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Journal Articles

New precise measurement of muonium hyperfine structure interval at J-PARC

Ueno, Yasuhiro*; Aoki, Masaharu*; Fukao, Yoshinori*; Higashi, Yoshitaka*; Higuchi, Takashi*; Iinuma, Hiromi*; Ikedo, Yutaka*; Ishida, Katsuhiko*; Ito, Takashi; Iwasaki, Masahiko*; et al.

Hyperfine Interactions, 238(1), p.14_1 - 14_6, 2017/11

 Times Cited Count:3 Percentile:86.59

Journal Articles

New muonium HFS measurements at J-PARC/MUSE

Strasser, P.*; Aoki, Masaharu*; Fukao, Yoshinori*; Higashi, Yoshitaka*; Higuchi, Takashi*; Iinuma, Hiromi*; Ikedo, Yutaka*; Ishida, Katsuhiko*; Ito, Takashi; Iwasaki, Masahiko*; et al.

Hyperfine Interactions, 237(1), p.124_1 - 124_9, 2016/12

 Times Cited Count:7 Percentile:91.29

Journal Articles

Progress report of Japanese simulation research projects using the high-performance computer system Helios in the International Fusion Energy Research Centre

Ishizawa, Akihiro*; Idomura, Yasuhiro; Imadera, Kenji*; Kasuya, Naohiro*; Kanno, Ryutaro*; Satake, Shinsuke*; Tatsuno, Tomoya*; Nakata, Motoki*; Nunami, Masanori*; Maeyama, Shinya*; et al.

Purazuma, Kaku Yugo Gakkai-Shi, 92(3), p.157 - 210, 2016/03

The high-performance computer system Helios which is located at The Computational Simulation Centre (CSC) in The International Fusion Energy Research Centre (IFERC) started its operation in January 2012 under the Broader Approach (BA) agreement between Japan and the EU. The Helios system has been used for magnetised fusion related simulation studies in the EU and Japan and has kept high average usage rate. As a result, the Helios system has contributed to many research products in a wide range of research areas from core plasma physics to reactor material and reactor engineering. This project review gives a short catalogue of domestic simulation research projects. First, we outline the IFERC-CSC project. After that, shown are objectives of the research projects, numerical schemes used in simulation codes, obtained results and necessary computations in future.

JAEA Reports

Performance confirmation operation of water environment control facility

Magome, Hirokatsu; Okada, Yuji; Tomita, Kenji; Iida, Kazuhiro; Ando, Hitoshi; Yonekawa, Akihisa; Ueda, Haruyasu; Hanawa, Hiroshi; Kanno, Masaru; Sakuta, Yoshiyuki

JAEA-Technology 2015-025, 100 Pages, 2015/09

JAEA-Technology-2015-025.pdf:78.32MB

In Japan Atomic Energy Agency, in order to solve the problem in the long-term operation of a light water reactor, preparation which does the irradiation experiment of light-water reactor fuel and material was advanced. JMTR stopped after the 165th operation cycle in August 2006, and is advancing renewal of the irradiation facility towards re-operation. The material irradiation test facility was installed from 2008 fiscal year to 2012 fiscal year in JMTR. The material irradiation test facility is used for IASCC study, and that consists of mainly three equipments. This report is described performance operating test of the water environmental control facilities for IASCC study carried out 2013 fiscal year.

JAEA Reports

Installation of the water environment irradiation facility for the IASCC research under the BWR/PWR irradiation environment, 2

Magome, Hirokatsu; Okada, Yuji; Hanawa, Hiroshi; Sakuta, Yoshiyuki; Kanno, Masaru; Iida, Kazuhiro; Ando, Hitoshi; Yonekawa, Akihisa; Ueda, Haruyasu; Shibata, Mitsunobu

JAEA-Technology 2014-023, 267 Pages, 2014/07

JAEA-Technology-2014-023-01.pdf:103.68MB
JAEA-Technology-2014-023-02.pdf:71.92MB

In Japan Atomic Energy Agency, in order to solve the problem in the long-term operation of a light water reactor, preparation which does the irradiation experiment of light-water reactor fuel and material was advanced. JMTR stopped after the 165th operation cycle in August 2006, and is advancing renewal of the irradiation facility towards re-operation. The material irradiation test facility was installed from 2008 fiscal year to 2012 fiscal year in JMTR. This report summarizes manufacture and installation of the material irradiation test facility for IASCC research carried out from 2012 to 2014 in the follow-up report reported before (JAEA-Technology 2013-019).

