Nobuchika Kawasaki - My portal

Profile Information

Affiliation: Japan Atomic Energy Agency

J-GLOBAL ID: 202101002512254655
researchmap Member ID: R000021802

Papers

Study on a unified criterion for preventing plastic strain accumulation due to long distance travel of temperature distribution

Okajima Satoshi, Wakai Takashi, Kawasaki Nobuchika

Mechanical Engineering Journal (Internet), 4(5) 16-00641\_1-16-00641\_11, Oct, 2017 Peer-reviewed
Development on rubber bearings for sodium-cooled fast reactor, 3; Ultimate properties of a half scale thick rubber bearings based on breaking test

Fukasawa Tsuyoshi*, Okamura Shigeki*, Yamamoto Tomohiko, Kawasaki Nobuchika, Hirotani Tsutomu*, Moriizumi Eriko*, Sakurai Yu*, Masaki Nobuo*

Proceedings of 2016 ASME Pressure Vessels and Piping Conference (PVP 2016) (Internet), 10, Jul, 2016 Peer-reviewed
Development of seismic isolation systems for sodium-cooled fast reactors in Japan

Kawasaki Nobuchika, Watakabe Tomoyoshi, Wakai Takashi, Yamamoto Tomohiko, Fukasawa Tsuyoshi*, Okamura Shigeki*

Proceedings of 2016 ASME Pressure Vessels and Piping Conference (PVP 2016) (Internet), 8, Jul, 2016 Peer-reviewed
Development on rubber bearings for sodium-cooled fast reactor, 2; Fundamental characteristics of half-scale rubber bearings based on static test

Fukasawa Tsuyoshi*, Okamura Shigeki*, Yamamoto Tomohiko, Kawasaki Nobuchika, Somaki Takahiro*, Sakurai Yu*, Masaki Nobuo*

Proceedings of 2015 ASME Pressure Vessels and Piping Conference (PVP 2015) (Internet), 10, Jul, 2015 Peer-reviewed
Development on rubber bearings for sodium-cooled fast reactor, 1; Examination plan

Yamamoto Tomohiko, Kawasaki Nobuchika, Fukasawa Tsuyoshi*, Okamura Shigeki*, Somaki Takahiro*, Samejima Yusuke*, Masaki Nobuo*

Proceedings of 2015 ASME Pressure Vessels and Piping Conference (PVP 2015) (Internet), 7, Jul, 2015 Peer-reviewed
Parametric design study about seismic isolation system for fast reactor JSFR

Kawasaki Nobuchika, Yamamoto Tomohiko, Fukasawa Tsuyoshi*, Okamura Shigeki*

Proceedings of 2015 ASME Pressure Vessels and Piping Conference (PVP 2015) (Internet), 9, Jul, 2015 Peer-reviewed
JSFR design progress related to development of safety design criteria for generation IV sodium-cooled fast reactors, 3; Progress of component design

Enuma Yasuhiro, Kawasaki Nobuchika, Orita Junichi*, Eto Masao*, Miyagawa Takayuki*

Proceedings of 23rd International Conference on Nuclear Engineering (ICONE-23) (DVD-ROM), 6, May, 2015 Peer-reviewed
Design study for reactor system of fast reactor JSFR; Concept of reactor system

Kawasaki Nobuchika, Sakamoto Yoshihiko, Eto Masao*, Taniguchi Yoshihiro*, Kamishima Yoshio*

Proceedings of 2015 International Congress on Advances in Nuclear Power Plants (ICAPP 2015) (CD-ROM), 760-769, May, 2015 Peer-reviewed
Comparison and assessment of the creep-fatigue evaluation methods with notched specimens made of Mod.9Cr-1Mo steel

Ando Masanori, Hirose Yuichi*, Karato Takanori*, Watanabe Sota*, Inoue Osamu*, Kawasaki Nobuchika, Enuma Yasuhiro*

Journal of Pressure Vessel Technology, 136(4) 041406\_1-041406\_10, Aug, 2014 Peer-reviewed
Stress mitigation design of a tubesheet by considering the thermal stress inducement mechanism

