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Ishii, Katsunori; Morita, Keisuke; Noguchi, Hiroki; Aoki, Takeshi; Mizuta, Naoki; Hasegawa, Takeshi; Nagatsuka, Kentaro; Nomoto, Yasunobu; Shimizu, Atsushi; Iigaki, Kazuhiko; et al.
Dai-27-Kai Doryoku, Enerugi Gijutsu Shimpojiumu Koen Rombunshu (Internet), 4 Pages, 2023/09
Koizumi, Mitsuo; Mochimaru, Takanori*; Hironaka, Kota; Takahashi, Tone; Yamanishi, Hirokuni*; Wakabayashi, Genichiro*
Nuclear Instruments and Methods in Physics Research A, 1042, p.167424_1 - 167424_6, 2022/11
Times Cited Count：4 Percentile：52.14(Instruments & Instrumentation)no abstracts in English
Koizumi, Mitsuo; Takahashi, Tone; Hironaka, Kota; Mochimaru, Takanori*; Yamanishi, Hirokuni*; Wakabayashi, Genichiro*
Annual Report of Cooperative Researches at Kindai University Reactor, 2020, p.76 - 80, 2021/12
no abstracts in English
Nishimura, Arashi; Okada, Yuji; Sugaya, Naoto; Sonobe, Hiroshi; Kimura, Nobuaki; Kimura, Akihiro; Hanawa, Yoshio; Nemoto, Hiroyoshi
JAEA-Technology 2021-003, 51 Pages, 2021/05
JAEA-Technology-2021-003.pdf:5.55MB
In the Japan Materials Testing Reactor (JMTR), the leakage accidents of radioactive waste liquid were occurred from the tanks and pipes of the liquid waste disposal facility in the JMTR tank-yard building in JFY2014. In order to respond to the accident, obtain the approval of the JAEA to the design and construction method from JFY2016, the tanks and pipes were replaced from JFY2016 to 2019. In the replaced, the production of the tanks and pipes of the liquid waste disposal facility applied Japanese technical standards correspondingly. On the other hand, the valve did not fall under the category of Japanese technical standards. The manufacturing specifications when replacing the valve were decided based on the including the selecting the standards of production and inspection for valves, Fluid properties, experience in JMTR. The production proceeded while carrying out the decided inspection. The valves that passed all the inspections were installed together with the tanks and pipes of the liquid waste, and the finished inspection was performed as a systems. The construction was completed with those inspection passed. This report is summarized valve Design, production and installation.
Chikazawa, Yoshitaka; Takaya, Shigeru; Tagawa, Akihiro; Kubo, Shigenobu
Proceedings of 2019 International Congress on Advances in Nuclear Power Plants (ICAPP 2019) (Internet), 6 Pages, 2019/05
A maintenance management required to prototype nuclear power reactors has been developed. One of important mission of a prototype reactor is to develop maintenance program for commercial reactors step by step securing safety. Since operating experience at the early stage is limited, the maintenance program for the prototype reactor should be a progressive one. It has to be modified and improved frequently taking into account R&D insight and operation experiences. Additionally, the maintenance program has to consider features of the prototype reactor even at the early stage. To select maintenance grades on particular components/systems, risk informed and graded approaches are effective. And maintenance programs have to take into account degradation mechanism originally due to reactor features. In this paper, applications for maintenance program on sodium valves of prototype fast breeder reactor Monju are studied as an example of prototype sodium-cooled reactors (SFR).
Nishihara, Tetsuo; Sakaki, Akihiro*; Inagaki, Yoshiyuki; Takami, Kazuo*
Nihon Genshiryoku Gakkai Wabun Rombunshi, 3(4), p.381 - 387, 2004/12
JAERI has been carried out research and development on the HTTR hydrogen production system. One of the key components in this system is a high temperature isolation valve (HTIV) installed on the hot helium gas piping penetrating the reactor containment vessel. Angle valve with inner thermal insulator was selected for HTIV and conceptual design was performed. The structural integrity of HTIV was clarified by the stress analyses. Allowable helium leak rate of HTIV was discussed. Helium leak tests using small-scaled valve seat models were performed to decide the seat surface shape and valve closing force. The test results show that the leak rate of wedge shape seat increased in proportion to the number of simulated temperature and stress cycles loaded on the seat models before helium leak test, however that of flat seat did not depend on the number of cycles. So flat seat is adopted for HTIV. It was found that the seat closing force of 30 MPa is reasonable to meet the allowable helium leak rate.
