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Journal Articles

Development of a method of periodic safety review to cope with the aging degradation of hot laboratories

Tamaoki, Yuichi; Omori, Tsuyoshi; Fujishima, Tadatsune; Mizukoshi, Yasutaka; Sakamoto, Naoki

Proceedings of 53rd Annual Meeting of Hot Laboratories and Remote Handling Working Group (HOTLAB 2016) (Internet), 6 Pages, 2016/11

Post irradiation examinations are conducted in hot laboratories in Oarai Research and Development Center of the Japan Atomic Energy Agency in order to develop fuels and materials for fast reactors. These facilities, the majority of which were constructed in the 1970s, have accumulated operating experience over a period of more than 40 years. Continuous operational safety requires the maintenance of important equipment such as electronic devices, manipulators, in-cell cranes, as well as air conditioning and ventilation systems. A method for the periodic safety review for hot laboratories based on the periodic safety review method employed for preventive maintenance at commercialized power reactors in Japan has been developed. In this paper, the status of implementation of the periodic safety review for hot laboratories using the safety review method are introduced.

Journal Articles

Bithiophene with winding vine-shaped molecular asymmetry; Preparation, structural characterization, and enantioselective synthesis

Toyomori, Yuka*; Tsuji, Satoru*; Mitsuda, Shinobu*; Okayama, Yoichi*; Ashida, Shiomi*; Mori, Atsunori*; Kobayashi, Toru; Miyazaki, Yuji; Yaita, Tsuyoshi; Arae, Sachie*; et al.

Bulletin of the Chemical Society of Japan, 89(12), p.1480 - 1486, 2016/09

 Times Cited Count:6 Percentile:27.13(Chemistry, Multidisciplinary)

Journal Articles

Development of safety review method to cope with an aging degradation for the facilities using nuclear material

Fujishima, Tadatsune; Mizukoshi, Yasutaka; Sakamoto, Naoki; Omori, Tsuyoshi

Hozengaku, 13(2), p.115 - 125, 2014/07

In order to develop fuels and materials for fast reactors, five hot laboratories as a facility using nuclear materials for post irradiation examination (PIE) are now in operation at the Oarai Research and Development Centre of Japan Atomic Energy Agency. More than 30 years have passed since the first hot run of these facilities was started, and it has been indispensable to maintain the principal equipment for continuous safe operation. For application to preventive maintenance and the safe operation, a new safety review method that could be applied for these facilities was developed by modification of periodic safety review tools using for Japanese commercialized power reactors. Effective repair or replacement of equipment before malfunction have been performed and the priority for preventive maintenance could be appropriately determined for stable management of hot facility operations by the developed method.

Journal Articles

Current status of JMTR

Ishihara, Masahiro; Kimura, Nobuaki; Takemoto, Noriyuki; Ooka, Makoto; Kaminaga, Masanori; Kusunoki, Tsuyoshi; Komori, Yoshihiro; Suzuki, Masahide

Proceedings of 5th International Symposium on Material Testing Reactors (ISMTR-5) (Internet), 7 Pages, 2012/10

The JMTR has been utilized for fuel/material irradiation examinations of LWRs, HTGR, fusion reactor as well as for RI productions. The refurbishment of the JMTR was started from the beginning of JFY 2007, and finished in March 2011 as planned schedule. Unfortunately, at the end of the JFY 2010 on March 11, the Great-Eastern-Japan-Earthquake occurred, and functional tests before the JMTR restart were delayed by the earthquake. Moreover, a detail inspection found some damages such as small cracks in the concrete structure, ground sinking around the reactor building. Consequently, the restart will delay from June 2011. Now, the safety evaluation of the facility after the earthquake disaster is being carried out aiming at the restart of the JMTR. The renewed JMTR will be started from JFY 2012 and operated for a period of about 20 years until around JFY 2030. The usability improvement of the JMTR is also discussed with users as the preparations for re-operation.

Journal Articles

Fabrication of U-Pu-Zr metallic fuel elements for the irradiation test at experimental fast test reactor Joyo

Nakamura, Kinya*; Ogata, Takanari*; Kikuchi, Hironobu; Iwai, Takashi; Nakajima, Kunihisa; Kato, Tetsuya*; Arai, Yasuo; Uozumi, Koichi*; Hijikata, Takatoshi*; Koyama, Tadafumi*; et al.

Nihon Genshiryoku Gakkai Wabun Rombunshi, 10(4), p.245 - 256, 2011/12

Sodium-bonded metallic fuel elements were fabricated for the first time in Japan for the irradiation test in the experimental fast test reactor JOYO. U-20Pu-10Zr fuel slugs of 200 mm in length and approximately 5 mm in diameter were fabricated in a small-scale injection casting furnace. Each fuel slug was loaded into the ferritic martenstic stainless steel (PNC-FMS) cladding tube with the sodium thermal bond, thermal insulator and reflector in a helium gas atmosphere glove box. After top-end plug welding to the cladding tube and heat treatment of the welding area, each fuel element was subjected to the sodium bonding process. After the inspection such as element length, gas plenum length and helium-leak tightness, six metallic fuel elements are transported to the JOYO site for the coming irradiation test.

