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JAEA Reports

Investigation on soundness of JMTR Facility piping by ultrasonic thickness measurement

Omori, Takazumi; Otsuka, Kaoru; Endo, Yasuichi; Takeuchi, Tomoaki; Ide, Hiroshi

JAEA-Review 2021-015, 57 Pages, 2021/11

JAEA-Review-2021-015.pdf:6.3MB

The JMTR reactor facility was selected as a decommissioning one in the Medium/Long-Term Management Plan of JAEA Facilities formulated on April 1, 2017. Therefore, the decommissioning plan was submitted to Nuclear Regulation Authority on September 18, 2019, and the approval was obtained on March 17, 2021 after two amendments. Currently, preparations for decommissioning are underway. The JMTR reactor facility has been aged for more than 50 years since the first criticality in March 1968. However, some of the water piping systems has not been updated since its construction, and there is a possibility of pipe wall thinning due to corrosion, etc. Therefore, the integrity of the water piping was investigated for the facilities that circulate cooling water and pump radioactive liquid waste. In this investigation, the main circulation system of the reactor primary cooling system, the pool canal circulation system, the CF pool circulation system, the drainage system of the liquid waste disposal system, and the hydraulic rabbit irradiation system of the main experimental facility were measured for the pipe wall thickness using the Ultrasonic Thickness Measurement (UTM) method. These values satisfied the technical standards for research and test reactor facilities. No loss of integrity is expected to occur during the upcoming decommissioning period. In the future, we will periodically confirm that there is no wall thinning in the piping of the cooling water circulation and the water transmission system during the decommissioning period by using this result as basic data.

JAEA Reports

Soundness survey of cooling tower of Utility Cooling Loop (UCL Cooling Tower) in JMTR

Oto, Tsutomu; Asano, Norikazu; Kawamata, Takanori; Yanai, Tomohiro; Nishimura, Arashi; Araki, Daisuke; Otsuka, Kaoru; Takabe, Yugo; Otsuka, Noriaki; Kojima, Keidai; et al.

JAEA-Review 2020-018, 66 Pages, 2020/11

JAEA-Review-2020-018.pdf:8.87MB

A collapse event of the cooling tower of secondary cooling system in the JMTR (Japan Materials Testing Reactor) was caused by the strong wind of Typhoon No.15 on September 9, 2019. The cause of the collapse of the cooling tower was investigated and analyzed. As the result, it was identified that four causes occurred in combination. Thus, the soundness of the cooling tower of Utility Cooling Loop (UCL cooling tower), which is a wooden cooling tower installed at the same period as the cooling tower of secondary cooling system, was investigated. The items of soundness survey are to grasp the operation conditions of the UCL cooling tower, to confirm the degradation of structural materials, the inspection items and inspection status of the UCL cooling tower, and to investigate the past meteorological data. As the results of soundness survey of the UCL cooling tower, the improvement of inspection items of the UCL cooling tower was carried out and the replacement and repair of the structural materials of the UCL cooling tower were planned for safe maintenance and management of this facility. And the renewal plan of new cooling tower was created to replace the existing UCL cooling tower. This report is summarized the soundness survey of the UCL cooling tower.

Journal Articles

Development of the treatment method for difficult wastes aimed at decommissioning of JMTR; Structural materials of reactor and used ion-exchange resins

Seki, Misaki; Nakano, Hiroko; Nagata, Hiroshi; Otsuka, Kaoru; Omori, Takazumi; Takeuchi, Tomoaki; Ide, Hiroshi; Tsuchiya, Kunihiko

Dekomisshoningu Giho, (62), p.9 - 19, 2020/09

Japan Materials Testing Reactor (JMTR) has been contributing to various research and development activities such as the fundamental research of nuclear materials/fuels, safety research and development of power reactors, and radioisotope production since the beginning of the operation in 1968. JMTR, however, was decided as a one of decommission facilities in April 2017 and it is taken an inspection of a plan concerning decommissioning because the performance of JMTR does not confirm with the stipulated earthquake resistance. As aluminum and beryllium are used for the core structural materials in JMTR, it is necessary to establish treatment methods of these materials for the fabrication of stable wastes. In addition, a treatment method for the accumulated spent ion-exchange resins needs to be examined. This report describes the overview of these examination situations.

Journal Articles

Research on activation assessment of a reactor structural materials for decommissioning, 2

Seki, Misaki; Ishikawa, Koji*; Sano, Tadafumi*; Nagata, Hiroshi; Otsuka, Kaoru; Omori, Takazumi; Hanakawa, Hiroki; Ide, Hiroshi; Tsuchiya, Kunihiko; Fujihara, Yasuyuki*; et al.

KURNS Progress Report 2019, P. 279, 2020/08

no abstracts in English

Journal Articles

Research on activation assessment of a reactor structural materials for decommissioning

Seki, Misaki; Ishikawa, Koji*; Nagata, Hiroshi; Otsuka, Kaoru; Omori, Takazumi; Hanakawa, Hiroki; Ide, Hiroshi; Tsuchiya, Kunihiko; Sano, Tadafumi*; Fujihara, Yasuyuki*; et al.

