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Shiotani, Hiroki; Uto, Nariaki; Kawaguchi, Koichi; Shinoda, Yoshihiko*; Ono, Kiyoshi; Namba, Takashi
Proceedings of 20th International Conference on Nuclear Engineering and the ASME 2012 Power Conference (ICONE-20 & POWER 2012) (DVD-ROM), 10 Pages, 2012/07
This paper argues the characteristics evaluation of Fast Reactor and fuel cycle concepts in the FS "Feasibility Study on commercialized fast reactor cycle systems" and the achievement of the performance evaluation conducted in FaCT (Fast Reactor Cycle System Technology Development) project in Japan. The methodologies and way of achievement evaluation has been changed according to the evaluation needs and objectives, etc. Some decision-making methodologies are tried to be applied in the FS, FaCT phase I evaluation put emphasis on the confirmation of the direction of FR cycle development. Although some items of respective facilities showed insufficient achievements because of the challenging design requirements to achieve higher performance, a comprehensive evaluation determined that the performance criteria set by the Japan Atomic Energy Commission were achieved in FaCT phase I evaluation in general.
Chimi, Yasuhiro; Shibata, Akira; Ise, Hideo; Kasahara, Shigeki; Kawaguchi, Yoshihiko*; Nakano, Junichi; Omi, Masao; Nishiyama, Yutaka
Proceedings of Enlarged Halden Programme Group Meeting 2011 (CD-ROM), 10 Pages, 2011/10
In order to load a large specimen of 0.5T-CT up to a high stress intensity factor of 
30 MPa
, we have adopted a lever type loading unit for in-pile irradiation-assisted stress corrosion crack (IASCC) growth tests in the Japan Materials Testing Reactor (JMTR). In this unit, the applied load is generated by shrinking a bellows with lower inner gas pressure than surrounding water pressure and enlarged by leverage. The crack length of the specimen is monitored by potential drop method (PDM) using mineral insulator (MI) cables. In this paper, technical concerns of the in-pile crack growth test unit, especially the estimation procedure of applied load to the specimen inside the irradiation capsule and the evaluation of precision of the PDM signals are presented.
Chimi, Yasuhiro; Kasahara, Shigeki; Ise, Hideo; Kawaguchi, Yoshihiko*; Nakano, Junichi; Nishiyama, Yutaka
Proceedings of 15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors (CD-ROM), p.1219 - 1228, 2011/08
The Japan Atomic Energy Agency (JAEA) has a plan of irradiation tests using the Japan Materials Testing Reactor (JMTR), in order to evaluate the effects of change in material properties and water chemistry caused by the neutron/
-ray irradiation on stress corrosion crack (SCC) growth of stainless steels from the view points of the integrity of reactor core internals for boiling water reactors (BWRs). The difference of SCC growth and its electrochemical corrosion potential (ECP) dependence between in-pile and out-of-pile tests is not fully understood because of a few in-pile data which is comparable with out-of-pile database. This paper presents a systematic review on SCC growth data of irradiated stainless steels and the outline of the in-pile test plan for crack growth of irradiated SUS316L stainless steel under simulated BWR conditions in the JMTR, together with the development of the in-pile test techniques.
Ise, Hideo; Ogiyanagi, Jin; Nakamura, Jinichi; Sasajima, Hideo; Takasa, Akira; Hanawa, Satoshi; Kawaguchi, Yoshihiko; Chimi, Yasuhiro; Nishiyama, Yutaka; Nakamura, Takehiko
FAPIG, (180), p.22 - 25, 2010/02
Refurbishment of Japan Materials Testing Reactor (JMTR) is conducted in Japan Atomic Energy Agency (JAEA) in order to solve irradiation related issues for safe long-term operation of current light water reactors (LWRs) and development of advanced LWRs. JMTR will restart its operation in FY 2011. Manufacturing and installation of the irradiation test facilities on safety research of fuels and materials are also in progress. The outline of the fuels and materials irradiation test plan is described in this report.
Nishiyama, Yutaka; Kawaguchi, Yoshihiko; Onizawa, Kunio
no journal, ,
no abstracts in English
Chimi, Yasuhiro; Hanawa, Satoshi; Ise, Hideo; Kawaguchi, Yoshihiko; Kaji, Yoshiyuki; Tsukada, Takashi; Nakajima, Hajime; Nishiyama, Yutaka; Nakamura, Takehiko
no journal, ,
Japan Atomic Energy Agency (JAEA) has a plan of irradiation tests by using Japan Materials Testing Reactor (JMTR), in order to evaluate the effects of change of materials and water chemistry caused by the neutron/-ray irradiation on the integrity of in-core structural materials for light water reactors (LWRs). In the present study, we are planning the in-pile tests for irradiation-assisted stress corrosion cracking (IASCC) and water chemistry, focusing on the irradiation effects not only of materials but also of water environment (radiolysis of water). The outline of the test conditions will be reported.
