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Nishimura, Arashi; Okada, Yuji; Sugaya, Naoto; Sonobe, Hiroshi; Kimura, Nobuaki; Kimura, Akihiro; Hanawa, Yoshio; Nemoto, Hiroyoshi
JAEA-Technology 2021-003, 51 Pages, 2021/05
JAEA-Technology-2021-003.pdf:5.55MB
In the Japan Materials Testing Reactor (JMTR), the leakage accidents of radioactive waste liquid were occurred from the tanks and pipes of the liquid waste disposal facility in the JMTR tank-yard building in JFY2014. In order to respond to the accident, obtain the approval of the JAEA to the design and construction method from JFY2016, the tanks and pipes were replaced from JFY2016 to 2019. In the replaced, the production of the tanks and pipes of the liquid waste disposal facility applied Japanese technical standards correspondingly. On the other hand, the valve did not fall under the category of Japanese technical standards. The manufacturing specifications when replacing the valve were decided based on the including the selecting the standards of production and inspection for valves, Fluid properties, experience in JMTR. The production proceeded while carrying out the decided inspection. The valves that passed all the inspections were installed together with the tanks and pipes of the liquid waste, and the finished inspection was performed as a systems. The construction was completed with those inspection passed. This report is summarized valve Design, production and installation.
Ono, Masato; Hanawa, Yoshio; Sonobe, Hiroshi; Nishimura, Arashi; Sugaya, Naoto; Iigaki, Kazuhiko
JAEA-Technology 2020-010, 14 Pages, 2020/09
JAEA-Technology-2020-010.pdf:1.74MB
In response to new standard for regulating research and test reactor which is enforced December 18, 2013, it was carried out assessment of the probability of aircraft crashing for HTTR. According to assessment method provided in the Assessment Criteria of the Probability of Aircraft Crashing on Commercial Power Reactor Facilities, assessment was conducted targeting reactor building, spent fuel storage building and cooling tower. As a result, it was confirmed that the probability was 5.98
10
, which is lower than the assessment criteria 10
.
Sugaya, Naoto; Okada, Yuji; Nishimura, Arashi; Sonobe, Hiroshi; Kimura, Nobuaki; Kimura, Akihiro; Hanawa, Yoshio; Nemoto, Hiroyoshi
JAEA-Testing 2020-004, 67 Pages, 2020/08
JAEA-Testing-2020-004.pdf:8.17MB
In the Japan Materials Testing Reactor (JMTR), the leakage accidents of radioactive waste liquid were occurred from the tanks and pipes of the liquid waste disposal facility in the JMTR tank-yard building in JFY2014. In order to respond to the accident, the tanks and pipes were replaced from JFY2016 to 2019. On the other hand, a lot of cracks were occurred on the concreate wall of the tank-yard building when the frame structure supports were fixed to the concrete wall in the replacement work. Thus, it is necessary to repair the concreate wall of the tank-yard building. Especially, some cracks with swelling (cone-shaped fracture) were raised around some anchor bolts (the post-installed chemical anchor bolts) fixed the frame structure supports. The repairing method for the cone-shaped fracture of the concrete wall is standardized, but there was no reference value of tensile strength for the validation of the post-installed chemical anchor bolts after the repairing method. In this report, the repairing method was selected for the cone-shaped fracture on the concreate wall and the reference value of tensile strength for the validation of the post-installed chemical anchor bolts by this repairing method. The mock-ups for repairing cone-shaped fracture were fabricated by the selected repairing method and the tensile tests of the post-installed chemical anchor bolts were performed. From the results, the validation of the repairing method was obtained in this test and it was obvious the repairing of cone-shaped fracture is preferable method for the concreate wall of the JMTR tank-yard building.
