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Uno, Yuki; Ouchi, Yasuhiro; Ouchi, Satoshi; Baba, Ryota; Kikuchi, Masanobu; Kawamata, Satoshi
JAEA-Technology 2021-046, 39 Pages, 2023/02
JAEA-Technology-2021-046.pdf:3.76MB
JRR-3 (Japan Research Reactor No.3) is a light water research reactor cooling pool type light water deceleration of low-enriched uranium up to 20MW thermal power. November 1990, begin to operation in modified that we are provided to users as a high neutron flux form reactor facility in various types of irradiation facilities and neutron beam experiment equipment. Currently, JRR-3 has completed the period of facility inspections, which had been extended due to the effects of the Great East Japan Earthquake of March 11, 2011, and has been able to conformity to the New Regulatory Requirements. It has also resumed operation for the first time in about 10 years. FY 2017, overhauled the primary cooling heat exchanger No.1 and No.2 based on a maintenance plan. This is report for take advantage what inspection and maintenance of future about overhaul of the primary cooling system heat exchanger for collect of inspection records and performance.
Imaizumi, Tomomi; Miyauchi, Masaru; Ito, Masayasu; Watahiki, Shunsuke; Nagata, Hiroshi; Hanakawa, Hiroki; Naka, Michihiro; Kawamata, Kazuo; Yamaura, Takayuki; Ide, Hiroshi; et al.
JAEA-Technology 2011-031, 123 Pages, 2012/01
JAEA-Technology-2011-031.pdf:16.08MB
The number of research reactors in the world is decreasing because of their aging. However, the planning to introduce the nuclear power plants is increasing in Asian countries. In these Asian countries, the key issue is the human resource development for operation and management of nuclear power plants after constructed them, and also the necessity of research reactor, which is used for lifetime extension of LWRs, progress of the science and technology, expansion of industry use, human resources training and so on, is increasing. From above backgrounds, the Neutron Irradiation and Testing Reactor Center began to discuss basic concept of a multipurpose low-power research reactor for education and training, etc. This design study is expected to contribute not only to design tool improvement and human resources development in the Neutron Irradiation and Testing Reactor Center but also to maintain and upgrade the technology on research reactors in nuclear power-related companies. This report treats the activities of the working group from July 2010 to June 2011 on the multipurpose low-power research reactor in the Neutron Irradiation and Testing Reactor Center and nuclear power-related companies.
Nakamura, Kazuo*; Jiang, Y.*; Liu, X.*; Mitarai, Osamu*; Kurihara, Kenichi; Kawamata, Yoichi; Sueoka, Michiharu; Hasegawa, Makoto*; Tokunaga, Kazutoshi*; Zushi, Hideki*; et al.
Fusion Engineering and Design, 86(6-8), p.1080 - 1084, 2011/10
Times Cited Count：4 Percentile：32.59(Nuclear Science & Technology)Ouchi, Yasuhiro; Ito, Masatoshi; Oba, Toshinobu; Kawamata, Satoshi; Ishizaki, Katsuhiko
JAEA-Technology 2009-038, 38 Pages, 2009/07
JAEA-Technology-2009-038.pdf:2.87MB
The primary cooling system of JRR-3 is one of important facility which removes heat from reactor core. Therefore, it is necessary for safe and stable reactor operation to keep performance of four pumps which are main equipments of primary cooling system. These four pumps have been checked and maintained appropriately since the operation of JRR-3 started. Maintenance items and its records of primary cooling pumps are reported in this paper. Furthermore, aging problems of primary cooling pumps is investigated to contribute to management for maintenance of primary cooling pumps.
Wang, F.*; Nakamura, Kazuo*; Mitarai, Osamu*; Kurihara, Kenichi; Kawamata, Yoichi; Sueoka, Michiharu; Sato, Konosuke*; Zushi, Hideki*; Hanada, Kazuaki*; Sakamoto, Mizuki*; et al.
