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pellets for Mo-99 production, 3Ishida, Takuya; Suzuki, Yoshitaka; Nishikata, Kaori; Yonekawa, Minoru; Kato, Yoshiaki; Shibata, Akira; Kimura, Akihiro; Matsui, Yoshinori; Tsuchiya, Kunihiko; Sano, Tadafumi*; et al.
KURRI Progress Report 2015, P. 64, 2016/08
no abstracts in English
Yonekawa, Minoru; Iwasaki, Maho; Shimada, Kozue; Yanagiya, Shoko; Tsukada, Manabu; Iizuka, Yoshiyuki; Kaneko, Munenori; Unno, Toshimichi
JAEA-Testing 2015-002, 151 Pages, 2016/03
JAEA-Testing-2015-002.pdf:4.29MB
JAEA-Testing-2015-002-appendix(CD-ROM).zip:5.7MB
Preparatory Office for Hot Laboratory Operation Management in Fukushima Research Infrastructural Creation Center has advanced research and development for decommissioning of TEPCO'S Fukushima Daiichi Nuclear Power Station. For this purpose, work procedure manual of chemical analysis for safety evaluation on processing, disposal and management of radioactive waste such as low dose level rubbles and fuel debris has been prepared. The manual will be used for personnel training and animation function of PowerPoint was used as the beginner of the chemical analysis to understand easily. This report describes about nuclides which were established analysis method and completed to make animation of work procedure.
pellets for Mo-99 production, 2Nishikata, Kaori; Ishida, Takuya; Yonekawa, Minoru; Kato, Yoshiaki; Kurosawa, Makoto; Kimura, Akihiro; Matsui, Yoshinori; Tsuchiya, Kunihiko; Sano, Tadafumi*; Fujihara, Yasuyuki*; et al.
KURRI Progress Report 2014, P. 109, 2015/07
As one of effective applications of the Japan Materials Testing Reactor (JMTR), JAEA has a plan to produce 
Mo by (n,
) method ((n,)Mo production), a parent nuclide of 
Tc. In this study, preliminary irradiation test was carried out with the high-density molybdenum trioxide (MoO) pellets in the hydraulic conveyer (HYD) of the Kyoto University Research Reactor (KUR) and the Tc solution extracted from Mo was evaluated. After the irradiation test of the high-density MoO pellets in the KUR, Tc was extracted from the Mo solution and the recovery rate of Tc achieved the target values. The Tc solution also got the value that satisfied the standard value for Tc radiopharmaceutical products by the solvent extraction method.
Shibata, Akira; Kato, Yoshiaki; Oishi, Makoto; Taguchi, Taketoshi; Ito, Masayasu; Yonekawa, Minoru; Kawamata, Kazuo
KAERI/GP-418/2015, p.151 - 165, 2015/05
The JMTR stopped its operation in 2006 for refurbishment. The reactor facilities have been refurbished from 2007. After refurbishment, JMTR Hot laboratory is expected to perform various post irradiation examinations. In this report, installations of experimental apparatuses and recent experimental method are introduced. (1) A nano-indenter with radius spherical indenter. Inverse analysis using FEM could presume material constants from load-depth curve of indentation. Mechanical properties of oxide layer of zirconium alloy and irradiated stainless steel will be analyzed. (2) Transmission Electron Microscope (TEM). TEM is capable of imaging at a significantly higher resolution than light microscopes or normal SEM. JAEA installed a TEM apparatus (JEOL JEM-2800) in JMTR Hot laboratory. The maximum magnification is 150,000,000 times. It can be operated from a remote location using a computer network. This contributes to the convenience of remote researchers and reducing the amount of exposure.
pellets for Mo-99 productionNishikata, Kaori; Ishida, Takuya; Yonekawa, Minoru; Kato, Yoshiaki; Kurosawa, Makoto; Kimura, Akihiro; Matsui, Yoshinori; Tsuchiya, Kunihiko; Sano, Tadafumi*; Fujihara, Yasuyuki*; et al.
KURRI Progress Report 2013, P. 242, 2014/10
As one of effective applications of the Japan Materials Testing Reactor (JMTR), JAEA has a plan to produce Mo-99 (Mo) by (n,) method ((n,)Mo production), a parent nuclide of Tc. In this study, preliminary irradiation tests were carried out with the high-density MoO pellets in the KUR and the Mo production amount was evaluated between the calculation results and measurement results.
