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JAEA Reports

Design and production of the valve used in Radioactive Liquid Disposal Facility

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.

JAEA Reports

Assessment of the probability of aircraft crashing for HTTR

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$$times$$10$$^{-8}$$, which is lower than the assessment criteria 10$$^{-7}$$.

JAEA Reports

Validation of repairing method for concrete wall of the JMTR tank-yard building

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.

Journal Articles

Improvement of plant reliability based on combining of prediction and inspection of crack growth due to intergranular stress corrosion cracking

Uchida, Shunsuke; Chimi, Yasuhiro; Kasahara, Shigeki; Hanawa, Satoshi; Okada, Hidetoshi*; Naito, Masanori*; Kojima, Masayoshi*; Kikura, Hiroshige*; Lister, D. H.*

Nuclear Engineering and Design, 341, p.112 - 123, 2019/01

 Times Cited Count:4 Percentile:56.51(Nuclear Science & Technology)

Improvement of plant reliability based on reliability-centered-maintenance (RCM) is going to be undertaken in NPPs. RCM is supported by risk-based maintenance (RBM). The combination of prediction and inspection is one of the key issues to promote RBM. Early prediction of IGSCC occurrence and its propagation should be confirmed throughout the entire plant systems which should be accomplished by inspections at the target locations followed by timely application of suitable countermeasures. From the inspections, accumulated data will be applied to confirm the accuracy of the code, to tune some uncertainties of the key data for prediction, and then, to increase their accuracy. The synergetic effects of prediction and inspection on application of effective and suitable countermeasures are expected. In the paper, the procedures for the combination of prediction and inspection are introduced.

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).

Journal Articles

Development of the irradiation facility for simulating condition of light-water reactor

Kitagishi, Shigeru; Endo, Yasuichi; Okada, Yuji; Hanawa, Hiroshi; Matsui, Yoshinori

UTNL-R-0486, p.7_1 - 7_10, 2014/03

no abstracts in English

JAEA Reports

Development of safety management system for works in radiation controlled area (Joint research)

Hiyama, Kazuhisa; Hanawa, Nobuhiro; Kurosawa, Akihiko; Eguchi, Shohei; Hori, Naohiko; Kusunoki, Tsuyoshi; Ueda, Hisao; Shimada, Hiroshi; Kanda, Hiroaki*; Saito, Isamu*

JAEA-Technology 2013-045, 32 Pages, 2014/02

JAEA-Technology-2013-045.pdf:5.83MB

This report summarizes regarding to develop of real-time multifunctional access control system which is able to manage worker's access control and exposure dose at real-time in the reactor building, besides worker's location and worker might be fall down by accident.

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.

Journal Articles

Development of new irradiation facility for BWR safety research

Okada, Yuji; Magome, Hirokatsu; Iida, Kazuhiro; Hanawa, Hiroshi; Omi, Masao

UTNL-R-0483, p.10_4_1 - 10_4_10, 2013/03

In JAEA(Japan Atomic Energy Agency), about the irradiation embrittlement of the reactor pressure vessel and the stress corrosion cracking of reactor core composition apparatus concerning the long-term use of the light water reactor (BWR), in order to check the influence of the temperature, pressure, and water quality, etc on BWR condition. The water environmental control facility which performs irradiation assisted stress corrosion-cracking (IASCC) evaluation under BWR irradiation environment was fabricated in JMTR. (Japan Materials Testing Reactor). This report is described the outline of manufacture of the water environmental control facility for doing an irradiation test using the saturation temperature capsule after JMTR re-operation.

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

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 study of the material irradiation facility for the SCC research under the LWR irradiation environment

Onuma, Yuichi; Tomita, Kenji; Okada, Yuji; Hanawa, Hiroshi

JAEA-Technology 2009-034, 79 Pages, 2009/07

JAEA-Technology-2009-034.pdf:11.23MB

Toward the re-operation of Japan Materials Testing Reactor on 2011 F.Y., the construction of new material irradiation facility for the stress corrosion cracking research under the LWR irradiation environment had been planed, and the design study of water control unit for BWR and water chemical study which supply the LWR simulated water to the material irradiation capsule were carried out on 2007 F.Y. The design study of new material irradiation facility was examined including the reflection of the operation experience and the reuse of components on old material irradiation facility. These examination results were summarized in this report.

JAEA Reports

Verification on reliability of diaphragm seal

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.

