safety design criteria based on fundamental orientations and approach on safety

Okano Yasushi, Kubo Shigenobu, Sakai Takaaki, Nakai Ryodai

日本原子力学会2012年秋の大会
Studies on the safety design criteria of Generation-IV Sodium-cooled Fast Reactor, 3; Safety design criteria based on the approach for design extension conditions

Kubo Shigenobu, Yamano Hidemasa, Okano Yasushi, Sakai Takaaki, Nakai Ryodai

日本原子力学会2012年秋の大会
Safety design criteria of sodium-cooled fast reactor as a Generation-IV reactor system, 1; Background, motivation and roadmap for the safety design criteria establishment

Okano Yasushi, Sakai Takaaki, Nakai Ryodai

日本原子力学会2011年秋の大会
Safety design criteria of sodium-cooled fast reactor as a generation-IV reactor system, 3; Approach for design extension condition in the safety design criteria of the SFR

Kubo Shigenobu, Yamano Hidemasa, Okano Yasushi, Sakai Takaaki, Nakai Ryodai

日本原子力学会2011年秋の大会
Safety design criteria of sodium-cooled fast reactor as a generation-IV reactor system, 2; Fundamental approach of the safety design criteria for SFR

Fujita Satoshi, Okano Yasushi, Sakai Takaaki, Nakai Ryodai

日本原子力学会2011年秋の大会
Safety-related design requirements and standards for demonstration JSFR, 2; Approaches for safety-related design requirements and standards

Fujita Satoshi, Okano Yasushi, Sakai Takaaki, Nakai Ryodai, Kubo Shigenobu*

日本原子力学会2011年春の年会
Safety-related design requirements and standards for demonstration JSFR, 1; Master plan for developing safety-related design requirements and standards

Nakai Ryodai, Okano Yasushi, Sakai Takaaki, Shimakawa Yoshio*

日本原子力学会2011年春の年会
Safety-related design requirements and standards for demonstration JSFR, 4; Approach for international harmonization of safety-related requirements regarding standardization of JSFR's safety designs

Okano Yasushi, Mihara Takatsugu, Sakai Takaaki, Nakai Ryodai, Kubo Shigenobu*

日本原子力学会2011年春の年会
Development of core damage evaluation technology (Level 2 PSA) for fast reactors, 12; Overview of evaluation technology development

Nakai Ryodai, Suzuki Toru, Kamiyama Kenji, Koyama Kazuya*, Morita Koji*

日本原子力学会2010年春の年会
Development of core damage evaluation technology (Level 2 PSA)

Nakai Ryodai

原子力システム研究開発事業平成21年度成果報告会