Kurosawa, Makoto; Kato, Yoshiaki; Yonekawa, Minoru; Taguchi, Taketoshi
UTNL-R-0486, p.9_1 - 9_11, 2014/03
It has been irradiated in the concrete cell, the microscope lead cell, the lead cell for materials examinations and the iron cell and, in the JMTR Hot Laboratory Facilities, examines it after the irradiation such as fuel and nuclear reactor structure materials. I install a monitoring board for a concrete cell, a microscope lead cell, a lead cell for materials examinations and iron cells in the control room I watch concentration such as the minus number pressure in these each cell, the air absorption dose rate in the cell, the cover door opening and shutting indication and to control it. As for these monitoring boards, about 30 through 40 or more passed after an in-service start, and high aging decided to update it in consideration of the driving of approximately 20 years after JMTR re-operation because trouble by becoming it and outbreak of the malfunction were concerned about.
MoTaguchi, Taketoshi; Yonekawa, Minoru; Kato, Yoshiaki; Kurosawa, Makoto; Nishikata, Kaori; Ishida, Takuya; Kawamata, Kazuo
UTNL-R-0483, p.10_5_1 - 10_5_13, 2013/03
JMTR focus on the activation method. By carrying out the preliminary tests using irradiation facilities existing, and verification tests using the irradiation facility that has developed in the cutting-edge research and development strategic strengthening business, as irradiation tests towards the production of Mo, we have been conducting research and development that can contribute to supply about 25% for Mo demand in Japan and the stable supply of radiopharmaceutical. This report describes a summary of the status of the preliminary tests for the production of Mo: Maintenance of test equipment in the facility in JMTR Hot Laboratory in preparation for research and development for the production of Mo in JMTR and using MoO pellet irradiated at Kyoto University Research Reactor Institute (KUR).
Ito, Masayasu; Kawamata, Kazuo; Tayama, Yoshinobu; Kanazawa, Yoshiharu; Yonekawa, Minoru; Nakagawa, Tetsuya; Omi, Masao; Iwamatsu, Shigemi
JAEA-Technology 2011-022, 44 Pages, 2011/07
JAEA-Technology-2011-022.pdf:3.29MB
Hot laboratory are facilities that execute the post irradiation examination of sample irradiated in material testing reactors etc. The handling of high burn-up fuel is scheduled in the JMTR (Japan Materials Testing Reactor) Hot Laboratory with JMTR re-operate in FY 2011. This report describes evaluation, production and installation of shielding of the hot cells in the JMTR Hot Laboratory.
Yonekawa, Minoru; Kato, Yoshiaki; Taguchi, Taketoshi; Sozawa, Shizuo
JAEA-Technology 2011-014, 16 Pages, 2011/06
JAEA-Technology-2011-014.pdf:3.6MB
The Japan Materials Testing Reactor (JMTR) is proceeding with the preparation for re-operation on 2011. The facilities and equipments in the hot laboratory had been improved from 2007 in order to deal with new requests for post irradiation examinations after re-operation of JMTR. Improvement of concrete cells and irradiation facilities are planned to be completed until the end of FY 2010 in order to carry out the post irradiated examination for research on high burnup fuel (maximum burn up: 110 GWd/t). In this report, improvement of concrete cells and irradiation facilities to handle the high burnup fuel in the hot laboratory is summarized.
Yonekawa, Minoru; Sozawa, Shizuo; Kato, Yoshiaki; Shibata, Akira; Nakagawa, Tetsuya; Kusunoki, Tsuyoshi
JAEA-Review 2010-049, 18 Pages, 2010/11
JAEA-Review-2010-049.pdf:2.09MB
The hot laboratory (JMTR-HL) was founded to examine the objects mainly irradiated in the JMTR (Japan Materials Testing Reactor), and has been operated since 1971. The JMTR has been stopped from FY2006 for the refurbishment and will be re-started from FY2011. The post irradiation examination for high burn up fuels and large specimen will be carried out in the restarted JMTR. The JMTR-HL plans to put a three dimensional X-ray Computerized Tomography (CT) inspection system in place until the restart of JMTR in order to satisfy the requirement of valuable irradiation data for safety and plant life time management of nuclear power plants in the future. The three dimensional X-ray CT inspection system is able to observe a defect geometry closely and visually compared with a two dimensional system. In this paper, system design, production, installation and performance tests of an X-ray CT inspection system in a hot cell are reported. The X-ray CT inspection system consists of a computed tomography scanner, an X-ray source, a movable sample positioned, an X-ray detector, a collimator, and so on. After installation of apparatus, performance tests using irradiated fuel rods and radioisotopes were carried out to confirm the influence of rays and transmission X-ray property. By this development of the X-ray CT inspection system, it became possible to provide data with high technical value for post irradiation examination of high burn-up fuels and large type specimens.
