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Takabe, Yugo; Otsuka, Noriaki; Fuyushima, Takumi; Sayato, Natsuki; Inoue, Shuichi; Morita, Hisashi; Jaroszewicz, J.*; Migdal, M.*; Onuma, Yuichi; Tobita, Masahiro*; et al.
JAEA-Technology 2022-040, 45 Pages, 2023/03
JAEA-Technology-2022-040.pdf:6.61MB
Because of the decommission of the Japan Materials Testing Reactor (JMTR), the domestic neutron irradiation facility, which had played a central role in the development of innovative nuclear reactors and the development of technologies to further improve the safety, reliability, and efficiency of light water reactors, was lost. Therefore, it has become difficult to pass on the operation techniques of the irradiation test reactors and irradiation technologies, and to train human resources. In order to cope with these issues, we conducted a study on the implementation of irradiation tests using overseas reactors as neutron irradiation sites as an alternative method. Based on the "Arrangement between the National Centre for Nuclear Research and the Japan Atomic Energy Agency for Cooperation in Research and Development on Testing Reactor," the feasibility of conducting an irradiation test at the MARIA reactor (30 MW) owned by the National Centre for Nuclear Research (NCBJ) using the temperature control system, which is one of the JMTR irradiation technologies, was examined. As a result, it was found that the irradiation test was possible by modifying the ready-made capsule manufactured in accordance with the design and manufacturing standards of the JMTR. After the modification, a penetration test, an insulation continuity test, and an operation test in the range of room temperature to 300
C, which is the operating temperature of the capsule, were conducted and favorable results were obtained. We have completed the preparations prior to transport to the MARIA reactor.
Asano, Norikazu; Nishimura, Arashi; Takabe, Yugo; Araki, Daisuke; Yanai, Tomohiro; Ebisawa, Hiroyuki; Ogasawara, Yasushi; Oto, Tsutomu; Otsuka, Kaoru; Otsuka, Noriaki; et al.
JAEA-Technology 2021-045, 137 Pages, 2022/06
JAEA-Technology-2021-045.pdf:2.97MB
A collapse event of a cooling tower for secondary cooling system in the Japan Materials Testing Reactor (JMTR) was caused by the strong winds of Typhoon No.15 on September 9, 2019. As measures against the event, the working group for the renewal of the UCL (Utility Cooling Loop) cooling tower was established in the department of JMTR, and the integrity of the UCL cooling tower, which is the same type of wooden cooling tower as the secondary cooling tower in the JMTR, was investigated. As a result of this investigation, we have decided to replace the existing UCL cooling tower with a new cooling system. After investigations, in order to reduce the risk of collapse due to wood decay, the new cooling system was installed as a component of the air system to be managed as a performance maintenance facility after decommissioning. This report describes the design of and the evaluation results of the facility.
Omori, Takazumi; Otsuka, Kaoru; Endo, Yasuichi; Takeuchi, Tomoaki; Ide, Hiroshi
JAEA-Review 2021-015, 57 Pages, 2021/11
JAEA-Review-2021-015.pdf:6.3MB
The JMTR reactor facility was selected as a decommissioning one in the Medium/Long-Term Management Plan of JAEA Facilities formulated on April 1, 2017. Therefore, the decommissioning plan was submitted to Nuclear Regulation Authority on September 18, 2019, and the approval was obtained on March 17, 2021 after two amendments. Currently, preparations for decommissioning are underway. The JMTR reactor facility has been aged for more than 50 years since the first criticality in March 1968. However, some of the water piping systems has not been updated since its construction, and there is a possibility of pipe wall thinning due to corrosion, etc. Therefore, the integrity of the water piping was investigated for the facilities that circulate cooling water and pump radioactive liquid waste. In this investigation, the main circulation system of the reactor primary cooling system, the pool canal circulation system, the CF pool circulation system, the drainage system of the liquid waste disposal system, and the hydraulic rabbit irradiation system of the main experimental facility were measured for the pipe wall thickness using the Ultrasonic Thickness Measurement (UTM) method. These values satisfied the technical standards for research and test reactor facilities. No loss of integrity is expected to occur during the upcoming decommissioning period. In the future, we will periodically confirm that there is no wall thinning in the piping of the cooling water circulation and the water transmission system during the decommissioning period by using this result as basic data.
Takeuchi, Tomoaki; Otsuka, Noriaki; Shibata, Hiroshi; Nagata, Hiroshi; Endo, Yasuichi; Matsui, Yoshinori; Tsuchiya, Kunihiko
KAERI/GP-418/2015, p.110 - 112, 2015/00
irradiation experiments with a 
Co source were carried out for developing Self-Powered Gamma Detectors (SPGDs) with lead (Pb) emitter and Self-Powered Neutron Detectors (SPNDs) with Pt-40%Rh emitter prior to in-core irradiation experiments. The results showed the output currents of the SPGDs were proportional to the dose rate in the range from about 200-6000 Gy/h with about 10% accuracy. In the case of SPNDs, the output currents flowed in inverse direction and were an order of magnitude lower compared with that of the SPGDs. These different behaviors of the output currents are considered to be caused by the difference in the emitter sizes and the current component originated at the MI cables.