Journal Articles

Activity of safety review for the facilities using nuclear material

Fujishima, Tadatsune; Sakamoto, Naoki; Mizukoshi, Yasutaka; Amagai, Tomio; Omori, Tsuyoshi

Nihon Hozen Gakkai Dai-5-Kai Gakujutsu Koenkai Yoshishu, p.388 - 392, 2008/07

no abstracts in English

Journal Articles

Longitudinal particle simulation for J-PARC RCS

Yamamoto, Masanobu; Anami, Shozo*; Ezura, Eiji*; Hasegawa, Katsushi; Hara, Keigo*; Horino, Mitsuyoshi*; Nomura, Masahiro; Omori, Chihiro*; Schnase, A.; Shimada, Taihei; et al.

Proceedings of 5th Annual Meeting of Particle Accelerator Society of Japan and 33rd Linear Accelerator Meeting in Japan (CD-ROM), p.358 - 360, 2008/00

The beam commissioning has been started at the J-PARC RCS in October 2007, and the beam acceleration and the extraction at 3 GeV has been succeeded. Some longitudinal bunch gymnastics has been tested toward the high intensity operation, one of the issues is arriviating the space charge effect at the injeciton. Since the multi-turn injection scheme is employed at the RCS, the electric charge density of the bunch near the center of the RF bucket tends to be high with only normal fundamental RF capture. Some schemes such as adding 2nd higher harmonic RF, the momentum offset and the phase offset of the 2nd one are simulated by longitudinal particle tracking code to make the bunching factor low. The comparison between the beam test result and the particle tracking simulation is described.

Journal Articles

The Summary report on engineering design activities in the International Thermonuclear Experimental Reactor (ITER) project

Mori, Masahiro; Shoji, Teruaki; Araki, Masanori; Saito, Keiji*; Senda, Ikuo; Omori, Junji*; Sato, Shinichi*; Inoue, Takashi; Ono, Isamu*; Kataoka, Takahiro*; et al.

Nihon Genshiryoku Gakkai-Shi, 44(1), p.16 - 89, 2002/01

no abstracts in English

JAEA Reports

Evaluation on rapid heating rupture behavior in heavily irradiated PNC316 fuel claddings

Yoshitake, Tsunemitsu; Omori, Tsuyoshi; Sakamoto, Naoki; Ukai, Shigeharu

PNC TN9410 96-281, 81 Pages, 1996/09

PNC-TN9410-96-281.pdf:6.48MB

The estimation of the life of fuel claddings at thermal transient event is important for evaluating of the fuel claddings validity under the loss of coolant flow (LOF) accident. In order to estimate the life time of the fuel claddings corresponding to any temperature rising condition, the instrumental technique was first improved in the post-irradiation examination and the temperature-transient-to-burst tests were extensively conducted on PNC316 claddings which were irradiated in JOYO as a fuel test assembly PFC030M and a driver fuel assembly PFD304. The life time evaluation of the irradiated PNC316 fuel claddings was carried out, based on these test results. The results obtained in this work are as follows; (1) As a result of the improvement in the temperature-transient-to-burst testing, the diametral change data and higher hoop stress data were obtained. And the highly accurate measurement of rupture temperature was also achieved. (2) The temperature-transient-to-burst test results showed that the rupture temperature of the irradiated PNC316 cladding was equal to that of unirradiated one up to present neutron fluence in LOF stress condition. It was indicated that the temperature-transient-to-burst property of PNC316 was not influenced by irradiation in lower hoop stress region. (3) The life time of the irradiated PNC316 cladding at any thermal transient condition was evaluated by means of LMP-Life Fraction Rule method. Consequently, the result of estimation for failure temperature of heavily irradiated PNC316 showed the possibility for rising the design limit of the cladding highest temperature for MONJU.

Journal Articles

Determination of Melting Point of Mixed-Oxide Fuel Irradiated in Fast Breeder Reactor

Tachibana, Toshimichi; Itaki, Toshiyuki; Yamanouchi, Sadamu; Omori, Tsuyoshi*

Journal of Nuclear Science and Technology, 22(2), p.155 - 157, 1985/00

 Times Cited Count:19 Percentile:93.02(Nuclear Science & Technology)

None

Oral presentation

Development of 1MW-CW gyrotron for ITER

Kasugai, Atsushi; Sakamoto, Keishi; Takahashi, Koji; Kajiwara, Ken; Ikeda, Yukiharu; Komori, Shinji; Kobayashi, Noriyuki; Kariya, Tsuyoshi*; Minami, Ryutaro*; Mitsunaka, Yoshika*

no journal, , 

no abstracts in English

Oral presentation

Development of safety review method for hot laboratories, 1; Safety review method for hot laboratories