JAEA Reports

Inspection of secondary cooling system piping of JMTR

Hanawa, Yoshio; Izumo, Hironobu; Fukasaku, Akitomi; Nagao, Yoshiharu; Kawamura, Hiroshi

JAEA-Review 2008-023, 55 Pages, 2008/06

JAEA-Review-2008-023.pdf:5.63MB

Piping condition was inspected form the view point of confirmation of long term utilization before renewal work of secondary cooling system in the JMTR on FY 2008. As the result, it was confirmed that crack, swelling and exfoliation in inner lining of piping could be observed, and corrosion in piping could hardly be observed. Repair of inner lining of piping during refurbishment of the JMTR is necessary to long term utilization of secondary cooling system after restart of the JMTR. In addition, periodic inspection of inner lining condition is necessary after repair of secondary cooling system piping.

JAEA Reports

Fabrication of irradiation capsule for IASCC irradiation tests, 3; Irradiation capsule for ECP sensor (Joint research)

Ide, Hiroshi; Izumo, Hironobu; Ishida, Takuya; Saito, Takashi; Hanawa, Satoshi; Matsui, Yoshinori; Iwamatsu, Shigemi; Kanazawa, Yoshiharu; Miwa, Yukio; Kaji, Yoshiyuki; et al.

JAEA-Technology 2008-013, 32 Pages, 2008/03

JAEA-Technology-2008-013.pdf:17.96MB

Dissolved oxygen ions and chlorine ions concentration have been used as an evaluation index of stress corrosion cracking behavior for the light water reactor materials. In addition to these parameters, Electrochemical Corrosion Potential (ECP) was commonly used as the evaluation. Therefore, as a part of the IASCC irradiation tests, the irradiation test of the iron oxide type and the platinum type of ECP sensor were carried out under the BWR coolant condition. As a result, some measurements of ECP sensor succeed. However, it was clear that the improvement of ECP sensor is necessary. In this report, developed irradiation capsule ECP sensor is reported.

JAEA Reports

Research and development for treatment and disposal technologies of TRU waste; JFY 2006 annual report

Kamei, Gento; Honda, Akira; Mihara, Morihiro; Oda, Chie; Murakami, Hiroshi; Masuda, Kenta; Yamaguchi, Kohei; Nakanishi, Hiroshi*; Sasaki, Ryoichi*; Ichige, Satoru*; et al.

JAEA-Research 2007-067, 130 Pages, 2007/09

JAEA-Research-2007-067.pdf:28.78MB

After the publication of the 2nd progress report of geological disposal of TRU waste in Japan, policy and general scheme of future study for the waste disposal in Japan was published by ANRE and JAEA. This annual report summarized aim and progress of individual problem, which was assigned into JAEA in the published policy and general scheme. The problems are as follows; characteristics of TRU waste and its geologic disposal, treatment and waste production, quality control and inspection methodology for waste, mechanical analysis of near-field, data acquisition and preparation on radionuclides migration, cementitious material transition, bentonite and rock alteration in alkaline solution, nitrate effect, performance assessment of the disposal system and decomposition of nitrate as an alternative technology.

Journal Articles

Development of in-pile capsule for IASCC study at JMTR

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).

Journal Articles

Construction of the J-PARC L3BT control system

Shen, G.; Watanabe, Kazuhiko*; Kato, Yuko; Sakaki, Hironao; Sako, Hiroyuki; Ito, Yuichi; Yoshikawa, Hiroshi; Hanawa, Katsushi*; Mizuno, Seiji*

Proceedings of 3rd Annual Meeting of Particle Accelerator Society of Japan and 31st Linear Accelerator Meeting in Japan (CD-ROM), p.364 - 366, 2006/00

The control system of J-PARC project is under construction. After almost finishing the hardware installation of the L3BT section, an online device commissioning was performed for magnet power supply, stepping motor and vacuum system. Many components for device control have already been developed separately, but not integrated together yet. It is the first experience to combine all the components, including core software for a front-end IO controller, an EPICS run-time database, and a remote graphic user interface. This paper describes the detail of the recent construction status of the L3BT control system, including component development, system integration, and device commissioning.

JAEA Reports

Study on Systematic Integration Technology of design and Safety Assessment for HLW geological Disposal(II)

Ishihara, Yoshinao*; Fukui, Hiroshi*; Sagawa, Hiroshi*; Ito, Takaya*; Matsunaga, Kenichi*; Kohanawa, Osamu*; Kuwayama, Yuki*

JNC TJ8400 2003-038, 41 Pages, 2003/02

JNC-TJ8400-2003-038.pdf:0.48MB

The present study was carried out relating to basic design of the "Geological Disposal Technology Integration System" that will be systematized as knowledge base for design analysis and safety assesment of HLW geological disposal system by integrating organically and hierarchically various technical information in three study field.

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