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JAEA Reports

Annual report of Department of Research Reactor and Tandem Accelerator, JFY2015; Operation, utilization and technical development of JRR-3, JRR-4, NSRR, Tandem Accelerator and RI Production Facility

Department of Research Reactor and Tandem Accelerator

JAEA-Review 2017-027, 142 Pages, 2018/01

JAEA-Review-2017-027.pdf:5.75MB

The Department of Research Reactor and Tandem Accelerator is in charge of the operation, utilization and technical development of JRR-3 (Japan Research Reactor No.3), JRR-4 (Japan Research Reactor No.4), NSRR (Nuclear Safety Research Reactor), Tandem Accelerator and RI Production Facility. This annual report describes the activities of our department in fiscal year of 2015.

Journal Articles

Approach for the treatment and disposal of dismantling waste (Research reactor)

Sakamoto, Yoshiaki

Genshiryoku Bakkuendo Kenkyu (CD-ROM), 24(2), p.141 - 146, 2017/12

Some research reactors are under decommissioning or preparation for application of decommissioning license for regulation authority in our country. The reasonable treatment and disposal of dismantling waste is important for decommissioning of research reactors. Therefore, in this paper, JAEA's approach of the treatment and disposal of dismantling waste was introduced from the point of view of disposal of low level radioactive waste arising from research, industrial and medical facilities.

Journal Articles

Study of the reduction method of the helium gas leakage from bolted gasket flanged connection for HTGRs

Hamamoto, Shimpei; Takada, Shoji

Proceedings of 2017 International Congress on Advances in Nuclear Power Plants (ICAPP 2017) (CD-ROM), 4 Pages, 2017/04

Journal Articles

A Sensitivity analysis for construction of the seismic response analysis model of a nuclear reactor building by using a three-dimensional finite element model

Choi, B.; Nishida, Akemi; Nakajima, Norihiro

Kozo Kogaku Rombunshu, B, 63B, p.325 - 333, 2017/03

The Japan Atomic Energy Agency promotes research and development of three-dimensional vibration simulation technologies for nuclear facilities. In this paper, we report a seismic response analysis of the Tohoku Pacific Coast Earthquake using three-dimensional models of the High-Temperature Engineering Test Reactor (HTTR) building. We conducted a sensitivity study using input parameters with uncertainty. Furthermore, we examined the variation of the seismic response results against the input parameters.

Journal Articles

Prolonged stoppage of research reactors and critical assemblies affects human resource development

Uesaka, Mitsuru*; Mineo, Hideaki

Nippon Genshiryoku Gakkai-Shi, 58(8), p.468 - 473, 2016/08

All the research reactors and critical assemblies (hereinafter RRCAs) in Japan are stopped in order to fulfil the new regulatory requirements, which were reinforced after the accident at the Tokyo Electric Power Company's Fukushima Daiichi Nuclear Power Station. These RRCAs have played important roles in the areas of human resource development, academic research, medical and industrial application of nuclear technology. Prolonged stoppage of RRCAs affects adversely those activities. Atomic Energy Society of Japan set up a group to discuss this issue. The group has shown a proposal that the roles of the RRCAs, which are indispensable facilities to nuclear human resource development, should be placed positively in the energy policy and the science and technology policy of the country.

Journal Articles

A Parametric study for the seismic response analysis of a nuclear reactor building by using a three-dimensional finite element model

Choi, B.; Nishida, Akemi; Nakajima, Norihiro

Proceedings of 24th International Conference on Nuclear Engineering (ICONE-24) (DVD-ROM), 7 Pages, 2016/06

Research and development of three-dimensional vibration simulation technologies for nuclear facilities have been promoted in the Center for Computational Science and e-Systems of the Japan Atomic Energy Agency (JAEA). A seismic intensity of upper 5 was observed in the area of High-Temperature Engineering Test Reactor (HTTR) at the Oarai Research and Development Center of the JAEA during the 2011 Tohoku earthquake. In this paper, we report a parametric study of seismic response analyses of this earthquake using three-dimensional finite element models of the HTTR building with various uncertainty parameters (e.g. soil-structure interaction effects, soil properties). By examining the variation of the response result against the uncertainty parameters, we obtained a knowledge, which is essential for constructing a valid three-dimensional finite element model.

Journal Articles

The Investigation of the new multipurpose research reactor succeeding to JRR-3

Takino, Kazuo; Arai, Masaji; Murayama, Yoji

Proceedings of International Topical Meeting on Research Reactor Fuel Management and Meeting of the International Group on Reactor Research (RRFM/IGORR 2016) (Internet), p.667 - 676, 2016/03

Our working group has started to investigate basic concepts of the new research reactor which foresaw twenty years later. The aim of this project is to build up the design of new multipurpose research reactor which is constructed instead of JRR-3 for utilization of the neutron beam, irradiation, training and so on.

