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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.
Izumo, Hironobu; Chimi, Yasuhiro; Ishida, Takuya; Kawamata, Kazuo; Inoue, Shuichi; Ide, Hiroshi; Saito, Takashi; Ise, Hideo; Miwa, Yukio; Ugachi, Hirokazu; et al.
JAEA-Technology 2009-011, 31 Pages, 2009/04
JAEA-Technology-2009-011.pdf:4.38MB
Regarding Irradiation Assisted Stress Corrosion Cracking (IASCC) for austenitic stainless steel of the light water reactor (LWR), a lot of data that concerns the post irradiation evaluation (PIE) is acquired. However, IASCC occurs in LWR condition. Therefore, it is necessary to confirm adequacy of the PIE data comparing the experiment data under the simulated LWR condition. Bigger specimen is needed to acquire the effective data for the destruction dynamics in the study of stress corrosion cracking under neutron irradiation condition. Therefore, development of a new crack growth unit which can load to bigger is necessary to the neutron irradiation test. As a result, a prospect was provided in the unit that could load to specimen by changing load mechanism to the lever type from the linear type. And also, in the development of crack propagation unit, some technical issues were extracted from the discussion of the unit structure adopting the LVDT (Linear Variable Differential Transformer).
Nakamura, Hiroo; Riccardi, B.*; Loginov, N.*; Ara, Kuniaki*; Burgazzi, L.*; Cevolani, S.*; Dell'Ocro, G.*; Fazio, C.*; Giusti, D.*; Horiike, Hiroshi*; et al.
Journal of Nuclear Materials, 329-333(1), p.202 - 207, 2004/08
Times Cited Count：14 Percentile：66.09(Materials Science, Multidisciplinary)International Fusion Materials Irradiation Facility (IFMIF), being developed by EU, JA, RF and US, is a deuteron-lithium (Li) reaction neutron source for fusion materials testing. In the end of 2002, 3 year Key Element technology Phase (KEP) to reduce the key technology risk factors has been completed. This paper describes these KEP tasks results. To evaluate Li flow characteristics, a water and Li flow experiments have been done. To develop Li purification system, evaluation of nitrogen and tritium gettering materials have been done. Conceptual design of remote handling and basic experiment have been donde. In addition, safety analysis and diganostics design have been done. In the presentation, the latest design and future prospects will be also summarized.
Kuroda, Toshimasa*; Sato, Kazuyoshi; Akiba, Masato; Ezato, Koichiro; Enoeda, Mikio; Osaki, Toshio*; Kosaku, Yasuo; Sato, Satoshi; Sato, Shinichi*; Suzuki, Satoshi*; et al.
JAERI-Tech 2002-044, 25 Pages, 2002/03
JAERI-Tech-2002-044.pdf:2.68MB
no abstracts in English
Ise, Hideo*; Izaki, Makoto*; Oishi, Haruo*; Mori, Seiji*; Ako, Kentaro*; Moriyama, Hisashi*; Kagaya, Hiroaki*; Kobayashi, Masami*; Taguchi, Ko*; Shibanuma, Kiyoshi
FAPIG, (159), p.10 - 14, 2001/11
no abstracts in English
Araki, Masanori; Akiba, Masato; Dairaku, Masayuki; *; Ise, Hideo*; Seki, Masahiro; ;
Journal of Nuclear Science and Technology, 29(9), p.901 - 908, 1992/09
no abstracts in English
Kunugi, Tomoaki; Akiba, Masato; Ogawa, Masuro; Ise, Hideo*; Yamazaki, Seiichiro*
Fusion Technology, 21, p.1863 - 1867, 1992/05
no abstracts in English
Araki, Masanori; Akiba, Masato; Seki, Masahiro; Dairaku, Masayuki; Ise, Hideo*; Yamazaki, Seiichiro*; Tanaka, Shigeru;
Fusion Engineering and Design, 19, p.101 - 109, 1992/00
Times Cited Count：15 Percentile：78.31(Nuclear Science & Technology)no abstracts in English
Ogawa, Masuro; Araki, Masanori; Seki, Masahiro; Kunugi, Tomoaki; Fukaya, Kiyoshi; Ise, Hideo*
Fusion Engineering and Design, 19, p.193 - 202, 1992/00
Times Cited Count：11 Percentile：70.41(Nuclear Science & Technology)no abstracts in English
Akiba, Masato; Araki, Masanori; ; Ise, Hideo*; Nakamura, Kazuyuki; ; Dairaku, Masayuki; Tanaka, Shigeru
Journal of Nuclear Materials, 191-194, p.373 - 376, 1992/00
no abstracts in English
Araki, Masanori; Akiba, Masato; ; Dairaku, Masayuki; ; Ise, Hideo*; Nakamura, Kazuyuki; Seki, Masahiro; Tanaka, Shigeru
Proc. of the 14th Symp. on Fusion Engineering,Vol. 1, p.357 - 360, 1992/00
no abstracts in English
; Akiba, Masato; Araki, Masanori; Dairaku, Masayuki; Ise, Hideo*;
JAERI-M 91-085, 20 Pages, 1991/05
no abstracts in English
M.Z.Hasan*; Kunugi, Tomoaki; Seki, Masahiro; Yokokawa, Mitsuo; Ise, Hideo*; ;
Fusion Technology, 19, p.908 - 912, 1991/05
no abstracts in English
Seki, Masahiro; Akiba, Masato; Araki, Masanori; ; Dairaku, Masayuki; *; Fukaya, Kiyoshi; Ogawa, Masuro; Ise, Hideo*
Fusion Engineering and Design, 15, p.59 - 74, 1991/00
Times Cited Count：17 Percentile：84.12(Nuclear Science & Technology)no abstracts in English
Akiba, Masato; Takatsu, Hideyuki; Kuroda, Toshimasa*; *; Araki, Masanori; Dairaku, Masayuki; Ise, Hideo*; ; Tanaka, Shigeru; ; et al.
Fusion Engineering and Design, 18, p.99 - 104, 1991/00
Times Cited Count：3 Percentile：40.8(Nuclear Science & Technology)no abstracts in English
; Akiba, Masato; Araki, Masanori; Seki, Masahiro; Ise, Hideo*; *; *; *; Yamazaki, Seiichiro*
Proc. of the 2nd Japan Int. SAMPE Symp. on Advanced Materials for Future Industries,Needs and Seeds, p.1176 - 1182, 1991/00
no abstracts in English
Araki, Masanori; Akiba, Masato; Ise, Hideo*; Dairaku, Masayuki; ; Seki, Masahiro
Int. Symp. on Carbon New Processing and New Applications; Extended Abstracts, Vol. l, p.210 - 213, 1990/00
no abstracts in English
*; Iida, Hiromasa; *; Adachi, Junichi*; ; Ebisawa, Katsuyuki*; *; Fukaya, Kiyoshi; *; *; et al.
JAERI-M 87-219, 336 Pages, 1988/01
no abstracts in English