Mizukoshi, Yasutaka; Fujishima, Tadatsune; Sakamoto, Naoki; Amagai, Tomio; Omori, Tsuyoshi

no journal, , 

no abstracts in English

Oral presentation

Development of safety review method for hot laboratories, 2; Operation experiences and safety review of hot laboratories

Fujishima, Tadatsune; Mizukoshi, Yasutaka; Sakamoto, Naoki; Amagai, Tomio; Omori, Tsuyoshi

no journal, , 

no abstracts in English

Oral presentation

Activity of safety review for the facilities using nuclear material, 3; Improvement of the management system for safety operation of aged facilities

Fujishima, Tadatsune; Amagai, Tomio; Mizukoshi, Yasutaka; Sakamoto, Naoki; Omori, Tsuyoshi

no journal, , 

no abstracts in English

Oral presentation

Activity of safety review for the facilities using nuclear material, 2; Safety review results and maintenance experiences for hot laboratories

Amagai, Tomio; Fujishima, Tadatsune; Mizukoshi, Yasutaka; Sakamoto, Naoki; Omori, Tsuyoshi

no journal, , 

In the site of O-arai research and development center of Japan Atomic Energy Agency (JAEA), five hot laboratories for post-irradiation examination and development of plutonium fuels are operated more than 30 years. A safety review method for preventive maintenance on these hot laboratories includes test facilities and devices are established in 2003. After that, the safety review of these facilities and devices are done and taken the necessary maintenance based on the results in each year. In 2008, 372 test facilities and devices in these hot laboratories were checked and reviewed by this method. As a results of the safety review, repair issues of 38 facilities of above 372 facilities were resolved. This report shows the review results and maintenance experiences based on the results.

Oral presentation

Management for preventive maintenance and the safety operation of hot laboratory

Fujishima, Tadatsune; Sakamoto, Naoki; Mizukoshi, Yasutaka; Amagai, Tomio; Omori, Tsuyoshi

no journal, , 

no abstracts in English

Oral presentation

Activity of safety review for the facilities using nuclear material and improvement in the future

Fujishima, Tadatsune; Omori, Tsuyoshi

no journal, , 

no abstracts in English

Oral presentation

Conceptual design of next generation MTR

Nagata, Hiroshi; Yamaura, Takayuki; Naka, Michihiro; Kawamata, Kazuo; Izumo, Hironobu; Hori, Naohiko; Nagao, Yoshiharu; Kusunoki, Tsuyoshi; Kaminaga, Masanori; Komori, Yoshihiro; et al.

no journal, , 

Conceptual design of the high-performance and low-cost next generation materials testing reactor which will be assumed to introduce to the nuclear power plant introduction country started from 2010 in the JAEA. Japanese atomic energy-related companies participate in this project, and this activity role as the environmental management and nuclear human resource development for the new research reactor designs. 10 MW thermal power by plate type fuel elements and swimming pool type was assumed as a design base. High safety, high cost performance, high reactor operation rate, high technology irradiation are targets of this conceptual design.

Oral presentation

Overview of refurbishment project of JMTR

Izumo, Hironobu; Hori, Naohiko; Kaminaga, Masanori; Kusunoki, Tsuyoshi; Ishihara, Masahiro; Komori, Yoshihiro; Suzuki, Masahide; Kawamura, Hiroshi

no journal, , 

The refurbishment project of the JMTR was promoted with two subjects, the one was the replacement of reactor components, and the other was the construction of new irradiation facilities. On the replacement of reactor components, an investigation on aged components was carried out, for concrete structures, tanks, tubes in order to identify their integrity. After the investigation, some components were decided to replace from viewpoints of future maintenance and improvement of reliability. On the construction of new irradiation facilities, corresponding to the user's irradiation request, new irradiation facilities, such as for LWRs materials or fuels, were installed. Furthermore, new project was selected in order to install new irradiation facilities, such as for $$^{99}$$Mo production and PIE equipments. The new JMTR will contribute the promotion on research and development of the nuclear energy from basic to applied fields as an internationally utilized facility.

Oral presentation

Current status of JMTR

Kaminaga, Masanori; Kusunoki, Tsuyoshi; Ishihara, Masahiro; Komori, Yoshihiro; Suzuki, Masahide; Hori, Naohiko

no journal, , 

The Japan Materials Testing Reactor (JMTR) in Japan Atomic Energy Agency (JAEA) is a light water cooled tank type reactor with first criticality in March 1968. Owing to the connection between the JMTR and hot laboratory by a canal, easy re-irradiation tests can be conducted with safe and quick transportation of irradiated samples. The renewed JMTR will be started from JFY 2012 and operated for a period of about 20 years until around JFY 2030. The usability improvement of the JMTR, e.g. higher reactor availability, shortening turnaround time to get irradiation results, attractive irradiation cost, business confidence, is also discussed with users as the preparations for re-operation.

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