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Journal Articles

Sodium-cooled Fast Reactors

Ohshima, Hiroyuki; Morishita, Masaki*; Aizawa, Kosuke; Ando, Masanori; Ashida, Takashi; Chikazawa, Yoshitaka; Doda, Norihiro; Enuma, Yasuhiro; Ezure, Toshiki; Fukano, Yoshitaka; et al.

Sodium-cooled Fast Reactors; JSME Series in Thermal and Nuclear Power Generation, Vol.3, 631 Pages, 2022/07

This book is a collection of the past experience of design, construction, and operation of two reactors, the latest knowledge and technology for SFR designs, and the future prospects of SFR development in Japan. It is intended to provide the perspective and the relevant knowledge to enable readers to become more familiar with SFR technology.

Journal Articles

Prevention of powder adhesion on substrate using nanoparticle coating

Suzuki, Michitaka*; Yoshikawa, Mao*; Iimura, Kenji*; Satone, Hiroshi*; Ishii, Katsunori

Funtai Kogakkai-Shi, 50(6), p.405 - 409, 2013/06

The glass substrate is coated by the silica nanoparticle suspension using dipping or spin coat method and dried in an electric oven. The glass substrate surface is covered with nanoparticle thin layer and the transparent and tiny rugged surface can be produced on a substrate. It was experimentally confirmed to prevent dust adhesion by covering the surface of the glass substrate with nanoparticle. The adhesion force between particle and substrate is measured by the centrifugal method and the relation between the adhesion force and the surface roughness is discussed from experimental and theoretical point of view. The measured and calculated results by Van der Waals force show that adhesion force decreased with the increment of the surface roughness. From the results, nanoparticle coating is very effective to prevent the dust adhesion on the substrate and the various application of nanoparticle coating can be expected.

JAEA Reports

Plan and reports of coupled irradiation (JRR-3 and JOYO of research reactors) and hot facilities work (WASTEF, JMTR-HL, MMF and FMF); R&D project on irradiation damage management technology for structural materials of long-life nuclear plant

Matsui, Yoshinori; Takahashi, Hiroyuki; Yamamoto, Masaya; Nakata, Masahito; Yoshitake, Tsunemitsu; Abe, Kazuyuki; Yoshikawa, Katsunori; Iwamatsu, Shigemi; Ishikawa, Kazuyoshi; Kikuchi, Taiji; et al.

JAEA-Technology 2009-072, 144 Pages, 2010/03

JAEA-Technology-2009-072.pdf:45.01MB

"R&D Project on Irradiation Damage Management Technology for Structural Materials of Long-life Nuclear Plant" was carried out from FY2006 in a fund of a trust enterprise of the Ministry of Education, Culture, Sports, Science and Technology. The coupled irradiations or single irradiation by JOYO fast reactor and JRR-3 thermal reactor were performed for about two years. The irradiation specimens are very important materials to establish of "Evaluation of Irradiation Damage Indicator" in this research. For the acquisition of the examination specimens irradiated by the JOYO and JRR-3, we summarized about the overall plan, the work process and the results for the study to utilize these reactors and some facilities of hot laboratory (WASTEF, JMTR-HL, MMF and FMF) of the Oarai Research-and-Development Center and the Nuclear Science Research Institute in the Japan Atomic Energy Agency.

Journal Articles

Remote maintenance technology for a large scale Hot Laboratory

Sakamoto, Naoki; Yoshikawa, Katsunori; Kushida, Naoya; Katsuyama, Kozo; Nagamine, Tsuyoshi

Proceedings of 46th Annual Meeting of "Hot Laboratories and Remote Handling" Working Group (HOTLAB 2009) (CD-ROM), 5 Pages, 2009/09

The large-scale post irradiation examination facility for fast breeder reactor fuel assemblies has been operated since 1978 in JAEAs Oarai Research and Development Center. The facility has several hot cells and irradiated fuel assemblies are dismantled in the examination cell which is 6 m in length, 19.5 m in width and 7 m in height. Remote maintenance technology for use in the hot laboratory was established using electromechanical manipulators, in-cell cranes and a repair hoist system installed in the examination cell. The test equipment which is used for post irradiation examinations can be repaired using the electromechanical manipulators and in-cell cranes by remote handling. In addition, the electromechanical manipulators and in-cell cranes are designed to permit self-repair using the repair hoist system in the cell by remote handling.