Ishitsuka, Etsuo; Motohashi, Jun; Hanawa, Yoshio; Komeda, Masao; Watahiki, Shunsuke; Mukanova, A.*; Kenzhina, I. E.*; Chikhray, Y.*
JAEA-Technology 2014-025, 77 Pages, 2014/08
JAEA-Technology-2014-025.pdf:43.46MB
It has been shown that tritium concentration in the primary coolant of the JMTR and JRR-3M increases during its operation. In this report, to clarify the tritium sources, the tritium release rate into the primary coolant in each operation cycle for the JMTR, JRR-3M and JRR-4 was evaluated. As a result, the tritium release rate is 
8 Bq/Wd in the JRR-4, which has not the beryllium core components installed, and no increase in the tritium concentration during reactor operation is observed. In contrast, the tritium release rate is about 10
95 and 60140 Bq/Wd in the JRR-3M and JMTR respectively, which cores contain beryllium components, and where the tritium content increases while reactor operates. It is also observed that the amount of released tritium is lower in the case of new beryllium components installation, and increases with the reactor operating cycle.
Kameyama, Yasuhiko; Onoue, Ryuji; Hanawa, Yoshio; Nemoto, Nobuaki
UTNL-R-0483, p.10_6_1 - 10_6_6, 2013/03
no abstracts in English
Ito, Masayasu; Kitagishi, Shigeru; Hanawa, Yoshio; Tsuchiya, Kunihiko; Hatano, Yuji*; Matsuyama, Masao*; Nagasaka, Takuya*; Hishinuma, Yoshimitsu*
Annual Report of National Institute for Fusion Science; April 2011 - March 2012, P. 535, 2012/12
Beryllium has been utilized as a moderator and/or reflector in a number of material testing reactors. Beryllium is also supposed to be widely used in fusion reactors as neutron multiplier and protective walls of plasma facing components. It is important to perform the characterization of the different grade beryllium such as the productivity, mechanical and chemical properties and the interaction under water and/or gas environment. In this study, three kinds of beryllium (S-200F, S-65H, I-220H) were prepared, and corrosion test and surface analysis of these beryllium samples were carried out for life time expansion under pure water. As a result, the surface change of each Be sample was observed by the corrosion test and influenced by the content of BeO and the grain size.
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
Watahiki, Shunsuke; Hanawa, Yoshio; Asano, Norikazu; Hiyama, Kazuhisa; Ito, Sachito; Tsuboi, Kazuaki; Fukasaku, Akitomi
JAEA-Review 2012-013, 92 Pages, 2012/03
JAEA-Review-2012-013.pdf:6.74MB
This replacement work was carried out under refurbishment plan of JMTR for beryllium distortion draw to acceptable limit. And gamma-ray shield refurbishment was carried out the view point of prevention maintenance in consideration of operation plan. Fabrication of beryllium frame and gamma-ray shield was spent for two years it was finished in February, 2010. It took five months to replacement work from January 2010. In this report is presented fabrication and replacement work of beryllium frame and gamma-ray shield.
Tsuchiya, Kunihiko; Kitagishi, Shigeru; Ito, Masayasu; Hanawa, Yoshio; Hatano, Yuji*; Matsuyama, Masao*; Nagasaka, Takuya*; Hishinuma, Yoshimitsu*
Annual Report of National Institute for Fusion Science; April 2010 - March 2011, P. 545, 2011/11
no abstracts in English
Tanimoto, Masataka; Taguchi, Taketoshi; Okada, Manabu; Hanawa, Yoshio; Tsuchiya, Kunihiko; Ikeda, Masayuki*; Fujimoto, Yoichi*; Kotov, V.*; Kenzhin, E.*; Kenzhin, Y.*
JAEA-Technology 2011-001, 39 Pages, 2011/03
JAEA-Technology-2011-001.pdf:4.15MB
It is important problem to recycle the irradiated beryllium from the points of effective use of resources, reduction of radioactive waste and nuclear nonproliferation. The recycling of the irradiated beryllium has been considered as the part of the development of Irradiation technology for JMTR refurbishment and restart. The ISTC regular project (K-1566) on recycling technology of irradiated beryllium has been carried out in the Institute of Atomic Energy (IAE), National Nuclear Center of Republic of Kazakhstan (NNC-RK). This paper is described on the transport procedure and transport results of the irradiated beryllium from Japan Atomic Energy Agency (JAEA) to IAE, NNC-RK under the ISTC project.