JAEA Reports

Installation of the water environment irradiation facility for the IASCC research under the BWR irradiation environment, 1

Okada, Yuji; Magome, Hirokatsu; Hanawa, Hiroshi; Omi, Masao; Kanno, Masaru; Iida, Kazuhiro; Ando, Hitoshi; Shibata, Mitsunobu; Yonekawa, Akihisa; Ueda, Haruyasu

JAEA-Technology 2013-019, 236 Pages, 2013/10

JAEA-Technology-2013-019.pdf:45.07MB

In Japan Atomic Energy Agency, in order to solve the problem in the long-term operation of a light water reactor, preparation which does the irradiation experiment of light-water reactor fuel and material is advanced. JMTR stopped after the 165th operation cycle in August 2006, and is advancing renewal of the irradiation facility towards re-operation. This material irradiation test facility and power ramping test facility for doing the neutron irradiation test of the fuel and material for light water reactors is scheduled to be manufactured and installed between the 2008 fiscal year and the 2012 fiscal year. This report summarizes manufacture and installation of the material irradiation test facility for IASCC research carried out from the 2008 fiscal year to the 2010 fiscal year.

JAEA Reports

Experimental study on dilution coefficients measurement of capsule dilution tube for fuel transient tests

Inoue, Shuichi; Omuro, Tadao; Nabeya, Hideaki; Matsui, Yoshinori; Iida, Kazuhiro; Ito, Kazuyuki; Kimura, Akihiro; Kanno, Masaru

JAEA-Technology 2010-010, 27 Pages, 2012/05

JAEA-Technology-2010-010.pdf:1.99MB

In fuel irradiation transient tests using a boiling water capsule, a dilution tube has been installed in the boiling water capsule in order to detect fission products (FP) from an irradiated fuel, in case of the fuel failure during the transient, by a radiation monitor located outside the reactor. When the fuel failure occurs, the released FP flows out from the capsule through the dilution tube. The dilution tube is designed to minimize the released FP that can be detected by the radiation monitor located outside the reactor. This report summarized the measurement results of the dilution tube installed in the boiling water capsule.

JAEA Reports

Outline of new irradiation facility in JMTR

Takahashi, Kiyoshi; Hanawa, Hiroshi; Onuma, Yuichi; Hosokawa, Jinsaku; Kanno, Masaru

JAEA-Technology 2012-007, 31 Pages, 2012/03

JAEA-Technology-2012-007.pdf:4.76MB

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.

JAEA Reports

Fabrication study of new irradiation facility for $$^{99}$$Mo production in JMTR

Takita, 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 $$^{99}$$Mo, which is a parent nuclide of $$^{99}$$Tc. $$^{99m}$$Tc is most commonly used as a radiopharmaceution in the field of nuclear medicine. Currently $$^{99}$$Mo supply is dependent only on foreign imports, so JAEA is aiming for working on partially manufacturing $$^{99}$$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 $$^{99}$$Mo, the technical study of fabrication technique.

Journal Articles

Status of the design and investigation for hydraulic rabbit irradiation facility

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

Journal Articles

Reduction of intrinsic critical current density under a magnetic field along the hard axis of a free layer in a magnetic tunnel junction

Miura, Katsuya*; Sugano, Ryoko*; Ichimura, Masahiko*; Hayakawa, Jun*; Ikeda, Shoji*; Ohno, Hideo*; Maekawa, Sadamichi

Physical Review B, 84(17), p.174434_1 - 174434_7, 2011/11

 Times Cited Count:1 Percentile:5.41(Materials Science, Multidisciplinary)

JAEA Reports

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.

JAEA Reports

Post irradiation examination of type 316 stainless steels for in-pile Oarai Water Loop No.2 (OWL-2)

Shibata, Akira; Kimura, Tadashi; Nagata, Hiroshi; Aoyama, Masashi; Kanno, Masaru; Omi, Masao

JAEA-Testing 2010-003, 22 Pages, 2010/11

JAEA-Testing-2010-003.pdf:8.82MB

Type 316 stainless steels (SSs) were used for tube material of the Oarai water loop No.2 (OWL-2) in the reactor. But data of highly irradiated Type 316 SSs has been insufficient since OWL-2 was installed. Therefore surveillance tests of type 316 SSs which were irradiated up to 3.4 $$times$$ 10$$^{25}$$ n/m$$^{2}$$ in fast neutron fluence ($$>$$1 MeV) were performed. But type 316 SSs were widely used in JMTR, then additional data of type 316 SSs irradiated higher was required. Therefore PIEs of type 316 SSs surveillance specimens which were irradiated up to 1.0 $$times$$ 10$$^{26}$$ n/m$$^{2}$$ in fast neutron fluence were performed and reported in this paper. Tendency of results has good agreement with results of 10$$^{24}$$-10$$^{25}$$ n/m$$^{2}$$ in fast neutron fluence. More than 37 % in total elongation was confirmed in all test conditions. It is confirmed that type 316 SS irradiated up to 1.0 $$times$$ 10$$^{26}$$ n/m$$^{2}$$ in fast neutron fluence has enough ductility as structure material.