KURNS Progress Report 2018, P. 257, 2019/08

no abstracts in English

Journal Articles

Status of JMTR decommissioning plan formulation, 2

Otsuka, Kaoru; Ide, Hiroshi; Nagata, Hiroshi; Omori, Takazumi; Seki, Misaki; Hanakawa, Hiroki; Nemoto, Hiroyoshi; Watanabe, Masao; Iimura, Koichi; Tsuchiya, Kunihiko; et al.

UTNL-R-0499, p.12_1 - 12_8, 2019/03

no abstracts in English

Journal Articles

Preliminary analysis for demolition of secondary cooling system and pool canal cycling system secondary piping

Hanakawa, Hiroki; Kawamata, Takanori; Ogasawara, Yasushi; Otsuka, Kaoru; Omori, Takazumi; Ide, Hiroshi; Tsuchiya, Kunihiko

UTNL-R-0499, p.11_1 - 11_7, 2019/03

no abstracts in English

Journal Articles

Status of JMTR decommissioning plan formulation

Otsuka, kaoru; Hanakawa, Hiroki; Nagata, Hiroshi; Omori, Takazumi; Takeuchi, Tomoaki; Tsuchiya, Kunihiko

UTNL-R-0496, p.13_1 - 13_11, 2018/03

no abstracts in English

JAEA Reports

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.

JAEA Reports

Renewal of reactor cooling system of JMTR; Reactor building site

Onoue, Ryuji; Kawamata, Takanori; Otsuka, Kaoru; Sekine, Katsunori; Koike, Sumio; Gorai, Shigeru; Nishiyama, Yutaka; Fukasaku, Akitomi

JAEA-Review 2012-010, 116 Pages, 2012/03

JAEA-Review-2012-010-01.pdf:65.41MB
JAEA-Review-2012-010-02.pdf:81.33MB
JAEA-Review-2012-010-03.pdf:87.98MB
JAEA-Review-2012-010-04.pdf:45.25MB

JMTR is a light water moderated and cooled tank-type reactor, and its thermal power is 50 MW. The JMTR is categorized as high flux testing reactors in the world. The JMTR has been utilized for irradiation experiments of nuclear fuels and materials, as well as for radioisotope productions since the first criticality in March 1968 until August 2006. JAEA is decided to refurbish the JMTR as an important fundamental infrastructure to promote the nuclear research and development. And The JMTR refurbishment work is carried out for 4 years from 2007. Before refurbishment work, from August 2006 to March 2007, all concerned renewal facilities were selected from evaluation on their damage and wear in terms of aging. Facilities which replacement parts are no longer manufactured or not likely to be manufactured continuously in near future, are selected as renewal ones. Replace priority was decided with special attention to safety concerns. A monitoring of aging condition by the regular maintenance activity is an important factor in selection of continuous using after the restart. In this report, renewal of the cooling system within refurbishment facilities in the JMTR is summarized.

JAEA Reports

Renewal of cooling system of JMTR

Onoue, Ryuji; Kawamata, Takanori; Otsuka, Kaoru; Koike, Sumio; Nishiyama, Yutaka; Fukasaku, Akitomi

JAEA-Review 2011-018, 17 Pages, 2011/06

JAEA-Review-2011-018.pdf:2.71MB

JMTR is a light water moderated and cooled tank-type reactor, and its thermal power is 50 MW. The JMTR is categorized as high flux testing reactors in the world. The JMTR has been utilized for irradiation experiments of nuclear fuels and materials, as well as for radioisotope productions since the first criticality in March 1968 until August 2006. JAEA decided to refurbish the JMTR as an important fundamental infrastructure to promote the nuclear research and development. The refurbishment work was started from 2007, and restart is planned in 2011. Renewal facilities were selected from evaluation on their damage and wear in terms of aging. Facilities whose replacement parts are no longer manufactured or not likely to be manufactured continuously in near future, are selected as renewal ones. Replacement priority was decided with special attention to safety concerns. A monitoring of aging condition by the regular maintenance activity is an important factor in selection of continuous using after the restart. In this report, renewal of the cooling system within refurbishment facilities in the JMTR is summarized.

JAEA Reports

Verification on reliability of heat exchanger for primary cooling system

Koike, Sumio; Gorai, Shigeru; Onoue, Ryuji; Otsuka, Kaoru

JAEA-Review 2010-007, 36 Pages, 2010/07

JAEA-Review-2010-007.pdf:5.0MB

Prior to the JMTR refurbishment, verification on reliability of the heat exchangers for primary cooling system was carried out to investigate an integrity of continuously use component. From a result of the significant corrosion, decrease of tube thickness, crack were not observed on the heat exchangers, and integrity of heat exchangers were confirmed. In the long terms usage of the heat exchangers, the maintenance based on periodical inspection and a long-term maintenance plan is scheduled.