Journal Articles

Development of transportation container for the neutron startup source of High Temperature engineering Test Reactor (HTTR)

Shimazaki, Yosuke; Ono, Masato; Tochio, Daisuke; Takada, Shoji; Sawahata, Hiroaki; Kawamoto, Taiki; Hamamoto, Shimpei; Shinohara, Masanori

Proceedings of International Topical Meeting on Research Reactor Fuel Management and Meeting of the International Group on Reactor Research (RRFM/IGORR 2016) (Internet), p.1034 - 1042, 2016/03

In High Temperature Engineering Test Reactor (HTTR), three neutron holders containing $$^{252}$$Cf with 3.7 GBq for each are loaded in the graphite blocks and inserted into the reactor core as a neutron startup source which is changed at the interval of approximately ten years. These neutron holders containing the neutron sources are transported from the dealer's hot cell to HTTR using the transportation container. The holders loading to the graphite block are carried out in the fuel handling machine maintenance pit of HTTR. There were two technical issues for the safety handling work of the neutron holder. The one is the radiation exposure caused by significant movement of the container due to an earthquake, because the conventional transportation container was so large ($$phi$$1240 mm, h1855 mm) that it can not be fixed on the top floor of maintenance pit by bolts. The other is the falling of the neutron holder caused by the difficult remote handling work, because the neutron holder capsule was also so long ($$phi$$155 mm, h1285 mm) that it can not be pulled into the adequate working space in the maintenance pit. Therefore, a new and low cost transportation container, which can solve the issues, was developed. To avoid the neutron and $$gamma$$ ray exposure, smaller transportation container ($$phi$$820mm, h1150 mm) which can be fixed on the top floor of maintenance pit by bolts was developed. In addition, to avoid the falling of the neutron holder, smaller neutron holder capsule ($$phi$$75 mm, h135 mm) with simple handling mechanism which can be treated easily by manipulator was also developed. As the result of development, the neutron holder handling work was safely accomplished. Moreover, a cost reduction for manufacturing was also achieved by simplifying the mechanism of neutron holder capsule and downsizing.

JAEA Reports

Operation, test, research and development of the High Temperature Engineering Test Reactor (HTTR); FY2013

Department of HTTR

JAEA-Review 2014-041, 140 Pages, 2014/12

JAEA-Review-2014-041.pdf:14.06MB

The High Temperature Engineering Test Reactor (HTTR) constructed at the Oarai Research and Development Center of the Japan Atomic Energy Agency (JAEA) is the first high-temperature gas-cooled reactor (HTGR) in Japan which is a graphite-moderated and helium gas-cooled reactor with 30MW of thermal power. In fiscal year 2013, we started to prepare the reactor installation application for the HTTR to prove conformity with the new research reactor's safety regulatory requirements taken effect from December 2013. We had been making effort to run the HTTR which was stopped since the 2011 in which the Pacific coast of Tohoku Earthquake (2011.3.11) occurred. This report summarizes activities and results of HTTR operation, maintenance, and several R&Ds, which were carried out in the fiscal year 2013.

JAEA Reports

JRR-2 decommissioning activity, 2

Suzuki, Takeshi; Nakano, Masahiro; Okawa, Hiroshi; Terunuma, Akihiro; Kishimoto, Katsumi; Yano, Masaaki

JAERI-Tech 2005-018, 84 Pages, 2005/03

JAERI-Tech-2005-018.pdf:27.52MB

no abstracts in English

JAEA Reports

Management techniques of the JRR-4 heat exchanger

Horiguchi, Hironori; Oyama, Koji; Ishikuro, Yasuhiro; Hirane, Nobuhiko; Ito, Kazuhiro; Kameyama, Iwao

JAERI-Tech 2005-001, 38 Pages, 2005/02

JAERI-Tech-2005-001.pdf:2.79MB

After JRR-4 heat exchanger was renewed in made of stainless steel from carbon steel, it was examined how to manage the heat exchanger. The main subject is the cleaning technology of the heat exchanger. The recovery of old heat exchanger cooling performance has been by only chemical cleaning. Now we use chemical and dry cleaning as a new technique. It helps prevent of corrosions of secondary pipes and reduce of management costs. This report describes the performance management and cleaning technology of the JRR-4 heat exchanger and the management of the JRR-4 coolant.

Journal Articles

Present status of JRR-2 decommissioning

Nakano, Masahiro; Okawa, Hiroshi; Suzuki, Takeshi; Kishimoto, Katsumi; Terunuma, Akihiro; Yano, Masaaki

Dekomisshoningu Giho, (30), p.11 - 24, 2004/09

Japan Research Reactor No.2(JRR-2), heavy water moderated and cooled tank type research reactor with maximum thermal power of 10MW,was operated for over 36 years, and was permanently shut down in December, 1996. In 1997, decommissioning plan was submitted to the STA, and dismantling was begun. Decommissioning program of JRR-2 is divided into 4 phases. Phase 1, 2 had already been completely finished without any trouble. Furthermore, the phase 3 was also finished in February, 2004 as planned. On exposure of worker in phase 1, 2 and 3, it was achieved to control lower than the estimate. On exposure of worker in phase 1, 2 and 3, it was achieved to control lower than the estimate. Reactor will be removed in phase 4 by one piece removal technique. The reactor building is planned to use effectively as a hot experimental facilities after decommissioning. The decommissioning plan was changed that the reactor would be kept in safety storage.