Ando Masanori, Takasho Hideki*, Kawasaki Nobuchika, Kasahara Naoto*

Journal of Pressure Vessel Technology, 135(6) 061207\_1-061207\_10, Dec, 2013 Peer-reviewed
Verification of the estimation methods of strain range in notched specimens made of Mod.9Cr-1Mo steel

Ando Masanori, Hirose Yuichi*, Date Shingo*, Watanabe Sota*, Enuma Yasuhiro*, Kawasaki Nobuchika

Journal of Pressure Vessel Technology, 134(6) 061403\_1-061403\_12, Dec, 2012 Peer-reviewed
Conceptual design study for the demonstration reactor of JSFR, 4; Structural design of reactor vessel

Kawasaki Nobuchika, Okamura Shigeki*, Sawa Naoki*, Sakamoto Yoshihiko, Negishi Kazuo

Proceedings of 19th International Conference on Nuclear Engineering (ICONE-19) (CD-ROM), 7, Oct, 2011 Peer-reviewed
An Evaluation method for plastic buckling of cantilever type pipes controlled by displacement loads, 2; Verification of proposal method by buckling test

Ando Masanori, Tezuka Taiji*, Nakamura Toshio*, Okawa Tomohiro*, Enuma Yasuhiro*, Kawasaki Nobuchika, Tsukimori Kazuyuki

Proceedings of 2011 ASME Pressure Vessels and Piping Conference (PVP 2011) (CD-ROM), 8, Jul, 2011 Peer-reviewed
An Evaluation method for plastic buckling of cantilever type pipes controlled by displacement loads, 1; Proposal of the estimation method and the criterion

Ando Masanori, Tezuka Taiji*, Nakamura Toshio*, Okawa Tomohiro*, Enuma Yasuhiro*, Kawasaki Nobuchika, Tsukimori Kazuyuki

Proceedings of 2011 ASME Pressure Vessels and Piping Conference (PVP 2011) (CD-ROM), 9, Jul, 2011 Peer-reviewed
Comparison of creep-fatigue evaluation methods with notched specimens made of Mod.9Cr-1Mo steel

Ando Masanori, Hirose Yuichi*, Karato Takanori*, Watanabe Sota*, Inoue Osamu*, Kawasaki Nobuchika, Enuma Yasuhiro*

Proceedings of 2011 ASME Pressure Vessels and Piping Conference (PVP 2011) (CD-ROM), 11, Jul, 2011 Peer-reviewed
Experimental investigation of strain concentration evaluation based on the stress redistribution locus method

Isobe Nobuhiro*, Kawasaki Nobuchika, Ando Masanori, Sukekawa Masayuki*

Journal of Nuclear Science and Technology, 48(4) 567-574, Apr, 2011 Peer-reviewed
Verification of the prediction methods of strain range in notched specimens made of Mod.9Cr-1Mo

Ando Masanori, Hirose Yuichi*, Date Shingo*, Watanabe Sota*, Enuma Yasuhiro*, Kawasaki Nobuchika

Proceedings of 2010 ASME Pressure Vessels and Piping Conference (PVP 2010) (CD-ROM), 11, Jul, 2010 Peer-reviewed
A Comparative study of negligible creep curves for rational elevated temperature design

Ando Masanori, Isobe Nobuhiro*, Kawasaki Nobuchika, Sukekawa Masayuki*, Kasahara Naoto*

Proceedings of 2009 ASME Pressure Vessels and Piping Division Conference (PVP 2009) (CD-ROM), 10, Jul, 2009 Peer-reviewed
Stress mitigation design of tubesheets with consideration of thermal stress inducement mechanism

Ando Masanori, Takasho Hideki*, Kawasaki Nobuchika, Kasahara Naoto

Proceedings of 2008 ASME Pressure Vessels and Piping Division Conference (PVP 2008) (CD-ROM), 10, Jul, 2008 Peer-reviewed
Spectra thermal fatigue tests under frequency controlled fluid temperature variation; Superposed sinusoidal temperature fluctuations tests

Kawasaki Nobuchika, Takasho Hideki*, Kobayashi Sumio, Hasebe Shinichi, Kasahara Naoto

Proceedings of 2008 ASME Pressure Vessels and Piping Division Conference (PVP 2008) (CD-ROM), 9, Jul, 2008 Peer-reviewed

Misc.

