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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
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.
Takahashi, Kiyoshi; Hanawa, Hiroshi; Onuma, Yuichi; Hosokawa, Jinsaku; Kanno, Masaru
JAEA-Technology 2012-007, 31 Pages, 2012/03
The Japan Materials Testing Reactor (JMTR), achieving first criticality in March 1968, has been used in testing the durability and integrity of reactor fuels and components, basic nuclear research, the production of radioisotopes, and other purposes. The JMTR, however, stopped in August 2006 after its 165th operation cycle, and is currently under going partial renewal of reactor facilities and installation of new irradiation facilities, geared toward being restarted in 2012. Now, the installation of two new irradiation facilities under the LWR irradiation environment were finished until 2011FY. One is a power ramping test facility of high-burnup fuel. Another one is a material irradiation facility for IASCC research under the LWR irradiation environment. And another irradiation facility (Hydraulic rabbit irradiation facility) maintenance is carried out on 2011FY. This report is described the installed new irradiation facilities and established irradiation facility until 2011FY in JMTR.
Inaba, Yoshitomo; Iimura, Koichi; Hosokawa, Jinsaku; Izumo, Hironobu; Hori, Naohiko; Ishitsuka, Etsuo
IEEE Transactions on Nuclear Science, 58(3), p.1151 - 1158, 2011/06
Times Cited Count:6 Percentile:43.05(Engineering, Electrical & Electronic)The Japan Materials Testing Reactor (JMTR) is now under refurbishment, and the operation of the new JMTR will start in FY 2011. The new JMTR has a plan to produce Mo, which is the parent nuclide of
Tc, and two
Mo production technologies have been developed: one is a solid irradiation method, and the other is a solution irradiation method. In this paper, the present status of the development on the
Mo production technologies with the solid and solution irradiation methods was described. In the solid irradiation method, it was found that JMTR can provide about 20% of the
Mo imported into Japan. In the solution irradiation method, the fundamental characteristics of the aqueous molybdate solutions selected as candidates for the irradiation target were cleared by the
-ray irradiation test.
Hosokawa, Jinsaku; Iimura, Koichi; Ogawa, Mitsuhiro; Tomita, Kenji; Yamaura, Takayuki
JAEA-Technology 2010-018, 269 Pages, 2010/08
At Oarai Research and Development Center, Japan Atomic Energy Agency (JAEA) advances the plan of refurbishing Japan Materials Testing Reactor (JMTR) to start the operation in fiscal 2011. Fuel Transient Test Facility is scheduled to be set up as neutron irradiation test equipment of the light-water reactor fuel that uses JMTR after it operates again. The abnormal transition examination device is the irradiation facilities where the output sudden rise examination that makes the light-water reactor fuel an irradiation sample is done to use it to develop the safety evaluation technology and the damage influence evaluation technology of the light-water reactor fuel that reaches high burn-up. In this report, as for the system design, it is a summary to JMTR among detailed designs of the abnormal transition examination device of the installation schedule.
Ogawa, Mitsuhiro; Iimura, Koichi; Hosokawa, Jinsaku; Kanno, Masaru
JAEA-Technology 2010-019, 178 Pages, 2010/07
JMTR is making preparations of the irradiation examinations towards the re-operation from the 2011 fiscal year now. Design examination of the high-duty irradiation loop is in one of these irradiation examinations of the irradiation plan. The examination is the plan to carry out the irradiation examination of the light water reactor fuel (uranium fuel and mixed oxide fuel) which reached the high burnup, under the irradiation environment nearer to the light water reactor plant. In the 2009 fiscal year, we carried out (1) System design and (2) Earthquake-proof calculation of in-pile tube of the high-duty irradiation loop. And, for the fuel action between covering pipe and pellets of fuel rod which reached the high burnup, we carried out (3) System design of the lift-off test facility. Moreover, we carried out (4) Examination about detection system of fuel breakage when a fuel sample is damaged, and (5) Examination about system composition of effluent treatment system.
Kimura, Akihiro; Iimura, Koichi; Hosokawa, Jinsaku; Izumo, Hironobu; Hori, Naohiko; Nakagawa, Tetsuya; Kanno, Masaru; Ishihara, Masahiro; Kawamura, Hiroshi
JAEA-Review 2009-072, 18 Pages, 2010/03
JAEA has a plan to produce Mo, a parent nuclide of
Tc. At present, radioisotopes are indispensable for a diagnosis and treatment in the medical field. Demand of
Tc (half life 6h) used as a radiopharmaceutical increases up year by year. Moreover, the expansion of demand will be expected in future. However, the supply of
Mo in Japan depends fully on the import from foreign countries. Therefore, it is necessary to supply
Mo stably by the domestic production. There are two methods of
Mo (half life 65.9h) production; the one is the nuclear fission (n,fiss) method, and the other is the (n,
) method using the
Mo target.
Mo production in the JMTR with the (n,
) method was studied and evaluated. As a result, it was found that the partial amount of
Mo demand is possible to supply stably if a new hydraulic-rabbit-irradiation-facility (HR) is used.
Inaba, Yoshitomo; Iimura, Koichi; Hosokawa, Jinsaku; Izumo, Hironobu; Hori, Naohiko; Ishitsuka, Etsuo
Proceedings of 1st International Conference on Advancements in Nuclear Instrumentation, Measurement Methods and their Applications (ANIMMA 2009) (USB Flash Drive), 8 Pages, 2009/06
The Japan Materials Testing Reactor (JMTR) is now under refurbishment, and the operation of the new JMTR will be started in FY 2011. The new JMTR has a plan to produce Mo, which is the parent nuclide of
Tc, and two
Mo production technologies have been developed; the one is a solid irradiation method, and the other is a solution irradiation method.