Matsui, Yoshinori; Takahashi, Hiroyuki; Yamamoto, Masaya; Nakata, Masahito; Yoshitake, Tsunemitsu; Abe, Kazuyuki; Yoshikawa, Katsunori; Iwamatsu, Shigemi; Ishikawa, Kazuyoshi; Kikuchi, Taiji; et al.
JAEA-Technology 2009-072, 144 Pages, 2010/03
JAEA-Technology-2009-072.pdf:45.01MB
"R&D Project on Irradiation Damage Management Technology for Structural Materials of Long-life Nuclear Plant" was carried out from FY2006 in a fund of a trust enterprise of the Ministry of Education, Culture, Sports, Science and Technology. The coupled irradiations or single irradiation by JOYO fast reactor and JRR-3 thermal reactor were performed for about two years. The irradiation specimens are very important materials to establish of "Evaluation of Irradiation Damage Indicator" in this research. For the acquisition of the examination specimens irradiated by the JOYO and JRR-3, we summarized about the overall plan, the work process and the results for the study to utilize these reactors and some facilities of hot laboratory (WASTEF, JMTR-HL, MMF and FMF) of the Oarai Research-and-Development Center and the Nuclear Science Research Institute in the Japan Atomic Energy Agency.
Sozawa, Shizuo; Nakagawa, Tetsuya; Iwamatsu, Shigemi; Hayashi, Koji; Tayama, Yoshinobu; Kawamata, Kazuo; Yonekawa, Minoru; Taguchi, Taketoshi; Kanazawa, Yoshiharu; Omi, Masao
JAEA-Technology 2009-070, 27 Pages, 2010/03
JAEA-Technology-2009-070.pdf:7.46MB
Refurbishment of the Japan Materials Testing Reactor (JMTR), which is recognized as one of important facilities in Japan for safety research, is in progress by the JAEA. In Extensive safety research of light-water reactor (LWR) fuels and materials under a contract with the Nuclear and Industrial Safety Agency of Ministry of Economy, Trade and Industry of Japan, the irradiation tests are planned in order to examine integrity of the LWR fuels and structure materials. For the irradiation tests of high burnup fuels and irradiated materials in the JMTR, modification of the hot laboratory facilities are needed, which are (1) making of application books for strengthening JMTR hot-lab. cell-shielding, (2) the capsule assembling device of detailed design, (3) safety analysis for domestic transportation cask and (4) confirmatory testing of diamond drill of fuel-rod center-hole processing device.
Yonekawa, Minoru; Sozawa, Shizuo; Omi, Masao; Nakagawa, Tetsuya
UTNL-R-0471, p.5_6_1 - 5_6_7, 2009/03
no abstracts in English
Miwa, Yukio; Kaji, Yoshiyuki; Tsukada, Takashi; Yamamoto, Toshio; Kato, Yoshiaki; Yonekawa, Minoru; Matsui, Yoshinori
Proceedings of 15th International Conference on Nuclear Engineering (ICONE-15) (CD-ROM), 6 Pages, 2007/04
Radiation-induced stress relaxation (RISR) test under uniaxial loading condition for tensile type specimens was carried out for type 316L stainless steel (SS). The specimens were irradiated in the Japan Materials Testing Reactor at 561 K to three dose levels (0.1-3 dpa) under four displacement constrained condition (prestrain range; 0.06-0.75%) in order to apply residual stress. Radiation hardening behavior and IASCC susceptibility of the RISR-tested 316L SS were examined by slow strain rate testing (SSRT) in oxygenated high temperature water. It was concluded from the SSRT results that the RISR had little influence on the radiation hardening behavior and IASCC susceptibility in the 316L SS. In all specimens, the residual stress rapidly decreased with increasing dose, and the residual stress level after irradiation was much lower than the stress level to initiate IASCC.
