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Journal Articles

Cause investigation for thinning of anchor bolts and gaps between anchor bolt nuts and a flange plate at the JMTR Hot Laboratory exhaust stack

Shibata, Akira; Kitagishi, Shigeru; Watashi, Katsumi; Matsui, Yoshinori; Omi, Masao; Sozawa, Shizuo; Naka, Michihiro

Nihon Hozen Gakkai Dai-13-Kai Gakujutsu Koenkai Yoshishu, p.290 - 297, 2016/07

The exhaust stack of Japan Materials Testing Reactor Hot laboratory is a part of gaseous waste treatment system. It was built in 1970 and is 40 m in height. In 2015, thinning was found at some anchor bolts on base of the stack. When thinning of anchor bolts were investigated, gaps between anchor bolt nuts and flange plate was found. JAEA removed steel cylinder of stack which is 33 m in height for safety. In the end of investigation, thinning was found in all anchor bolts of the stack. Cause investigation for the thinning and the gaps were performed. It is concluded that the thinning was caused by water infiltration over a long period of time and the gaps were caused by elongation of thinning part of anchor bolts by the 2011 earthquake off the Pacific coast of Tohoku.

JAEA Reports

Laboratory testing of rock core samples from pre-excavation grouting area at Mizunami Underground Research Laboratory

Uyama, Masao*; Hitomi, Takashi*; Nakashima, Satoru*; Sato, Toshinori; Sanada, Hiroyuki; Aoyagi, Yoshiaki

JAEA-Research 2015-010, 67 Pages, 2015/10

JAEA-Research-2015-010.pdf:32.34MB
JAEA-Research-2015-010-appendix(CD-ROM).zip:528.25MB

Japan Atomic Energy Agency has been conducting a research project on (Grouting Technology Development for the Radioactive Waste Repository) funded by Ministry of Economy, Trade and Industry (METI), Japan. As a part of the project, various investigations were carried out in the -200m Refuge Niche where pre-excavation grouting was performed and the distribution of the injected grouting material, also the effectiveness of grouting penetration for reduction of groundwater inflow were confirmed As the continuation of these investigations, chemical influences of grouting material on the rock mass were determined through (Laboratory testing of rock core samples from pre-excavation grouting area at Mizunami Underground Research Laboratory). Specifically, core samples were obtained by check boring at where infiltration solidification of the grouting material was expected, and X-ray florescent analysis and Transmission Electron Microscope observation were performed focused on the contact parts of the grouting material and rock mass in fractures. As a result, the chemical influences of grouting material on the rock mass were identified.

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

Investigation methodology for influence of cement material from grouting origin to granite

Uyama, Masao*; Hitomi, Takashi*; Sato, Toshinori

Doboku Gakkai Heisei-25-Nendo Zenkoku Taikai Dai-68-Kai Nenji Gakujutsu Koenkai Koen Gaiyoshu (DVD-ROM), 2 Pages, 2013/09

no abstracts in English

Journal Articles

Observation of granite influenced by cement material from grouting origin

Hitomi, Takashi*; Uyama, Masao*; Sato, Toshinori

Doboku Gakkai Heisei-25-Nendo Zenkoku Taikai Dai-68-Kai Nenji Gakujutsu Koenkai Koen Gaiyoshu (DVD-ROM), 2 Pages, 2013/09

no abstracts in English

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.

Journal Articles

Development of in-pile instruments for fuel and material irradiation tests

Shibata, Akira; Kitagishi, Shigeru; Kimura, Nobuaki; Saito, Takashi; Nakamura, Jinichi; Omi, Masao; Izumo, Hironobu; Tsuchiya, Kunihiko

JAEA-Conf 2011-003, p.185 - 188, 2012/03

To get measurement data with high accuracy for fuel and material behavior studies in irradiation tests, two kinds of measuring equipments have been developed; these are the Electrochemical Corrosion Potential (ECP) sensor, the Linear Voltage Differential Transformer (LVDT) type gas pressure gauge. The ECP sensor has been developed to determine the corrosive potential under high temperature and high pressure water condition. The structure of the joining parts was optimized to avoid stress concentration. The LVDT type gas pressure gauge has been developed to measure gas pressure in a fuel element during neutron irradiation. To perform stable measurements with high accuracy under high temperature, high pressure and high dosed environment, the coil material of LVDT was changed to MI cable. As a result of this development, the LVDT type gas pressure gauge showed high accuracy at 1.8% of a full scale, and good stability.