Journal Articles

JAEA Reports

Selection of important nuclides from the viewpoint of safety assessment for disposal of radioactive waste arising from research institutes, 2; Analytical scheme for nuclide composition in radwastes arising from research and testing reactor and post-irradiation examination facilities

Asai, Shiho; Sakai, Akihiro; Yoshimori, Michiro; Kihara, Shinji

JAERI-Tech 2003-071, 46 Pages, 2003/08

JAERI-Tech-2003-071.pdf:4.31MB

As part of survey concerning radioactive inventory of radwastes arising from research institutes, an analytical scheme has been studied for verifying their nuclide composition based on calculation analysis and record, in consideration of the its characteristics. In this study, radwastes are used as samples, which arise from research and testing reactors and post-irradiation examination facilities (PIE facilities). Though separation procedures are simplified and rationalized, quantifiable values could be obtained with relative errors under 10% for almost all the samples containing nuclides like $$^{59}$$Ni and $$^{238}$$U which concentrations are low, and recoveries were high on the whole. These show that the analytical scheme is useful for chemical separation of radwastes arising from research and testing reactors and PIE facilities.

Journal Articles

Transportation of spent fuels from research reactor to USA

Koda, Nobuyuki; Kusunoki, Tsuyoshi; Watanabe, Masanori; Ojima, Masao*; Kondo, Makoto

UTNL-R-0426, p.5_1 - 5_9, 2003/03

no abstracts in English

Journal Articles

General description and operational experience of a dry storage facility for JRR-3 spent fuels in JAERI

Kusunoki, Tsuyoshi; Koda, Nobuyuki; Uchiyama, Junzo*

Dai-24-Kai Kaku Busshitsu Kanri Gakkai Nippon Shibu Nenji Taikai Rombunshu, p.149 - 156, 2003/00

A dry storage facility (DSF) was constructed in March 1982 to store the JRR-3 metallic natural uranium spent fuel elements those had been stayed under water in a core or a spent fuel pool for a long period (Maximum : about 20 years). The facility consists of a storage, an air circulation system, an auxiliary system and a control room. The storage is composed of the concrete shielding and 100 dry-wells. In each dry-well, a stainless steel made canister with the spent fuels is stored. The air circulation system has an air-inlet and outlet pipes, headers and air circulation blowers to circulate air in the system and maintain the pressure inside the dry-well below the atmosphere. This system also performs the role as radiation monitoring system. The facility is designed to satisfy safety requirements as a nuclear fuel facility, such as criticality safety, radiation shielding and earthquake performance. JAERI has successfully experienced the dry storage of 1798 spent fuel elements about for 20 years.

JAEA Reports

Data on HTTR irradiation test specimens; The First and second irradiation tests

Baba, Shinichi; Ishihara, Masahiro; Suzuki, Yoshio*; Takahashi, Tsuneo*; Hoshiya, Taiji

JAERI-Data/Code 2002-008, 126 Pages, 2002/03

JAERI-Data-Code-2002-008.pdf:4.82MB

no abstracts in English

JAEA Reports

Proceedings of the Seminar on the Utilization of Neutron Irradiation; March 9th 2000, Tokai

Department of JMTR, Oarai; Department of Research Reactor, Tokai; Department of Hot Laboratories, Tokai

JAERI-Conf 2001-018, 109 Pages, 2002/01

JAERI-Conf-2001-018.pdf:13.67MB

The “Seminar on the Utilization of Neutron Irradiation" was held on March 9th 2000 in Tokai establishment as a part of activities of the “Program Committee for Neutron Irradiation". The topics presented in the seminar included the recent irradiation studies on the materials for the light water reactors, development of fusion reactor materials and materials used under high temperature, application of neutron activation and recent activities in the post irradiation examinations. This report contains the shortpapers and the copies of the OHPs presented at the seminar.

Journal Articles

Treatment of malignant brain tumors using nuclear reactor

Matsumura, Akira*; Yamamoto, Tetsuya*; Shibata, Yasushi*; Nose, Tadao*; Yamamoto, Kazuyoshi; Kumada, Hiroaki; Torii, Yoshiya

Nippon Genshiryoku Gakkai-Shi, 43(10), p.957 - 963, 2001/10

 Times Cited Count:2 Percentile:77.82(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Reduction technique of welding defect in the welded joint of aluminum alloys base on GTAW

Maeda, Akio; Oba, Toshihiro; Kikuchi, Hiroyuki; Shibata, Katsuyuki

JAERI-Tech 2001-003, 48 Pages, 2001/02

JAERI-Tech-2001-003.pdf:5.95MB

no abstracts in English

104 (Records 1-20 displayed on this page)