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Yonomoto, Taisuke; Nakashima, Hiroshi*; Sono, Hiroki; Kishimoto, Katsumi; Izawa, Kazuhiko; Kinase, Masami; Osa, Akihiko; Ogawa, Kazuhiko; Horiguchi, Hironori; Inoi, Hiroyuki; et al.
JAEA-Review 2020-056, 51 Pages, 2021/03
JAEA-Review-2020-056.pdf:3.26MB
A group named as "The group for investigation of reasonable safety assurance based on graded approach", which consists of about 10 staffs from Sector of Nuclear Science Research, Safety and Nuclear Security Administration Department, departments for management of nuclear facility, Sector of Nuclear Safety Research and Emergency Preparedness, aims to realize effective graded approach (GA) about management of facilities and regulatory compliance of JAEA. The group started its activities in September, 2019 and has had discussions through 10 meetings and email communications. In the meetings, basic ideas of GA, status of compliance with new regulatory standards at each facility, new inspection system, etc were discussed, while individual investigation at each facility were shared among the members. This report is compiled with expectation that it will help promote rational and effective safety management based on GA by sharing contents of the activity widely inside and outside JAEA.
Kinase, Masami; Arai, Masaji; Maruo, Takeshi
Proceedings of Joint IGORR 2013 & IAEA Technical Meeting (Internet), 12 Pages, 2013/10
JRR-3 at the Tokai-Shirakata site of JAEA was in its regular maintenance period, when the Great East Japan Earthquake took place on 11th March 2011. The reactor building with the solid foundations and the equipment important to safety survived the earthquake without serious damage, and no radioactive leakage has been occurred. Recovery works, check and test to confirm the integrity of all components and structures, and seismic assessment necessary for proving that the seismic loads which worked on a structure or component by the earthquake accommodated within its allowable stress have been carried out. After our recovery works and verification of the integrity of JRR-3, we confirmed that the integrity is ensured, and then reported the fact to the regulatory body. As another topic, the regulatory body will introduce new regulatory requirements for research reactors. Now, JRR-3 considers applying the new requirements for restart. This paper presents the current status of JRR-3 including the recovery works, seismic assessment and new regulatory requirements.
Mo production in JRR-3Hirose, Akira; Komeda, Masao; Kinase, Masami; Sorita, Takami; Wada, Shigeru
JAEA-Technology 2010-007, 68 Pages, 2010/06
JAEA-Technology-2010-007.pdf:3.76MB
We investigated the production process of Mo, which is parent nuclide of 
Tc, in JRR-3. Tc is most commonly used as a radiopharmaceutical in the field of nuclear medicine. Currently the supplying of Mo is only dependent on imports from foreign countries, so JAEA is aiming at domestic production of a part of Mo in cooperation with the industrial arena. This report presents the technical study for the production process of Mo by using the neutron radiation method of (n,
) reaction in JRR-3.
Kishi, Toshiaki; Ichimura, Shigeju; Kinase, Masami; Wada, Shigeru
JAEA-Conf 2008-010, p.146 - 158, 2008/12
The Department of Research Reactor and Tandem Accelerator operates three research reactors, JRR-3, JRR-4 and NSRR. JRR-3 was operated for 180 days in Japanese Fiscal Year 2007. The neutron bender system was installed on the cold neutron guide tube. As a result, the cold beam intensity has increased by about 10 times. JRR-4 was operated for 93 days in Japanese Fiscal Year 2007. Boron neutron capture therapy was carried out 25 times. The trouble of reflector occurred in December 2007. At present, the reactor has stopped to replace the reflectors. NSRR has been built for the investigation of light water reactor fuel behavior during off-normal conditions such as reactivity-initiated accident. Recently the investigation is performed for the behavior of high burnup fuel and mixed oxide fuel. At present, the NSRR experiments with the new capsule are continuing for high burnup fuels of 59, 67 and 71 GWd/t.
Kato, Tomoaki; Araki, Masaaki; Izumo, Hironobu; Kinase, Masami; Torii, Yoshiya; Murayama, Yoji
JAEA-Technology 2007-050, 39 Pages, 2007/08
JAEA-Technology-2007-050.pdf:14.09MB
On the conversion from aluminide fuel to silicide fuel, burnable absorbers were introduced for decreasing excess reactivity. The burnable absorbers influence reactivity during reactor operation. So, the burning of the burnable absorbers was studied and the influence on reactor operation was made cleared. Furthermore, necessary excess reactivity on beginning of operation cycle and the time limit for restart after unplanned reactor shutdown was calculated. After the conversion, the fuel exchange procedure was changed from the six-batch dispersion procedure to the fuel burn-up management procedure. The previous estimation of fuel burn-up was required for the planning of fuel exchange, so that the estimation was carried out by means of past operation data. Finally, a new fuel exchange procedure was proposed for effective use of fuel elements. The average length of fuel-staying in the core can be increased by two percent on the procedure.