Kyushu Daigaku Oyo Rikigaku Kenkyujo RIAM Foramu 2006 Koen Yoshi, p.138 - 141, 2006/06
no abstracts in English
Matsui, Yoshinori; Hanawa, Satoshi; Ide, Hiroshi; Tobita, Masahiro*; Hosokawa, Jinsaku; Onuma, Yuichi; Kawamata, Kazuo; Kanazawa, Yoshiharu; Iwamatsu, Shigemi; Saito, Junichi; et al.
JAEA-Conf 2006-003, p.105 - 114, 2006/05
Irradiation assisted stress corrosion cracking (IASCC) caused by the simultaneous effects of radiation, stress and high temperature water environment is considered to be one of the critical concerns of in-core structural materials not only for light water reactors (LWRs) but also for water-cooled fusion reactors. In the research field of IASCC, post-irradiation examinations (PIEs) for irradiated materials have been mainly carried out, because there are many difficulties on SCC tests under neutron irradiation environment. Hence we have embarked on a development of the test techniques for performing the in-pile SCC tests. In this paper, we describe the developed several in-pile test techniques and the current status of in-pile SCC tests at Japan Materials Testing Reactor (JMTR).
Kusama, Yoshinori; Ogawa, Hiroaki; Kasai, Satoshi; Sugie, Tatsuo; Hatae, Takaki; Sato, Kazuyoshi; Neyatani, Yuzuru; Kawamata, Yoichi; Kurihara, Kenichi
no journal, ,
no abstracts in English
Nakamura, Kazuo*; Matsufuji, Shinji*; Tomoda, Seiji*; Wang, F.*; Mitarai, Osamu*; Kurihara, Kenichi; Kawamata, Yoichi; Sueoka, Michiharu; Sato, Konosuke*; Zushi, Hideki*; et al.
no journal, ,
no abstracts in English
Nakamura, Kazuo*; Matsufuji, Shinji*; Tomoda, Seiji*; Wang, F.*; Mitarai, Osamu*; Kurihara, Kenichi; Kawamata, Yoichi; Sueoka, Michiharu; Sato, Konosuke*; Zushi, Hideki*; et al.
no journal, ,
no abstracts in English
Nakamura, Kazuo*; Matsufuji, Shinji*; Tomoda, Seiji*; Wang, F.*; Mitarai, Osamu*; Kurihara, Kenichi; Kawamata, Yoichi; Sueoka, Michiharu; Sato, Konosuke*; Zushi, Hideki*; et al.
no journal, ,
no abstracts in English
Nakamura, Kazuo*; Yi, J.*; Liu, X.*; Mitarai, Osamu*; Kurihara, Kenichi; Kawamata, Yoichi; Sueoka, Michiharu; Hasegawa, Makoto*; Tokunaga, Kazutoshi*; Zushi, Hideki*; et al.
no journal, ,
no abstracts in English
Yi, J.*; Nakamura, Kazuo*; Liu, X.*; Mitarai, Osamu*; Kurihara, Kenichi; Kawamata, Yoichi; Sueoka, Michiharu; Hasegawa, Makoto*; Tokunaga, Kazutoshi*; Zushi, Hideki*; et al.
no journal, ,
no abstracts in English
Tayama, Yoshinobu; Kanazawa, Yoshiharu; Souzawa, Shizuo; Kawamata, Kazuo; Shizuoka, Yoshihiro; Onizawa, Satoshi; Nakagawa, Tetsuya
no journal, ,
In the JMTR, the power ramping test is planned with high burn-up fuel as irradiation test. In the hot laboratory facilities, in accordance with the plan, as part of the development of facilities to deal with high burn-up fuel, replacing the assemble method using conventional shielding container, the system was developed that carries capsule to cell and performs assembling using capsule loading system put underwater of canal. Development has been completed in FY 2010.
Ouchi, Yasuhiro; Kawamata, Satoshi; Taguchi, Yuji; Kamiishi, Eigo; Koda, Nobuyuki
no journal, ,
no abstracts in English
