Irradiation test using foreign reactor, 1; Study of irradiation test with capsule temperature control system (Joint research)

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 300C, 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.

Simulator for materials testing reactors

Takemoto, Noriyuki; Sugaya, Naoto; Otsuka, Kaoru; Hanakawa, Hiroki; Onuma, Yuichi; Hosokawa, Jinsaku; Hori, Naohiko; Kaminaga, Masanori; Tamura, Kazuo*; Hotta, Koji*; et al.

JAEA-Technology 2013-013, 44 Pages, 2013/06

JAEA-Technology-2013-013.pdf:4.42MB

A real-time simulator for operating both a reactor and irradiation facilities of a materials testing reactor, Simulator of Materials Testing Reactors, was developed for understanding reactor behavior and upskilling in order to utilize for a nuclear human resource development and to promote partnership with developing countries which have a plan to introduce nuclear power plant. The simulator is designed based on the JMTR (Japan Materials Testing Reactor) and it simulates operation, irradiation tests and various kinds of anticipated operational transients and accident conditions caused by the reactor and irradiation facilities. The development of the simulator was sponsored by the Japanese government as one of the specialized projects of advanced research infrastructure in order to promote basic as well as applied researches. This report summarizes the simulation model, hardware specification and operation procedure of the simulator.

Design of advanced capsule temperature control system

Onuma, Yuichi; Inoue, Shuichi; Okada, Yuji; Sakuta, Yoshiyuki; Kanno, Masaru

JAEA-Technology 2011-016, 13 Pages, 2011/06

JAEA-Technology-2011-016.pdf:3.58MB

The Japan Material Testing Reactor (JMTR) in the Oarai Research and Development Center has been continued to improvement of the temperature control capability for irradiation specimens is being carried out for applying the JMTR. The JMTR had developed and been utilized the High accuracy capsule temperature control system had developed by adopting a feed forward control using measured reactor output power, and have been utilized in the JMTR. Based on the development knowledge, the advanced capsule temperature control system is now under development taking into consideration of additional function and so on so as to obtain high quality irradiation test data in the world in order to contribute the nuclear technology development.

Design study of the material irradiation facility for the SCC research under the LWR irradiation environment

Onuma, Yuichi; Tomita, Kenji; Okada, Yuji; Hanawa, Hiroshi

JAEA-Technology 2009-034, 79 Pages, 2009/07

JAEA-Technology-2009-034.pdf:11.23MB

Toward the re-operation of Japan Materials Testing Reactor on 2011 F.Y., the construction of new material irradiation facility for the stress corrosion cracking research under the LWR irradiation environment had been planed, and the design study of water control unit for BWR and water chemical study which supply the LWR simulated water to the material irradiation capsule were carried out on 2007 F.Y. The design study of new material irradiation facility was examined including the reflection of the operation experience and the reuse of components on old material irradiation facility. These examination results were summarized in this report.

Study on decommissioning of water loop irradiation facility and classification of waste

Onuma, Yuichi; Ishida, Takuya; Sakata, Ikuma*; Kodaira, Akira*; Sakai, Jun*; Oba, Seiichiro*; Kanno, Masaru; Saito, Takashi; Kinase, Muneyuki*; Ishitsuka, Etsuo

JAEA-Technology 2008-078, 39 Pages, 2008/12

JAEA-Technology-2008-078.pdf:13.42MB

Decommissioning of the water loop irradiation facility polluted by fission products and cruds was studied, and the reasonable waste classification occurring by the decommissioning was also studied. A out-pile equipment of the irradiation loop facility installed in JMTR is considered as a decommissioning object. Measurement of ambient dose rate in the out-pile facility and evaluation of the deposited radionuclide concentration in the cooling pipe were carried. In result, it was clear that the significant radionuclide is Co, and that occurred waste can classify as the shallow-ground trench disposal level, clearance level, non-radioactive waste. Furthermore, through the investigation of the cutting method for minimizing secondary waste generation, plumbing cutting machine with preventing scattering function was developed by trial manufactured cutter that surrounds the cutting pipe by box.

Detaching test on an irradiated mock-up contaminated with tritium from the core of JMTR

Tomita, Kenji; Tsuchiya, Kunihiko; Onuma, Yuichi; Inoue, Shuichi; Watanabe, Hiroyuki; Saito, Takashi; Kikuchi, Taiji; Hayashi, Kimio; Kitajima, Toshio

JAEA-Technology 2008-036, 61 Pages, 2008/06

JAEA-Technology-2008-036.pdf:7.47MB

The second in-situ irradiation experiment using a mock-up (ORIENT-II, JMTR capsule Number: 99M-54J) with a tritium breeder (LiTiO) pebble bed in the Japan Materials Testing Reactor (JMTR) was finished on Aug. 1, 2006. Consideration on the detaching procedure of the irradiated mock-up contaminated with tritium with pebble bed and a detaching test of this mock-up was carried out. The tritium removal properties were examined in the irradiated mock-up, the sweep gas tube, the protective tube and the junction box, for the decreasing of the tritium release to the area of detaching test. Melting/enclosed tests of sealing plug were also carried out for the prevention of tritium leakage from sweep gas lines of pebble bed. Then, the detaching test of the pebble bed was carried out. This report describes the results of tritium removal tests, examination of the detaching procedure, and the detaching test, as well as knowledge obtained from these tests and works.

Fabrication of irradiation capsule for IASCC irradiation tests, 1; Irradiation capsule for crack growth test (Joint research)

Ide, Hiroshi; Matsui, Yoshinori; Kawamata, Kazuo; Taguchi, Taketoshi; Kanazawa, Yoshiharu; Onuma, Yuichi; Watanabe, Hiroyuki; Inoue, Shuichi; Izumo, Hironobu; Ishida, Takuya; et al.

JAEA-Technology 2008-011, 46 Pages, 2008/03

JAEA-Technology-2008-011.pdf:19.39MB

It is known that Irradiation Assisted Stress Corrosion Cracking (IASCC) occurs when austenitic stainless steel components used for light water reactor (LWR) are irradiated for a long period. In order to evaluate the high aging of the nuclear power plant, the study of IASCC becomes the important problem. The specimens irradiated in the reactor were evaluated by post irradiation examination in the past study. For the appropriate evaluation of IASCC, It is necessary to test it under the simulated LWR conditions; temperature, water chemistry and irradiation conditions. In order to perform in-pile SCC test, saturated temperature capsule (SATCAP) was developed. There are crack growth test, crack propagation test and so on for in-pile SCC test. In this report, SATCAP for crack growth test is reported.

The Development of the advanced temperature control device for the irradiation capsule

Kitajima, Toshio; Abe, Shinichi; Takahashi, Kiyoshi; Onuma, Yuichi; Watanabe, Hiroyuki; Okada, Yuji; Oyake, Noriyuki*

UTNL-R-0404, p.6_1 - 6_9, 2001/00

no abstracts in English

Decommissioning study of water loop irradiation facility

Onuma, Yuichi; Ishida, Takuya; Saito, Takashi; Kanno, Masaru; Ito, Haruhiko*

no journal, , 

no abstracts in English