Study on unified criteria for preventing plastic strain accumulation due to thermal stress with long range travel

Okajima Satoshi, Wakai Takashi, Kawasaki Nobuchika

Proceedings of International Conference on Asia-Pacific Conference on Fracture and Strength 2016 (APCFS 2016) (USB Flash Drive), 269-270, Sep, 2016
Experimental investigation of strain concentration evaluation based on the stress redistribution locus method

Isobe Nobuhiro*, Kawasaki Nobuchika, Ando Masanori, Sukekawa Masayuki*

Proceedings of International Conference on Fast Reactors and Related Fuel Cycles (FR 2009) (CD-ROM), 11, Jan, 2012
Equivalent plastic solid materials of perforated plates based on effective stress ratio

Kasahara Naoto*, Takasho Hideki*, Kawasaki Nobuchika, Ando Masanori

Proceedings of International Symposium on Plasticity 2010 (CD-ROM), 34-36, Jan, 2010
Development of elevated temperature structural design method for fast reactor vessels, 3; Critical temperature difference of 316FR steel and Inconel-718 for high-cycle thermal fatigue

Okajima Satoshi, Isobe Nobuhiro*, Kawasaki Nobuchika, Sukekawa Masayuki*

Nippon Kikai Gakkai 2009-Nendo Nenji Taikai Koen Rombunshu, Vol.1, 125-126, Sep, 2009
Development of constitutive models for fast reactor design; Strategy of the study and results in the first half stage

Tsukimori Kazuyuki, Iwata Koji, Kawasaki Nobuchika, Yada Hiroki, Kasahara Naoto

Transactions of 20th International Conference on Structural Mechanics in Reactor Technology (SMiRT-20) (CD-ROM), 10, Aug, 2009
Estimation of the buckling limits for secondary stress in FBR piping systems

Ando Masanori, Tezuka Taiji*, Sato Keisuke*, Kawasaki Nobuchika, Enuma Yasuhiro*, Tsukimori Kazuyuki

Nippon Kikai Gakkai Kanto Shibu Ibaraki Koenkai 2009 Koen Rombunshu, 171-172, Aug, 2009
Development of elevated temperature structural design method for fast reactor vessels, 5; Effect of ratcheting strain on 316FR fatigue strength

Okajima Satoshi, Date Shingo*, Kawasaki Nobuchika, Kikuchi Koichi*, Isobe Nobuhiro*, Kasahara Naoto

Nippon Kikai Gakkai M\&M 2009 Zairyo Rikigaku Kanfarensu Koen Rombunshu (CD-ROM), 537-538, Jul, 2009
Development of elevated temperature structural design method for fast reactor vessels, 4; Effect of ratcheting strain on 316FR creep-fatigue strength

Kawasaki Nobuchika, Date Shingo*, Kikuchi Koichi*, Isobe Nobuhiro*, Kasahara Naoto

Nippon Kikai Gakkai M\&M 2009 Zairyo Rikigaku Kanfarensu Koen Rombunshu (CD-ROM), 535-536, Jul, 2009
Applicability of effective stress concept to structural design of tubesheets

Kasahara Naoto*, Takasho Hideki*, Kawasaki Nobuchika, Ando Masanori

Nippon Kikai Gakkai M\&M 2008 Zairyo Rikigaku Kanfarensu Koen Rombunshu (CD-ROM), OS0623\_1-OS0623\_2, Sep, 2008
Development of elevated temperature structural design method for fast reactor vessels, 1; Concept of development in strength evaluation

Kawasaki Nobuchika, Nagae Yuji, Kato Shoichi, Ando Masanori, Kasahara Naoto

Dai-13-Kai Doryoku, Enerugi Gijutsu Shimpojiumu Koen Rombunshu, 507-510, Jun, 2008
Thermal fatigue evaluation method considering fluid-structure interaction against fluid temperature fluctuation

Kasahara Naoto, Kawasaki Nobuchika, Kamide Hideki, Sakai Shinsuke*, Okajima Satoshi*