Journal Articles

Development of remote welding techniques for in-pile IASCC capsules and evaluation of material integrity on capsules for long irradiation period

Shibata, Akira; Nakano, Junichi; Omi, Masao; Kawamata, Kazuo; Nakagawa, Tetsuya; Tsukada, Takashi

Journal of Nuclear Materials, 422(1-3), p.14 - 19, 2012/03

 Times Cited Count:0 Percentile:0.01(Materials Science, Multidisciplinary)

To simulate Irradiation assisted stress corrosion cracking (IASCC) behavior by in-pile experiments, it is necessary to irradiate specimens up to a neutron fluence that is higher than the IASCC threshold fluence. Pre-irradiated specimens must be relocated from pre-irradiation capsules to in-pile capsules. Hence, a remote welding machine has been developed. And the integrity of capsule housing for a long term irradiation was evaluated by tensile tests in air and slow strain rate tests in water. Two type specimens were prepared. Specimens were obtained from the outer tubes of capsule irradiated to 1.0-3.9 $$times$$ 10$$^{26}$$ n/m$$^{2}$$ (E$$>$$ 1 MeV). And specimens were irradiated in a leaky capsule to 0.03-1.0 $$times$$ 10$$^{26}$$ n/m$$^{2}$$. Elongation more than 15% in tensile test at 423 K was confirmed and no IGSCC fraction was shown in SSRT at 423 K which was estimated as temperature at the outer tubes of the capsule under irradiation.

Journal Articles

Technical development for in-pile IASCC growth tests by using a 0.5T-CT specimen in JMTR

Chimi, Yasuhiro; Shibata, Akira; Ise, Hideo; Kasahara, Shigeki; Kawaguchi, Yoshihiko*; Nakano, Junichi; Omi, Masao; Nishiyama, Yutaka

Proceedings of Enlarged Halden Programme Group Meeting 2011 (CD-ROM), 10 Pages, 2011/10

In order to load a large specimen of 0.5T-CT up to a high stress intensity factor of $$sim$$30 MPa$$sqrt{m}$$, we have adopted a lever type loading unit for in-pile irradiation-assisted stress corrosion crack (IASCC) growth tests in the Japan Materials Testing Reactor (JMTR). In this unit, the applied load is generated by shrinking a bellows with lower inner gas pressure than surrounding water pressure and enlarged by leverage. The crack length of the specimen is monitored by potential drop method (PDM) using mineral insulator (MI) cables. In this paper, technical concerns of the in-pile crack growth test unit, especially the estimation procedure of applied load to the specimen inside the irradiation capsule and the evaluation of precision of the PDM signals are presented.

JAEA Reports

Neutron shielding reinforcement in the JMTR Hot Laboratory

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.

JAEA Reports

Establishment of experimental equipments in irradiation technology development building

Ishida, Takuya; Tanimoto, Masataka; Shibata, Akira; Kitagishi, Shigeru; Saito, Takashi; Omi, Masao; Nakamura, Jinichi; Tsuchiya, Kunihiko

JAEA-Testing 2011-001, 44 Pages, 2011/06

JAEA-Testing-2011-001.pdf:4.52MB

The Neutron Irradiation and Testing Reactor Center has developed new irradiation technologies to provide irradiation data with high technical value for the refurbishment and resume of the Japan Materials Testing Reactor (JMTR). For the purpose to perform assembling of capsules, materials tests, materials inspection and analysis of irradiation specimens for the development of irradiation capsules, improvement and maintenance of facilities were performed. The RI application development building was refurbished and maintained for above-mentioned purpose. After refurbishment, the building was named Irradiation Technology Development Building. It contains eight laboratories based on the purpose of use, and experimental apparatuses were installed. This report describes the refurbishment work of the RI application development building, the installation work and operation method of the experimental apparatuses and the basic management procedure of the Irradiation Technology Development Building.