Magara, Masaaki; Sakakibara, Takaaki; Kurosawa, Setsumi; Takahashi, Masato; Sakurai, Satoshi; Hanzawa, Yukiko; Esaka, Fumitaka; Watanabe, Kazuo; Usuda, Shigekazu
Journal of Analytical Atomic Spectrometry, 17(9), p.1157 - 1160, 2002/09
Times Cited Count：11 Percentile：43.51(Chemistry, Analytical)no abstracts in English
Miyo, Yasuhiko; Hiratsuka, Hajime; Masui, Hiroshi*; Hosogane, Nobuyuki; Miya, Naoyuki
JAERI-Tech 2001-070, 33 Pages, 2001/11
JAERI-Tech-2001-070.pdf:3.02MB
In order to improve the gas injection valve used for the operation of JT-60, a new type of valve (multilayer piezoelectric actuator valve) was developed .The conventional valve (bimorph piezoelectric actuator valve) has been used for 15 years from the beginning of experimental operation in April, 1985. Consequently, it came to be hard to keep the performance of the valve as a gas injector because its driving source, piezoelectric element, has deteriorated by long time use.In the design, it is required:(1) to be hard structure for sheet leak,(2) to allow a repair work at atmosphere side without an air vent of the vacuumvessel,(3) to be more smaller and lighter compaired with the conventional one,(4) to have a high maintenance efficiency. The new valve developed was examined with various tests such as gas flow characteristic test, high magnetic field proof test, high temperature proof test and gas flow rate test for aged deterioration. As a result, the valve with desired performance for JT-60 could be obtained.
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and neutron counting with phoswich detectors by using a dual-parameter techniqueYasuda, Kenichiro; Usuda, Shigekazu; Gunji, Hideho
IEEE Transactions on Nuclear Science, 48(4), p.1162 - 1164, 2001/08
Times Cited Count：9 Percentile：55.14(Engineering, Electrical & Electronic)no abstracts in English
Hidaka, Akihide; Maruyama, Yu; Igarashi, Minoru*; Hashimoto, Kazuichiro; Sugimoto, Jun
Nuclear Engineering and Design, 200(1-2), p.303 - 315, 2000/08
Times Cited Count：8 Percentile：46.13(Nuclear Science & Technology)no abstracts in English
Nishihara, Tetsuo; Iwatsuki, Jin*
JAERI-Tech 99-078, p.55 - 0, 1999/11
no abstracts in English
H.Yang*; Hidaka, Akihide; Sugimoto, Jun
JAERI-Tech 99-013, 97 Pages, 1999/03
no abstracts in English
Ebisawa, Noboru; Ito, Takao
KEK Proceedings 99-17 (CD-ROM), 4 Pages, 1999/00
no abstracts in English
Ishii, Toshimitsu; Ooka, Norikazu; Saito, Junichi; Kobayashi, Shunichi; Takahashi, Kunihiro; Tsukada, Takashi; Iwai, Takashi; Kurosawa, Yoshiaki; Hoshiya, Taiji; Tsuji, Hirokazu
Proceedings of International Symposium on Case Histories on Integrity and Failures in Industry (CHIFI), p.227 - 236, 1999/00
no abstracts in English
Hidaka, Akihide; Maruyama, Yu; Shibazaki, Hiroaki*; Maeda, Akio; Harada, Yuhei; ; Yoshino, T.*; Sugimoto, Jun
JAERI-Tech 98-026, 83 Pages, 1998/07
no abstracts in English
Usuda, Shigekazu
Radioisotopes, 47(3), p.227 - 229, 1998/03
no abstracts in English
- discrimination in liquid scintillation measurementKuwabara, Jun; Shimizu, Isamu
Radioisotopes, 47(3), p.222 - 225, 1998/03
no abstracts in English
Usuda, Shigekazu; Yasuda, Kenichiro; Sakurai, Satoshi
Applied Radiation and Isotopes, 49(9-11), p.1131 - 1134, 1998/00
Times Cited Count：13 Percentile：70.26(Chemistry, Inorganic & Nuclear)no abstracts in English
Usuda, Shigekazu; Yasuda, Kenichiro
Hoshasen, 24(1), p.59 - 66, 1998/00
no abstracts in English