JAEA Reports

Dismantlement technique of irradiation facilities in JMTR

Onuma, Yuichi; Okada, Yuji; Hanawa, Hiroshi; Tsuchiya, Kunihiko; Kanno, Masaru

JAEA-Review 2010-047, 27 Pages, 2010/11

JAEA-Review-2010-047.pdf:3.0MB

The Japan Materials Testing Reactor (JMTR) has been refurbished to re-operate from 2011. As a part of the establishment of new irradiation facilities, technology development for the dismantling and removing of irradiation facilities such as OWL-1 (Oarai Water Loop No.1), OWL-2 (Oarai Water Loop No.2) and IASCC (Irradiation Assisted Stress Corrosion Cracking) facility installed in the JMTR loop cubicles has been performed. By using developed methods, techniques for the dismantling and removing of the irradiation facilities were established.

JAEA Reports

Design examination of the high-duty irradiation loop

Ogawa, Mitsuhiro; Iimura, Koichi; Hosokawa, Jinsaku; Kanno, Masaru

JAEA-Technology 2010-019, 178 Pages, 2010/07

JAEA-Technology-2010-019.pdf:20.16MB

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.

JAEA Reports

Conceptual study for new $$^{99}$$Mo-production facility in JMTR

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-Review-2009-072.pdf:9.29MB

JAEA has a plan to produce $$^{99}$$Mo, a parent nuclide of $$^{99m}$$Tc. At present, radioisotopes are indispensable for a diagnosis and treatment in the medical field. Demand of $$^{99m}$$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 $$^{99}$$Mo in Japan depends fully on the import from foreign countries. Therefore, it is necessary to supply $$^{99}$$Mo stably by the domestic production. There are two methods of $$^{99}$$Mo (half life 65.9h) production; the one is the nuclear fission (n,fiss) method, and the other is the (n,$$gamma$$) method using the $$^{98}$$Mo target. $$^{99}$$Mo production in the JMTR with the (n,$$gamma$$) method was studied and evaluated. As a result, it was found that the partial amount of $$^{99}$$Mo demand is possible to supply stably if a new hydraulic-rabbit-irradiation-facility (HR) is used.

Journal Articles

Development of mechanical seal for re-capsule

Inoue, Shuichi; Yamaura, Takayuki; Saito, Takashi; Kanno, Masaru

UTNL-R-0475, p.2_4_1 - 2_4_10, 2010/03

no abstracts in English

JAEA Reports

Current status of JMTR refurbishment project

Kaminaga, Masanori; Niimi, Motoji; Hori, Naohiko; Takahashi, Kunihiro; Kanno, Masaru; Nakagawa, Tetsuya; Nagao, Yoshiharu; Ishihara, Masahiro; Kawamura, Hiroshi

JAEA-Review 2009-056, 20 Pages, 2010/02

JAEA-Review-2009-056.pdf:8.35MB

The JMTR is a light water moderated and cooled, beryllium reflected tank- type reactor using LUE silicide plate-type fuels. Its thermal power is 50 MW, maximum thermal and fast neutron flux is 4 $$times$$ 10$$^{18}$$ m$$^{-2}$$s$$^{-1}$$. First criticality was achieved in March 1968, and its operation was stopped from August, 2006 for the refurbishment. The refurbishment is scheduled from the beginning of FY2007 to the end of FY2010. The renewed and upgraded JMTR will be re-started from FY2011. An investigation on aged components (aged-investigation) was carried out for concrete structures of the JMTR reactor building, exhaust stack, etc., and for tanks in the primary cooling system, heat exchangers, pipes in the secondary cooling system, cooling tower, emergency generators and so on, in order to identify their integrity. The aged-investigation was carried out at the beginning of FY2007. As a result, some components were decided to replace from viewpoints of future maintenance and improvement of reliability, and some components or structures were decided to repair. A visual inspection of inner side of the pressure vessel was carried out using an underwater camera in FY2008, and no serious damage was observed. Up to now, refurbishment works are in progress according to the planned schedule. In this paper, current status of JMTR refurbishment project is presented.

Journal Articles

Conceptual plan of radiopharmaceutical production process in JMTR

Iimura, Koichi; Sakamoto, Taichi; Kanno, Masaru; Hori, Naohiko

FAPIG, (178), p.14 - 18, 2009/02

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 $$^{99}$$Mo, which is a parent nuclide of $$^{rm 99m}$$Tc. $$^{rm 99m}$$Tc is most commonly used as a radiopharmaceutical in the field of nuclear medicine. Currently the supplying of $$^{99}$$Mo is only depend on imports from foreign countries, so JAEA is aiming at domestic production of a part of $$^{99}$$Mo in cooperation with the industrial circles. In this article, JAEA introduced the Conceptual Plan about the choice and fabric of the irradiation facilities for $$^{99}$$Mo production, and commercializing equipment after irradiation for $$^{99}$$Mo production.

JAEA Reports

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 $$^{60}$$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.

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