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Center for Computational Science & e-Systems
JAEA-Evaluation 2021-001, 66 Pages, 2021/11
JAEA-Evaluation-2021-001.pdf:1.66MB
Research on advanced computational science for nuclear applications, based on "the plan to achieve the mid- and long-term goal of the Japan Atomic Energy Agency", has been performed by Center for Computational Science & e-Systems (CCSE), Japan Atomic Energy Agency. CCSE established a committee consisting of external experts and authorities which does research evaluation and advice for the assistance of the future research and development. This report summarizes the results of the R&D performed by CCSE in FY2020 (April 1st, 2020 - March 31st, 2021), the results expected at the end of the 3rd mid and long-term goal period, and the evaluation by the committee on them.
Center for Computational Science & e-Systems
JAEA-Evaluation 2020-002, 37 Pages, 2020/12
JAEA-Evaluation-2020-002.pdf:1.59MB
Research on advanced computational science for nuclear applications, based on "the plan to achieve the mid and long term goal of the Japan Atomic Energy Agency", has been performed at Center for Computational Science & e-Systems (CCSE), Japan Atomic Energy Agency. CCSE established a committee consisting of outside experts and authorities which does research evaluation and advice for the assistance of the future research and development. This report summarizes the results of the R&D performed at CCSE in FY2019 (April 1st, 2019 - March 31st, 2020) and the evaluation by the committee on them.
Nuclear Safety Research Center, Sector of Nuclear Safety Research and Emergency Preparedness
JAEA-Review 2018-022, 201 Pages, 2019/01
JAEA-Review-2018-022.pdf:20.61MB
Nuclear Safety Research Center (NSRC), Sector of Nuclear Safety Research and Emergency Preparedness, Japan Atomic Energy Agency (JAEA) is conducting technical support to nuclear safety regulation and safety research based on the Mid-Long Term Target determined by Japanese government. This report summarizes the research structure of NSRC and the cooperative research activities with domestic and international organizations as well as the nuclear safety research activities and results in the period from JFY 2015 to 2017 on the nine research fields in NSRC; (1) severe accident analysis, (2) radiation risk analysis, (3) safety of nuclear fuels in light water reactors (LWRs), (4) thermohydraulic behavior under severe accident in LWRs, (5) materials degradation and structural integrity, (6) safety of nuclear fuel cycle facilities, (7) safety management on criticality, (8) safety of radioactive waste management, and (9) nuclear safeguards.
Jitsukawa, Shiro; Tamura, Manabu*; Van der Schaaf, B.*; Klueh, R. L.*; Alamo, A.*; Petersen, C.*; Schirra, M.*; Spaetig, P.*; Odette, G. R.*; Tavassoli, A. A.*; et al.
Journal of Nuclear Materials, 307-311(Part1), p.179 - 186, 2002/12
Times Cited Count：157 Percentile：99.28(Materials Science, Multidisciplinary)Reduced activation ferritic/martensitic steel is the primary candidate structural material for ITER Test Blanket Modules and DEMOnstration fusion reactor because of its excellent dimensional stability under irradiation and lower residual activity as compared with the Ni bearing steels such as the austenitic stainless steels. In this paper, microstructural features, tensile, fracture toughness, creep and fatigue properties of a reduced activation martensitic steel F82H (8Cr-2W-0.04Ta-0.1C) are reported before and after irradiation, in addition to the design concept used for development of this alloy. A large number of collaborative test results including those generated under the IEA working group implementing agreements are collected and are used to evaluate the feasibility of use of F82H steel as one of the reference alloys. The effect of metallurgical variables on the irradiation hardening is reviewed and compared with the results obtained from irradiation experiments.
Tsukada, Takashi; Komori, Yoshihiro; Tsuji, Hirokazu; Nakajima, Hajime; Ito, Haruhiko
Proceedings of International Conference on Water Chemistry in Nuclear Reactor Systems 2002 (CD-ROM), 5 Pages, 2002/00
Irradiation assisted stress corrosion cracking (IASCC) is caused by the synergistic effects of neutron and gamma radiation, residual and applied stresses and high temperature water environment on the structural materials of vessel internals. IASCC has been studied since the beginning of the 1980s and the phenomenological knowledge on IASCC is accrued extensively. However, mainly due to the experimental difficulties, data for the mechanistic understanding and prediction of failures of the specific in-vessel components are still insufficient and further well-controlled experiments are needed [1]. In recent years, efforts to perform the in-pile materials test for IASCC study have been made at some research reactors [2-4]. At JAERI, a high temperature water loop facility was designed to install at the Japan Materials Testing Reactor (JMTR) to carry out the in-core IASCC testing. This report describes an overview of design and specification of the loop facility.
Von-Moellendorff, U.*; Maekawa, Fujio; Giese, H.*; Wilson, P. P. H.*
Fusion Engineering and Design, 51-52(Part.B), p.919 - 924, 2000/11
Times Cited Count：4 Percentile：32.65(Nuclear Science & Technology)no abstracts in English
Seki, Yasushi; Aoki, Isao; Ueda, Shuzo; Nishio, Satoshi; Kurihara, Ryoichi; Tabara, Takashi*
Fusion Technology, 34(3), p.353 - 357, 1998/11
no abstracts in English
JAERI-Data/Code 97-049, 101 Pages, 1997/12
JAERI-Data-Code-97-049.pdf:2.36MB
no abstracts in English
; Watanabe, Katsutoshi; Shindo, Masami
JAERI-Research 95-088, 16 Pages, 1996/01
JAERI-Research-95-088.pdf:1.07MB
no abstracts in English
Nakajima, Hideo
Yosetsu Gakkai-Shi, 64(3), p.168 - 171, 1995/00
no abstracts in English
Onuki, Kaoru; Nakajima, Hayato; Ioka, Ikuo; Futakawa, Masatoshi; Shimizu, Saburo
JAERI-Review 94-006, 53 Pages, 1994/11
JAERI-Review-94-006.pdf:1.52MB
no abstracts in English
Hishinuma, Akimichi
Purazuma, Kaku Yugo Gakkai-Shi, 70(7), p.719 - 725, 1994/07
no abstracts in English
Hishinuma, Akimichi
Purazuma, Kaku Yugo Gakkai-Shi, 70(7), p.697 - 703, 1994/07
no abstracts in English
Ikeda, Yujiro; A.Kumar*; Konno, Chikara; Kosako, Kazuaki*; Oyama, Yukio; *; Maekawa, Hiroshi; M.Z.Youssef*; M.A.Abdou*
JAERI-M 93-018, 164 Pages, 1993/02
no abstracts in English
*; *; Kume, Etsuo
JAERI-M 91-197, 42 Pages, 1991/11
no abstracts in English
JAERI-M 91-060, 164 Pages, 1991/04
no abstracts in English
Yamamoto, Katsumune; Yokouchi, Iichiro; ; ;
Nihon Genshiryoku Gakkai-Shi, 29(8), p.717 - 723, 1987/08
Times Cited Count：1 Percentile：19.44(Nuclear Science & Technology)no abstracts in English
;
Genshiryoku Kogyo, 33(3), p.51 - 55, 1987/03
no abstracts in English
; ; ; ; *; ; *
Advances in Cryogenic Engineering Materials, Vol.32, p.23 - 32, 1986/00
no abstracts in English
; ;
Journal of Nuclear Materials, 102, p.97 - 118, 1981/00
Times Cited Count：14 Percentile：82.97(Materials Science, Multidisciplinary)no abstracts in English