Proceedings of International Symposium on Research for Aging Management of Light Water Reactors and Its Future Trend, 23\_1-23\_16, Oct, 2007
Influence of crack initiation, propagation and coalescence on load in fatigue test at elevated temperature

Bubphachot B.*, Watanabe Osamu*, Kawasaki Nobuchika, Kasahara Naoto

Nippon Kikai Gakkai M\&M 2007 Zairyo Rikigaku Kanfarensu Koen Rombunshu (CD-ROM), 346-347, Oct, 2007
Observation of initiation and propagation crack of perforated plate at elevated temperature

Bubphachopt B.*, Watanabe Osamu*, Kawasaki Nobuchika, Kasahara Naoto

Nippon Kikai Gakkai 2007-Nendo Nenji Taikai Koen Rombunshu, Vol.1, 689-690, Sep, 2007
A General determination method of non-linear equivalent material properties for perforated plates

Kasahara Naoto, Kawasaki Nobuchika, Wakai Takashi, Takasho Hideki*

Transactions of 19th International Conference on Structural Mechanics in Reactor Technology (SMiRT-19) (CD-ROM), 8, Aug, 2007
Fatigue strength evaluation of perforated plate at elevated temperature based on SRL method

Watanabe Osamu*, Bubphachot B.*, Kasahara Naoto, Kawasaki Nobuchika

Nippon Kikai Gakkai 2006-Nendo Nenji Taikai Koen Rombunshu, Vol.1, 117-118, Sep, 2006
Thermal hydraulic-structure total analysis of core support structure

Kawasaki Nobuchika, Hosogai Hiromi*, Furuhashi Ichiro*, Kasahara Naoto

Nippon Kikai Gakkai 2006-Nendo Nenji Taikai Koen Rombunshu, Vol.1, 2006 959-960, Sep, 2006
Thermal fatigue evaluation of partially cooled pipes

Kawasaki Nobuchika, Takasho Hideki*, kasahara Naoto

5.1$\sim$5.20, Oct, 2004
Spectra thermal fatigue tests under frequency controlled fluid temperature change; Development of test equipment and preliminary tests

kasahara Naoto, Hasebe Shinichi, Kobayashi Sumio, Ando Masanori, Kawasaki Nobuchika, Morita Hiroshi*

ASME PVP-Vol.472, -2986, Jan, 2004
Development of System Based Code Vol.6: Probabilistic approach Part 2; Model calculation of failure probability about End-caps

Kawasaki Nobuchika, Asayama Tai

JNC-TN9400 2003-086, 69, Sep, 2003
None

Kawasaki Nobuchika

JNC-TY9400 2002-018, 527, Sep, 2002

Presentations

Conceptual design of horizontal type under sodium viewer for next generation sodium-cooled fast reactor

Aizawa Kosuke, Kawasaki Nobuchika, Chikazawa Yoshitaka, Eto Masao*, Matsunaga Shoko*

日本原子力学会2016年秋の大会
Study of reactor structure for next generation sodium fast reactor; Insertability of core assemblies considering deformation due to irradiation

Matsubara Shinichiro*, Imaoka Kengo*, Ikarimoto Iwao*, Ogawa Shinta*, Eto Masao*, Kawasaki Nobuchika

日本原子力学会2016年春の年会
Study on external hazard conditions applied to conceptual design of a next-generation sodium-cooled fast reactor

Yamano Hidemasa, Kawasaki Nobuchika, Kubo Shigenobu

日本原子力学会2016年春の年会
Study on reduction of vertical seismic response for JSFR

Yamamoto Tomohiko, Kawasaki Nobuchika, Ishikawa Nobuyuki, Chikazawa Yoshitaka, Fukasawa Tsuyoshi*, Okamura Shigeki*

日本原子力学会2015年秋の大会
Design study for reactor system of fast reactor JSFR, 2; Aseismic study of the column type UIS with a slit

Eto Masao*, Kamishima Yoshio*, Kawasaki Nobuchika, Sakamoto Yoshihiko, Noi Hiromi*

日本原子力学会2014年秋の大会
Design study for reactor system of fast reactor JSFR, 1; Concept of reactor system