Kitagishi, Shigeru; Endo, Yasuichi; Okada, Yuji; Hanawa, Hiroshi; Matsui, Yoshinori
UTNL-R-0486, p.7_1 - 7_10, 2014/03
no abstracts in English
Tsuchiya, Kunihiko; Ito, Masayasu; Kitagishi, Shigeru; Endo, Yasuichi; Saito, Takashi; Hanawa, Yoshio; Dorn, C. K.*
JAEA-Conf 2012-002, p.111 - 114, 2012/12
no abstracts in English
Kitagishi, Shigeru; Saito, Takashi; Kikuchi, Taiji; Endo, Yasuichi; Tsuchiya, Kunihiko
Nihon Kikai Gakkai Rombunshu, A, 78(788), p.564 - 570, 2012/04
The development of the friction welded joint between Zircaloy-2 (Zry-2) and Type 316L stainless steel (SUS316L) has been carried out for the fabrication of fuel irradiation capsules in Japan Materials Testing Reactor (JMTR). The welding condition was determined from the fabrication test results of total loss and tensile strength. The joint interface was characterized by metallographic observation, elemental analysis and micro-hardness test. It was found that heat-affected zones at the joint interface were different between the center and outside positions. The tensile strength of the joint was equal to that of base Zry-2 metals at 300C. And, the joint performance was good from the results of helium leak test and hydraulic pressure burst test. From the results of these tests, it was obvious that the Zry-2/SUS316L friction welded joints were promised to use for the structural material of irradiation capsules for fuel irradiation tests.
Mo production in JMTRTakita, Kenji; Iimura, Koichi; Tomita, Kenji; Endo, Yasuichi; Kanno, Masaru
JAEA-Technology 2012-006, 41 Pages, 2012/03
JAEA-Technology-2012-006.pdf:6.8MB
At JAEA Oarai Research and Developnment Establishment (JAEA Oarai), JAEA Oarai was proceeding a plan to repair JMTR, which is to re-operate in fiscal 2012. Additionally, as an effective utilizati of JMTR, JAEA Oarai is planning to manufacture Mo, which is a parent nuclide of Tc. 
Tc is most commonly used as a radiopharmaceution in the field of nuclear medicine. Currently Mo supply is dependent only on foreign imports, so JAEA is aiming for working on partially manufacturing Mo domestically with industrial circles in Japan. In this article, this report described the choice and fabric of irradiathion facility named Hydraulic Rabbit Facility for manufacturing Mo, the technical study of fabrication technique.
Takita, Kenji; Iimura, Koichi; Tomita, Kenji; Endo, Yasuichi; Kanno, Masaru
UTNL-R-0480, p.7_4_1 - 7_4_6, 2012/03
no abstracts in English
Ide, Hiroshi; Tobita, Kenji; Endo, Yasuichi; Hori, Naohiko
JAEA-Review 2010-043, 80 Pages, 2010/10
JAEA-Review-2010-043.pdf:34.97MB
"Regulations Concerning the Installment, Operation, etc. of Research Reactors" was revised in February 2004. Based on the regulations, the reactor owner must perform the technical evaluation on aging if reactor operation is over 30 years. Moreover, based on the evaluation, the reactor owner must make the 10 years maintenance program concerning the action to maintain the reactor facility. Result of the technical evaluation on aging and the maintenance plan of JMTR reactor facility were reported to the MEXT in March 2005. In response to the report, the advisor meeting was held by the MEXT to evaluate the result of technical evaluation on aging and the maintenance plan. Corresponding to the meeting, we reviewed the technical evaluation result on aging and the maintenance program of JMTR reactor facility. This report summarized the review on the technical evaluation of aging of JMTR reactor facility and so on corresponding to the advisor meeting.
; Endo, Yasuichi; Yamaura, Takayuki; Matsui, Yoshinori; Niimi, Motoji; Hoshiya, Taiji; Kobiyama, M.*; Motohashi, Yoshinobu*
JAERI-Conf 99-006, p.343 - 348, 1999/08
no abstracts in English
; Endo, Yasuichi; Yamaura, Takayuki; Hoshiya, Taiji; Niimi, Motoji; Saito, Junichi; ; Ooka, Norikazu; Kobiyama, M.*
Journal of Nuclear Materials, 258-263, p.2041 - 2045, 1998/00
Times Cited Count：6 Percentile：48.76(Materials Science, Multidisciplinary)no abstracts in English
; Endo, Yasuichi; Yamaura, Takayuki; Niimi, Motoji; Hoshiya, Taiji; Saito, Junichi; ; Ooka, Norikazu;
JAERI-Research 97-028, 46 Pages, 1997/03
JAERI-Research-97-028.pdf:2.49MB
no abstracts in English
Nakamura, Jinichi; Endo, Yasuichi; ; ; Furuta, Teruo
JAERI-Research 95-083, 38 Pages, 1995/11
JAERI-Research-95-083.pdf:1.42MB
no abstracts in English
pellets and thermocouple re-instrumentation to fuel rod; Saito, Junichi; ; Endo, Yasuichi; ; Nakagawa, Tetsuya; ; Kawamata, Kazuo; ; Kawamura, Hiroshi; et al.
JAERI-Tech 95-037, 87 Pages, 1995/07
no abstracts in English
Matsumoto, Mikio; Endo, Yasuichi; ; Itabashi, Yukio; ; Yokouchi, Iichiro; Ando, Hiroei
JAERI-M 92-212, 62 Pages, 1993/01
no abstracts in English
Sawa, Kazuhiro; ; ; Endo, Yasuichi; Shiozawa, Shusaku;
JAERI-M 91-207, 34 Pages, 1991/12
no abstracts in English
; Endo, Yasuichi; Hoshiya, Taiji; Niimi, Motoji; Harayama, Yasuo
JAERI-M 90-214, 57 Pages, 1990/11
no abstracts in English
; Endo, Yasuichi; ;
UTNL-R-0247, 6 Pages, 1990/00
no abstracts in English
Mitsui, Kento; Ushijima, Hiroki; Ogasawara, Reira; Okada, Yuji; Suzuki, Makoto; Kimura, Kazuya; Ouchi, Satoshi; Nio, Daisuke; Ishijima, Yasuhiro; Endo, Yasuichi; et al.
no journal, ,
no abstracts in English