Mo production in the JMTR will be started by the solid irradiation method, and it was found that the JMTR can produce about 20% of the demand for
Mo in Japan. In the solution irradiation method, the fundamental characteristics of the aqueous molybdate solutions selected as the candidates for the irradiation target were cleared.
Iimura, Koichi; Hosokawa, Jinsaku; Izumo, Hironobu; Hori, Naohiko; Nakagawa, Tetsuya; Kanno, Masaru; Kawamura, Hiroshi
JAEA-Conf 2008-010, p.251 - 258, 2008/12
At Oarai Research and Development Center, Japan Atomic Energy Agency (JAEA) being advanced is the plan of refurbishing Japan Materials Testing Reactor (JMTR) to start the operation in FY 2011. As one of effective use of the JMTR, JAEA has a plan to product Mo, a parent nuclide of
Tc.
Tc is most commonly used as a radiopharmaceutical in the field of nuclear medicine. Currently the supplying of
Mo depends only on imports from foreign countries, therefore JAEA is aiming at domestic production of a part of
Mo in cooperation with industrial users. As JAEA's activities, mentioned are the process, the selection and fabric of the irradiation facilities for
Mo production, the technical study of commercializing equipment after irradiation, and the cost evaluation for
Mo production.
Tomita, Kenji; Hosokawa, Jinsaku; Matsui, Yoshinori
JAEA-Technology 2008-043, 21 Pages, 2008/07
In JMTR, highly precise-ization of irradiation temperature evaluation of material capsule is advanced towards re-operation in the 2011 fiscal year. In the conventional sub-program, rectangular form was loaded into the capsule and temperature evaluation was carried out. In this development, the CT specimen which is special form is loaded into capsule, and it enabled it to analyze a temperature distribution. Moreover, the sub-program which can also evaluate the heat stress distribution by this uneven temperature distribution was developed. And, in order to be able to perform easily extraction and re-load of irradiation specimens, the structure of separation specimen holder effective in a re-irradiation examination is adopted. However, with this structure, the inside of capsule serves as uneven temperature distribution. For this reason, the sub-program which can evaluate this temperature distribution was developed.
Hosokawa, Jinsaku; Kanno, Masaru; Sakamoto, Taichi
JAEA-Technology 2008-038, 24 Pages, 2008/06
At Oarai Research and Development Center, Japan Atomic Energy Agency (JAEA) advances the plan of refurbishing Japan Materials Testing Reactor (JMTR) to start the operation in fiscal 2011. Silicon Semiconductor is used in every Country and every industrial field. Nowadays, the demand of large diameter Silicon Semiconductors are increasing. At JMTR in JAEA Oarai, the production of Silicon Semiconductors utilizing NTD (Neutron Transmutation Doping) Method is investigated. Particularly, this report describes the installation of Silicon Semiconductors producing facility on JMTR. This Report described the Conceptual Study for Silicon Semiconductor Irradiation Facility in JMTR.
Iimura, Koichi; Hosokawa, Jinsaku; Kanno, Masaru; Kitajima, Toshio; Nakagawa, Tetsuya; Sakamoto, Taichi; Hori, Naohiko; Kawamura, Hiroshi
JAEA-Technology 2008-035, 47 Pages, 2008/06
At Oarai Research and Development Center, Japan Atomic Energy Agency (JAEA) advances the plan of refurbishing Japan Materials Testing Reactor (JMTR) to start the operation in fiscal 2011. As part of effective use for JMTR, JAEA is planning to product Mo, which is a parent nuclide of
Tc.
Tc is most commonly used as a radiopharmaceutical in the field of nuclear medicine. Currently the supplying of
Mo is only depend on imports from foreign countries, so JAEA is aiming at domestic production of a part of
Mo in cooperation with the industrial circles. In this article, JAEA described the process, the choice and fabric of the irradiation facilities for
Mo production, the technical study of commercializing equipment after irradiation, and the cost study for
Mo production.
Hosokawa, Jinsaku; Izumo, Hironobu; Ishitsuka, Etsuo
JAEA-Review 2008-028, 39 Pages, 2008/06
For the purpose of advanced technology developments on new irradiation facilities installed in the JMTR, the Mo production facility for medical RI, silicon semiconductor production facility, pneumatic irradiation facilities, RI handling facilities in the OPAL were investigated. In this paper, basic structure and the safety design concepts for these irradiation facilities are reported.
Matsui, Yoshinori; Hanawa, Satoshi; Ide, Hiroshi; Tobita, Masahiro*; Hosokawa, Jinsaku; Onuma, Yuichi; Kawamata, Kazuo; Kanazawa, Yoshiharu; Iwamatsu, Shigemi; Saito, Junichi; et al.
JAEA-Conf 2006-003, p.105 - 114, 2006/05
Irradiation assisted stress corrosion cracking (IASCC) caused by the simultaneous effects of radiation, stress and high temperature water environment is considered to be one of the critical concerns of in-core structural materials not only for light water reactors (LWRs) but also for water-cooled fusion reactors. In the research field of IASCC, post-irradiation examinations (PIEs) for irradiated materials have been mainly carried out, because there are many difficulties on SCC tests under neutron irradiation environment. Hence we have embarked on a development of the test techniques for performing the in-pile SCC tests. In this paper, we describe the developed several in-pile test techniques and the current status of in-pile SCC tests at Japan Materials Testing Reactor (JMTR).
Nagata, Hiroshi; Yamaura, Takayuki; Hosokawa, Jinsaku; Matsui, Yoshinori; Kanno, Masaru
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no abstracts in English
Ogawa, Mitsuhiro; Hosokawa, Jinsaku; Tomita, Kenji; Iimura, Koichi; Sakuta, Yoshiyuki
no journal, ,
no abstracts in English