Tsuchiya, Kunihiko; Hanawa, Yoshio; Kitagishi, Shigeru; Ito, Masayasu; Hatano, Yuji*; Matsuyama, Masao*
Heisei-21-Nendo Toyama Daigaku Kyodo Riyo, Kyodo Kenkyu Seika Hokokusho, p.9 - 10, 2010/12
no abstracts in English
Watahiki, Shunsuke; Asano, Norikazu; Hanawa, Yoshio; Gorai, Shigeru; Nishiyama, Yutaka; Tsuboi, Kazuaki
JAEA-Review 2010-019, 65 Pages, 2010/07
JAEA-Review-2010-019.pdf:7.25MB
JMTR secondary cooling system piping and a cooling tower were inspected from the view point of long term utilization before the renewal work for the secondary cooling system of the JMTR on FY 2008. As the result, it was confirmed that crack, swelling, and exfoliations in inner of piping lining, and decay and dryness of wood in the upper part of the cooling tower. From the result of this inspection some facilities and machinery were repaired or replaced from the view point of preventive maintenance.
Hanawa, Yoshio; Tsuboi, Kazuaki; Uchida, Munenori*; Suzuki, Ken*; Takahashi, Kunihiro
JAEA-Technology 2009-078, 18 Pages, 2010/03
JAEA-Technology-2009-078.pdf:11.35MB
Beryllium has been used as the neutron reflector in the Japan Materials Testing Reactor (JMTR). A beryllium frame is arranged in the JMTR core and the frame consists of 3 sections (North, East and West). Each section has 7 stories of the beryllium blocks. Each block is connected by the aluminum joints. The capsule or the beryllium plug is located in the inside of the beryllium frame. The first criticality achieved in 1968 and the frame has been replaced 6 times and now the 7th frame is being manufactured. The replacement is planned to be done in the spring of 2010. The design has been modified to decrease the swelling camber and the lifetime has been improved. The manufacturing procedure is severely controlled to assure the quality. The chemical composition must be specified to minimize the swelling and radiation. The machining procedure is highly controlled because beryllium is very brittle. And the environmental control is also important, because the beryllium is a toxic material.
Ebisawa, Hiroyuki; Hanakawa, Hiroki; Asano, Norikazu; Kusunoki, Hidehiko; Yanai, Tomohiro; Sato, Shinichi; Miyauchi, Masaru; Oto, Tsutomu; Kimura, Tadashi; Kawamata, Takanori; et al.
JAEA-Technology 2009-030, 165 Pages, 2009/07
JAEA-Technology-2009-030.pdf:69.18MB
The condition of facilities and machinery used continuously were investigated before the renewal work of JMTR on FY 2007. The subjects of investigation were reactor building, primary cooling system tanks, secondary cooling system piping and tower, emergency generator and so on. As the result, it was confirmed that some facilities and machinery were necessary to repair and others were used continuously for long term by maintaining on the long-term maintenance plan. JMTR is planed to renew by the result of this investigation.
Ide, Hiroshi; Sakuta, Yoshiyuki; Hanawa, Yoshio; Tsuji, Tomoyuki; Tsuboi, Kazuaki; Nagao, Yoshiharu; Miyazawa, Masataka
JAEA-Technology 2009-019, 28 Pages, 2009/06
JAEA-Technology-2009-019.pdf:41.1MB
The main body of the JMTR is composed of reactor pressure vessel, core and reactor pool. At the bottom of the reactor pool, the Diaphragm-seal (2.6m outer diameter, 2m inner diameter, thickness 1.5mm) of the JMTR made of stainless steel is installed to prevent the water leak of the reactor pool and to absorb the expansion of the reactor pressure vessel due to pressure and temperature changes. Prior to the refurbishment of the JMTR, the inspection device which is a deposition-collection apparatus with underwater-camera was developed, and the visual inspection was carried out to confirm the soundness of the diaphragm-seal. As a result, harmful flaws and/or corrosions were not inspected in the visual inspection, and the soundness of the diaphragm seal was confirmed. In future, the long-term integrity of the diaphragm-seal will could be achieved by conducting the periodic inspection.