JAEA Reports

The Outline of investigation on integrity of JMTR concrete structures, cooling system and utility facilities

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.

Journal Articles

Vapor-liquid equilibria for the HI+H$$_{2}$$O system and the HI+H$$_{2}$$O+I$$_{2}$$ system

Hodotsuka, Masatoshi; Yang, X.*; Okuda, Hiroyuki; Onuki, Kaoru

Journal of Chemical and Engineering Data, 53(8), p.1683 - 1687, 2008/07

 Times Cited Count:27 Percentile:71.87(Thermodynamics)

The isobaric Vapor Liquid Equilibrium(VLE) data in the pressure range of 0.11-0.58MPa where no experimental data had existed was measured for the purpose of increasing VLE data of hydriodic acid which is important physical properties which influence greatly the heat balance and mass balance in the thermochemical IS Cycle. Bubbling point and VLE data of hydriodic acid, which is prepared as adding iodine to almost azeotrope (57%) in the I$$_{2}$$/HI molar ratio from 0 to 4, were acquired at atmospheric pressure using a glass-made Othemer still. It was confirmed that the ratio of HI/H$$_{2}$$O of pseudo azeotrope increased as adding iodine. Furthermore, bubbling point and VLE data near the azeotrope in the high pressure range using a tantalum and Hastelloy made Gillespie still. The results quantitatively showed decrese of HI/H$$_{2}$$O molar ratio of azeotrope as increasing pressure, which used to be estimated by the result of measuring total pressure of hydriodic acid.

Journal Articles

Flow sheet evaluations for the thermochemical water-splitting Iodine-Sulfur process, 1

Kubo, Shinji; Ijichi, Masanori*; Hodotsuka, Masatoshi; Yoshida, Mitsunori*; Kasahara, Seiji; Isaka, Kazuyoshi; Tanaka, Nobuyuki; Imai, Yoshiyuki; Onuki, Kaoru

Proceedings of 2007 AIChE Annual Meeting (CD-ROM), 7 Pages, 2007/11

no abstracts in English

Oral presentation

Application of membrane systems to the IS process

Onuki, Kaoru; Kasahara, Seiji; Tanaka, Nobuyuki; Okuda, Hiroyuki; Yoshida, Mitsunori; Hodotsuka, Masatoshi; Iwatsuki, Jin; Imai, Yoshiyuki; Noguchi, Hiroki; Terada, Atsuhiko; et al.

no journal, , 

Development of efficient HI processing scheme is important for attaining high thermal efficiency of hydrogen production by IS process. We are studying an application of electro-electrodialysis to pre-concentrate the HIx solution before distillation, which is supplied from the Bunsen reaction section. So far, feasibility of the pre-concentration was experimentally verified and also, by flowsheet analysis, the importance was clarified of improving the performance of membrane and electrode catalyst.

Oral presentation

Hydrogen production with high-temperature gas-cooled reactors, 5; Electrolytic HI concentration for thermochemical water-splitting iodine-sulfur process

Yoshida, Mitsunori; Okuda, Hiroyuki; Hodotsuka, Masatoshi; Kubo, Shinji; Onuki, Kaoru; Hino, Ryutaro

no journal, , 

no abstracts in English

Oral presentation

Hydrogen production with high-temperature gas-cooled reactors, 6; Vapor-Liquid equilibrium of HI solution for the thermochemical IS process

Hodotsuka, Masatoshi; Okuda, Hiroyuki; Yoshida, Mitsunori; Kubo, Shinji; Onuki, Kaoru; Hino, Ryutaro

no journal, , 

no abstracts in English

Oral presentation

Hydrogen production with high-temperature gas-cooled reactors, 3; Vapor-liquid equilibrium of HI solution for thermochemical IS process

Hodotsuka, Masatoshi; Yang, X.*; Okuda, Hiroyuki; Kubo, Shinji; Onuki, Kaoru; Hino, Ryutaro

no journal, , 

no abstracts in English

Oral presentation

Hydrogen production with high-temperature gas-cooled reactors, 1; Vapor pressure measurement of HI solution for thermochemical IS process

Okuda, Hiroyuki; Hodotsuka, Masatoshi; Kubo, Shinji; Onuki, Kaoru

no journal, , 

Vapor pressure of hydroiodic acid is necessary for design of distillation column, which is important for improvement of thermal efficiency of IS process. In general, vapor pressure is significant data for getting gas-liquid equilibrium data or azeotropic data, which are necessary for design and operation of distillation separation process. However, the vapor pressure of hydroiodic acid has not almost been known, because it is difficult to design a measurement apparatus to use the corrosive-resistant material for hydroiodic acid such as tantalum, Teflon, and the resisting pressure glass. So, we sellect synthetic method in the measurement method at high pressure such as circulation method, currency method, and static method. Synthetic method has simple structure andsuitable for the measurement of high corrosive material such as supercritical water at high pressure.

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