Kurihara, Kenichi; Yonekawa, Izuru; Kawamata, Yoichi; Sueoka, Michiharu; Hosoyama, Hiroki*; Sakata, Shinya; Oshima, Takayuki; Sato, Minoru; Kiyono, Kimihiro; Ozeki, Takahisa
Fusion Engineering and Design, 81(15-17), p.1729 - 1734, 2006/07
Times Cited Count：13 Percentile：64.72(Nuclear Science & Technology)A large tokamak fusion device JT-60 is expected to explore more advanced tokamak discharge scenario towards the ITER and a future power reactor. We believe the following experimental issues are expected to be solved in JT-60. To clarify how to keep a steady-state plasma with high performance, and how to avoid plasma instabilities almost completely. By stimulus of this motivation, several essential development and modifications of plasma control and data acquisition systems have been performed in JT-60. In this report, we discuss the developments to improve the JT-60 plasma control and data acquisition systems. In addition, a future plasma control and data acquisition systems leading to a standard design for a power reactor is envisaged on the basis of the 20-year plasma operation experiences.
Miwa, Yukio; Jitsukawa, Shiro; Yonekawa, Minoru
Journal of Nuclear Materials, 329-333(Part2), p.1098 - 1102, 2004/08
Times Cited Count：12 Percentile：60.66(Materials Science, Multidisciplinary)Fatigue properties were examined on a reduced activation ferritic/martensitic steel, and preliminary results were presented. F82H steel was irradiated at 523 K to 3.8 dpa, and then fatigue-tested at 298-573 K in vacuum with total strain range of 0.4-1.0%. Effect of irradiation on fatigue lives was observed on test at 298 K with total strain range of 0.4%. The fatigue life of irradiated specimen was reduced to about 1/7 of unirradiated specimen. The reduction of the fatigue life was attributed to the occurrence of channel fracture. Effect of test temperature was discussed.
Kaji, Yoshiyuki; Miwa, Yukio; Tsukada, Takashi; Kikuchi, Masahiko; Kita, Satoshi; Yonekawa, Minoru; Nakano, Junichi; Tsuji, Hirokazu; Nakajima, Hajime
Journal of Nuclear Materials, 307-311(Part1), p.331 - 334, 2002/12
Times Cited Count：5 Percentile：33.92(Materials Science, Multidisciplinary)Irradiation assisted stress corrosion cracking (IASCC) caused by simultaneous effects of neutron irradiation and high temperature water environments has been pointed out as one of the major concerns of in-core structural materials not only for the light water reactors (LWRs) but also for the water-cooled fusion reactor. It is necessary to evaluate precisely stress condition under irradiation environment, because stress is one of key factors on IASCC. Stress relaxation of tensile type specimens under fast neutron irradiation at 288
C has been studied for type 316L stainless steel in Japan Materials Testing Reactor (JMTR). This paper describes the in-pile and out-of-pile stress-relaxation test results of tensile type specimens for type 316L stainless steel as compared with the literature data by Foster, which were mainly obtained by bent beam specimens. Moreover these experimental results were compared with the analytical ones by using Nakagawa's model.
Saito, Shigeru; Fukaya, Kiyoshi*; Ishiyama, Shintaro; Amezawa, Hiroo; Yonekawa, Minoru; Takada, Fumiki; Kato, Yoshiaki; Takeda, Takashi; Takahashi, Hiroyuki*; Nakahira, Masataka
Journal of Nuclear Materials, 307-311(Part2), p.1573 - 1577, 2002/12
Times Cited Count：2 Percentile：16.38(Materials Science, Multidisciplinary)no abstracts in English
Ioka, Ikuo; Miwa, Yukio; Tsuji, Hirokazu; Yonekawa, Minoru; Takada, Fumiki; Hoshiya, Taiji
JSME International Journal, Series A, 45(1), p.51 - 56, 2002/01
The low cycle creep-fatigue test with tensile strain hold of the austenitic stainless steel irradiated to 2dpa was carried out at 823K in vacuum. The applicability of creep-fatigue life prediction methods to the irradiated specimen was examined. The fatigue life on the irradiated specimen without tensile strain hold time was reduced by a factor of 2-5 in comparison with the unirradiated specimen. The fraction of intergranular fracture increased with increasing strain hold time. The decline in fatigue life of the irradiated specimen with tensile strain hold was almost equal to that of the unirradiated specimen. For the irradiated specimen, the time fraction damage rule trends to yield unsafe estimated lives and the ductility exhaustion damage rule trends to yield generous results. However, all of data were predicted within a factor of three on life by the linear damage rule.
Ishii, Toshimitsu; Yonekawa, Minoru; Omi, Masao; Takada, Fumiki; Saito, Junichi; Ioka, Ikuo; Miwa, Yukio
KAERI/GP-192/2002, p.157 - 166, 2002/00
no abstracts in English