Kawasaki Nobuchika, Sakamoto Yoshihiko, Eto Masao*, Taniguchi Yoshihiro*, Kamishima Yoshio*

日本原子力学会2014年秋の大会
Design study for seismic isolation system of fast reactor JSFR, 1; Concept of seismic isolation system

Sakamoto Yoshihiko, Fukasawa Tsuyoshi*, Kawasaki Nobuchika, Okamura Shigeki*

日本原子力学会2014年秋の大会
Development of evaluation method based on inelastic analyses for structural design of fast reactor components

Kasahara Naoto, Tsukimori Kazuyuki, Iwata Koji, Kawasaki Nobuchika, Okajima Satoshi

日本原子力学会計算科学技術部会「シミュレーションの信頼性」ワーキング・グループ第3回会合
Validation for the creep-fatigue evaluation method under intermediate hold conditions by the tests on the liquid-surface model

Okajima Satoshi, Kawasaki Nobuchika, Kasahara Naoto

日本機械学会M\&M2010材料力学カンファレンス
Development of evaluation method based on inelastic analyses for structural design of fast reactor components, 1; Guidelines for inelastic design analysis

Tsukimori Kazuyuki, Iwata Koji, Kawasaki Nobuchika, Kasahara Naoto

日本機械学会M\&M2010材料力学カンファレンス
Development of evaluation method based on inelastic analyses for structural design of fast reactor components, 2; Summary of recommended inelastic constitutive models

Iwata Koji, Tsukimori Kazuyuki, Kasahara Naoto, Kawasaki Nobuchika

日本機械学会M\&M2010材料力学カンファレンス
Development of evaluation method based on inelastic analyses for structural design of fast reactor components, 4; Examples of design analyses by use of the guidelines

Tsukimori Kazuyuki, Okajima Satoshi, Ando Masanori, Kasahara Naoto, Kawasaki Nobuchika

日本機械学会M\&M2010材料力学カンファレンス
Development of evaluation method based on inelastic analyses for structural design of fast reactor components, 3; Verification and validation of constitutive models

Iwata Koji, Tsukimori Kazuyuki, Kawasaki Nobuchika

日本機械学会M\&M2010材料力学カンファレンス
Conceptual design study toward the demonstration reactor of JSFR, 2; Reactor vessel design of JSFR

Negishi Kazuo, Kawasaki Nobuchika, Sakamoto Yoshihiko, Kotake Shoji, Okamura Shigeki*, Kamishima Yoshio*

日本原子力学会2010年秋の大会
Conceptual design toward the commercial reactor of JSFR, 4; Reactor system

Eto Masao*, Kamishima Yoshio*, Okamura Shigeki*, Negishi Kazuo*, Sakamoto Yoshihiko, Kawasaki Nobuchika

日本原子力学会2010年秋の大会
Conceptual design study and related R\&Ds toward the demonstration reactor of JSFR, 4; Verification of elevated temperature structural design standard for application of high chromium steel

Ando Masanori, Kawasaki Nobuchika, Enuma Yasuhiro*, Urata Kazuhiro*, Date Shingo*, Hirose Yuichi*, Watanabe Sota*

日本原子力学会2010年春の年会
Development of elevated temperature structural design method for fast reactor vessels, 2; Creep-fatigue evaluation method of intermediate hold type

Kawasaki Nobuchika, Kato Shoichi, Yamauchi Masafumi*, Nagae Yuji, Kikuchi Koichi*, Kasahara Naoto

日本機械学会2009年度年次大会
Development of constitutive models for fast breeder reactor design; Multi-linear kinematic hardening model with stress reversal-on resetting

Iwata Koji, Tsukimori Kazuyuki, Kawasaki Nobuchika, Yada Hiroki, Kasahara Naoto

第52回日本学術会議材料工学連合講演会
Design evaluation of tubesheet structures for steam generators of FBRs, 1; Stress mitigation tubesheet design with consideration of the stress inducement mechanism

Ando Masanori, Takasho Hideki*, Kawasaki Nobuchika, Kasahara Naoto

日本原子力学会2008年春の年会