JAEA Reports

Development of groundwater treatment method using radiation-induced graft polymerization adsorbent at the Mizunami Underground Research Laboratory; Annual report for 2008 fiscal year (Joint research)

Iyatomi, Yosuke; Hoshina, Hiroyuki; Seko, Noriaki; Shimada, Akiomi; Ogata, Nobuhisa; Sugihara, Kozo; Kasai, Noboru; Ueki, Yuji; Tamada, Masao

JAEA-Technology 2010-045, 10 Pages, 2011/02

JAEA-Technology-2010-045.pdf:1.16MB

The concentrations of fluorine (7.2-10 mg/L) and boron (0.8-1.5 mg/L) dissolved in groundwater pumped from the shafts during excavation of the Mizunami Underground Research Laboratory (MIU), Tono Geoscience Centre, must be reduced to the levels below the environmental standards for fluorine: 0.8mg/L and boron: 1 mg/L. As well, collaborative research on groundwater treatment to remove fluorine and boron started in 2006 between the Environmental and Industrial Materials Research Division, Quantum Beam Science Directorate and the Tono Geoscientific Research Unit, Geological Isolation Research and Development Directorate. This is because the Quantum Beam Science Directorate has synthesized fibrous adsorbents with radiation-induced graft polymerization and applied adsorbents to collect rare metals dissolved in hot springs and sea water. The results of previous testing indicate that the adsorbent was able to remove more than 95% of the boron and fluorine and that performance of adsorbent for boron removal was better than the performance using ion-exchange resin. It was also apparent that the pH of groundwater had an influence on the performance of the adsorbent with respect to boron removal. Therefore we reran the recycling test using groundwater from the neutralization tank at the groundwater treatment facility. The results indicated that the performance of the adsorbent using neutral groundwater for boron removal was higher than using uncontrolled groundwater. However the bed volume (BV) with recycled adsorbent decreased compared to first use. It is thought that sulfur added at the groundwater treatment facility was retained by the adsorbent despite elution, and affected the performance such that repeat usage resulted in decreased efficiency. In addition, it is considered that the goals established in the first year compared to the results obtained to date, including the status of waste water treatment at the MIU, and summarized the results in this 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

Development of measuring instruments for material irradiation tests

Kitagishi, Shigeru; Tanimoto, Masataka; Iimura, Koichi; Inoue, Shuichi; Saito, Takashi; Omi, Masao; Tsuchiya, Kunihiko

JAEA-Review 2010-046, 19 Pages, 2010/11

JAEA-Review-2010-046.pdf:2.51MB

The Japan Materials Testing Reactor (JMTR) has been utilized for the various neutron irradiation tests of fuels and materials, as well as for radioisotope production since achieving the first criticality in March 1968. The operation of JMTR was halted for the refurbishment in August 2006. The new JMTR is expected to contribute to many fields: the lifetime extension of LWRs and the expansion of industry use. To meet a wide range of users' needs, the development of new irradiation technologies has been carried out for the new JMTR. This report summarizes the present conditions of the development of FP gas pressure gauges, multi-paired thermocouples, ECP and ceramics sensors.