Izumo, Hironobu; Kato, Tomoaki; Kinase, Masami; Torii, Yoshiya; Murayama, Yoji
JAEA-Technology 2007-046, 23 Pages, 2007/07
JAEA-Technology-2007-046.pdf:4.54MB
JRR-3 (Japan Research Reactor No.3) has been operated for about 15 years after the modification, without significant troubles by carrying out maintenance such as the preventive maintenance (mainly Time-Based Maintenance: TBM) for the safety-grade equipments and the breakdown maintenance for the non-safety-grade equipments. Recently, numbers of unscheduled shutdowns caused by aging of the non-safety-grade equipment have been increasing, but resources for both maintenances have been decreasing year by year. In such a situation, new JRR-3 maintenance program is studying and reviewed considering safety, reliability and economical. In the evaluation, the maintenance data (i.e. vibration, measurement, etc.) which accumulated on JRR-3 is applied effectively. This report offers the policy on the maintenance review at JRR-3 and the future direction of JRR-3 maintenance programs.
Kinase, Masami; Sagawa, Hisashi; Nakagome, Yoshihiro*; Unesaki, Hironobu*
Proceedings of International Meeting on Reduced Enrichment for Research and Test Reactors 2006 (RERTR 2006) (Internet), 10 Pages, 2006/00
The reduced enrichment programs for the JRR-3M, JRR-4 and JMTR of Japan Atomic Energy Research Institute (JAERI) has been completed until 1999. The KUR of Kyoto University Research Reactor Institute (KURRI) has been partially completed and is still in progress under the Joint Study Program with Argonne National Laboratory (ANL). The JRR-3M using LEU silicide fuel elements has done a functional test by the Japanese Government in 2000, and the property of the reactor core was satisfied. JAERI established a "U-Mo fuel ad hoc committee" for feasibility study concerning future LEU fuel instead of the silicide fuel in 2001, and an installation of the U-Mo fuel was estimated from 2012, even the irradiation tests are carried out successfully. The U.S. Policy of Foreign Research Reactor Spent Nuclear Fuels is strongly expected to expand the policy until U-Mo fuel installed. The Japanese Government approved a cancellation of the KUHFR Project in February 1991, and in April 1994 the U.S. Government gave an approval to utilize HEU fuel in the KUR instead of the KUHFR. Therefore, the KUR will be operated with HEU fuel until March 2006, then the full core conversion with LEU fuel will be done. All KUR spent fuel elements will be sent to the U.S. by March 2008.
Izumo, Hironobu; Wada, Shigeru; Kinase, Masami; Torii, Yoshiya; Murayama, Yoji
no journal, ,
no abstracts in English
Nio, Daisuke; Ikekame, Yoshinori; Suwa, Masayuki; Isaka, Koji; Ouchi, Satoshi; Mineshima, Hiromi; Motohashi, Jun; Torii, Yoshiya; Kinase, Masami; Murayama, Yoji
no journal, ,
no abstracts in English
Izumo, Hironobu; Murayama, Yoji; Kinase, Masami; Torii, Yoshiya; Kato, Tomoaki
no journal, ,
no abstracts in English
Izumo, Hironobu; Kato, Tomoaki; Kinase, Masami; Torii, Yoshiya; Murayama, Yoji
no journal, ,
JRR-3(Japan Research Reactor No.3) has been operated for about 15 years after the modification, without significant troubles by carrying out maintenance such as the preventive maintenance (mainly Time-Based Maintenance: TBM) for the safety-grade equipments and the breakdown maintenance for the non-safety-grade equipments. Recently, numbers of out-of-schedule-shutdowns caused by aging of the non-safety-grade equipment have been increasing, but resources for both maintenances have been decreasing year by year. In such a situation, new JRR-3 maintenance program is studying and reviewed considering safety, reliability and economical. In the evaluation, the maintenance data (i.e. vibration, measurement, etc.) which accumulated on JRR-3 is applied effectively. In the conference, it is offered that the policy on the maintenance review at JRR-3 and the future direction of JRR-3 maintenance programs.
Hirose, Akira; Komeda, Masao; Kinase, Masami; Sorita, Takami; Sagawa, Hisashi; Wada, Shigeru
no journal, ,
no abstracts in English
Kinase, Masami
no journal, ,
In Japan, since the JRR-1 went critical in 1957, a lot of research reactors have been constructed and many of these reactors are currently in operation. Accordingly, it has become important to assure the future safety and reliability of the older reactors, which have a long period of operating experience. So, ageing management was introduced and carried out in Japan. In this workshop, I am going to talk about "Ageing management in JAEA". And I will use specific examples of JRR-3 and JRR-4, and try and touch on an overview of ageing regulation in Japan. This presentation may lead to help Asia's participants introduce ageing management.