Hanawa, Yoshio; Taguchi, Taketoshi; Kitagishi, Shigeru; Tsuboi, Kazuaki; Tsuchiya, Kunihiko
UTNL-R-0471, p.5_2_1 - 5_2_8, 2009/03
no abstracts in English
Taguchi, Taketoshi; Sozawa, Shizuo; Hanawa, Yoshio; Kitagishi, Shigeru; Tsuchiya, Kunihiko
JAEA-Conf 2008-010, p.343 - 352, 2008/12
Beryllium has been utilized as a moderator and/or reflector in Japan Materials Testing Reactor (JMTR), because of nuclear properties of beryllium, low neutron capture and high neutron scattering cross sections. At present, it is necessary to exchange the beryllium frames within every fixed period; frames were exchanged five times up to the JMTR operation periods of 165th cycles, and amount of irradiated beryllium frames in JMTR is about 2 tons in the JMTR canal. In this study, preliminary irradiation test with two kinds of beryllium metals (S-200F and S-65C) was performed from 162nd to 165th operation cycles of JMTR as irradiation and PIE technique development for lifetime expansion of beryllium frames. The design study of irradiation capsule, development of dismount device of irradiation capsule and the high accuracy size measurement device were carried out. The results of PIEs such as tensile tests, metallurgical observation, and size change measurement were presented in this seminar.
Takemoto, Noriyuki; Hanawa, Yoshio; Gorai, Shigeru; Fukasaku, Akitomi; Miyazawa, Masataka; Niimi, Motoji
JAEA-Conf 2008-010, p.97 - 105, 2008/12
Operation of the Japan Materials Testing Reactor (JMTR), a light-water-cooling tank-type reactor with a 50 MW thermal power, was stopped in August 2006, and now its refurbishment is on going. The reactor facilities are to be refurbished during four years from the beginning of FY 2007, and the renewed JMTR will be operated from FY 2011 until around FY 2030. As for the decision of the refurbishment, reactor facilities to be renewed and to be continuously used were selected from a viewpoint of ensuring safety, improvement of availability-factor, etc. The selected renewal reactor facilities were the reactor instrument and control system, cooling system, radioactive waste facility, power supply system, boiler, etc. Presented are the basic idea on selection of the renewal facilities, outline of these facilities and schedule of refurbishment work.
Taguchi, Taketoshi; Hanawa, Yoshio; Watahiki, Shunsuke; Tsuchiya, Kunihiko
JAEA-Technology 2008-041, 23 Pages, 2008/06
JAEA-Technology-2008-041.pdf:3.76MB
Beryllium has been utilized as a reflector in a number of material testing reactors because of low parasitic capture cross section for thermal neutrons and good neutron elastic scattering characteristics. Beryllium frames and beryllium reflectors, which have been utilized as neutron reflector in Japan JMTR, were fabricated beryllium metals. Especially, it is necessary to exchange the beryllium frames every fixed period. Therefore, preliminary irradiation test of beryllium metals (S-200F and S-65C) was performed in JMTR for development on long life of beryllium reflectors. The post irradiation examinations (PIEs) were carried out for the effect on the properties of these irradiated beryllium metals. In these PIEs, size change of the irradiated beryllium was measured with the specimens for bending. This report is described development of the high accuracy measurement device.
Hanawa, Yoshio; Taguchi, Taketoshi; Tsuboi, Kazuaki; Saito, Takashi; Ishikawa, Kazuyoshi; Watahiki, Shunsuke; Tsuchiya, Kunihiko
JAEA-Technology 2008-039, 53 Pages, 2008/06
JAEA-Technology-2008-039.pdf:6.18MB
Beryllium has been utilized as a moderator and/or reflector in a number of material testing reactors. Beryllium frames and beryllium reflectors, which have been utilized as neutron reflector in Japan Materials Testing Reactor (JMTR) in JAEA, were fabricated beryllium metals of S-200F grade. Especially, it is necessary to exchange the beryllium frames every fixed period and there frames were exchanged six times up to the JMTR operation periods of 165 cycles. Therefore, preliminary irradiation test of beryllium metals was performed from 162 to 165 cycles of JMTR operations as a part of development on long life of beryllium reflectors. Two kinds of beryllium metals (S-200F and S-65C) were prepared in this test. This report is described the design study and fabrication of irradiation capsule of beryllium metals and dismount device of irradiation capsule.