Journal Articles

Removal of fluorine and boron from groundwater using radiation-induced graft polymerization adsorbent at Mizunami Underground Research Laboratory

Iyatomi, Yosuke; Hoshina, Hiroyuki; Seko, Noriaki; Kasai, Noboru; Ueki, Yuji; Tamada, Masao

Proceedings of 13th International Conference on Environmental Remediation and Radioactive Waste Management (ICEM 2010) (CD-ROM), p.485 - 490, 2010/10

Journal Articles

Investigations to increase the efficiency of fluorine and boron removal from groundwater using radiation-induced graft polymerization adsorbent

Iyatomi, Yosuke; Hoshina, Hiroyuki; Seko, Noriaki; Shimada, Akiomi; Ogata, Nobuhisa; Sugihara, Kozo; Kasai, Noboru; Ueki, Yuji; Tamada, Masao

Nihon Genshiryoku Gakkai Wabun Rombunshi, 9(3), p.330 - 338, 2010/09

The Mizunami Underground Research Laboratory (MIU) Project is a research project investigating the deep underground environment within crystalline rock being conducted by JAEA. The concentrations of fluorine and boron dissolved in groundwater pumped from shafts during excavation of geoscientific studies at MIU, are reduced to the levels below the environmental standards at a water treatment facility. Coagulation treatment and ion exchange treatment are applied for fluorine and boron respectively. So we have started to research on efficient groundwater treatment for fluorine and boron using radiation-induced graft polymerization adsorbent. Regarding the treatment for boron, the processing that about 12 times were faster than the general ion exchange resin was possible and the use of the adsorbent was possible repeatedly. In addition, it developed that the pH of the underground water gave adsorption performance of adsorbent influence. With respect to fluorine removal, fluorine adsorption more than 90% was able to confirm by the adsorbent, but low value in comparison with boron. As the reason, a difference of the concentration of fluorine and boron in groundwater is thought about. It is necessary to grasp the concentration which adsorption performance can show enough.

Journal Articles

Evaluation of graft adsorbent with N-methyl-D-glucamine for boron removal from groundwater

Hoshina, Hiroyuki; Seko, Noriaki; Ueki, Yuji; Tamada, Masao; Iyatomi, Yosuke

Nihon Ion Kokan Gakkai-Shi, 21(3), p.153 - 156, 2010/09

Journal Articles

Recent progress in the energy recovery linac project in Japan

Sakanaka, Shogo*; Akemoto, Mitsuo*; Aoto, Tomohiro*; Arakawa, Dai*; Asaoka, Seiji*; Enomoto, Atsushi*; Fukuda, Shigeki*; Furukawa, Kazuro*; Furuya, Takaaki*; Haga, Kaiichi*; et al.

Proceedings of 1st International Particle Accelerator Conference (IPAC '10) (Internet), p.2338 - 2340, 2010/05

Future synchrotron light source using a 5-GeV energy recovery linac (ERL) is under proposal by our Japanese collaboration team, and we are conducting R&D efforts for that. We are developing high-brightness DC photocathode guns, two types of cryomodules for both injector and main superconducting (SC) linacs, and 1.3 GHz high CW-power RF sources. We are also constructing the Compact ERL (cERL) for demonstrating the recirculation of low-emittance, high-current beams using above-mentioned critical technologies.

JAEA Reports

Renewal plan of the JMTR Hot Laboratory for the irradiation test of high burn-up fuels in FY2008

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.

JAEA Reports

Renewal plan of the JMTR Hot Laboratory for the Irradiation test of high burn-up fuels in FY2007

Sozawa, Shizuo; Nakagawa, Tetsuya; Omi, Masao; Hayashi, Koji; Iwamatsu, Shigemi; Kawamata, Kazuo; Kato, Yoshiaki; Kanazawa, Yoshiharu

JAEA-Technology 2009-069, 32 Pages, 2010/03

JAEA-Technology-2009-069.pdf:7.33MB

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) strengthening JMTR hot-lab. cell-shielding, (2) the capsule assembling device, (3) domestic transportation cask, (4) fuel-rod center-hole processing device, (5) master-slave manipulators, (6) power manipulator, and (7) scanning electron microscope.

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