Journal Articles

Applying the remote maintenance technology to the large scale hot laboratory

Sakamoto, Naoki; Yoshikawa, Katsunori; Kushida, Naoya; Nakamura, Yasuo; Sukegawa, Kiyoshi*

Nihon Hozen Gakkai Dai-5-Kai Gakujutsu Koenkai Yoshishu, p.226 - 230, 2008/07

no abstracts in English

JAEA Reports

Re-assembly technology establishment of Material Testing Rig with Temperature Control (MARICO-2)

Abe, Kazuyuki; Kobayashi, Takashi*; Kajima, Hisashi*; Yoshikawa, Katsunori; Nagamine, Tsuyoshi; Nakamura, Yasuo

JAEA-Technology 2008-008, 53 Pages, 2008/03

JAEA-Technology-2008-008.pdf:19.28MB

MARICO-2 is a Testing Rig for the continuous irradiation examination of ODS ferrite steel etc.. It was necessary to re-assemble of MARICO-2 in Fuel Monitoring Facility (FMF). However, MARICO-2 is not applicable a past technology of re-assembly because it is a Rig of the total length about 11 m and its hex-tube must be welded by remote control. Then, MARICO-2 re-assembly technology development was executed, the device was designed, it produced, and the procedure of re-assembly by remote control was established.

Journal Articles

Progress in physics and technology developments for the modification of JT-60

Tamai, Hiroshi; Matsukawa, Makoto; Kurita, Genichi; Hayashi, Nobuhiko; Urata, Kazuhiro*; Miura, Yushi; Kizu, Kaname; Tsuchiya, Katsuhiko; Morioka, Atsuhiko; Kudo, Yusuke; et al.

Plasma Science and Technology, 6(1), p.2141 - 2150, 2004/02

 Times Cited Count:2 Percentile:6.52(Physics, Fluids & Plasmas)

The dominant issue for the the modification program of JT-60 (JT-60SC) is to demonstrate the steady state reactor relevant plasma operation. Physics design on plasma parameters, operation scenarios, and the plasma control method are investigated for the achievement of high-$$beta$$. Engineering design and the R&D on the superconducting magnet coils, radiation shield, and vacuum vessel are performed. Recent progress in such physics and technology developments is presented.

Journal Articles

Objectives and design of the JT-60 superconducting tokamak

Ishida, Shinichi; Abe, Katsunori*; Ando, Akira*; Chujo, T.*; Fujii, Tsuneyuki; Fujita, Takaaki; Goto, Seiichi*; Hanada, Kazuaki*; Hatayama, Akiyoshi*; Hino, Tomoaki*; et al.

Nuclear Fusion, 43(7), p.606 - 613, 2003/07

no abstracts in English

Journal Articles

Objectives and design of the JT-60 superconducting tokamak

Ishida, Shinichi; Abe, Katsunori*; Ando, Akira*; Cho, T.*; Fujii, Tsuneyuki; Fujita, Takaaki; Goto, Seiichi*; Hanada, Kazuaki*; Hatayama, Akiyoshi*; Hino, Tomoaki*; et al.

Nuclear Fusion, 43(7), p.606 - 613, 2003/07

 Times Cited Count:33 Percentile:69.18(Physics, Fluids & Plasmas)

no abstracts in English

Oral presentation

R&D project on irradiation damage management technology for structural materials of long-life nuclear plant, 2; Plan and execution of coupling irradiation (JRR-3 and JOYO) and Hot facilities work (WASTEF, JMTR-HL, MMF and FMF)

Matsui, Yoshinori; Nabeya, Hideaki; Kusunoki, Tsuyoshi; Takahashi, Hiroyuki; Aizawa, Masao; Nakata, Masahito; Numata, Masami; Usami, Koji; Endo, Shinya; Ito, Kazuhiro; et al.

no journal, , 

We are proceeding with the study of "R&D Project on Irradiation Damage Management Technology for Structural Materials of Long-life Nuclear Plant". For the study, it is important that the irradiated specimens are gotten by the coupling of JRR-3 and JOYO. This reports the total irradiation plan in the study, and the executed work for the coupling irradiation (JRR-3 and JOYO) including the Hot facilities work of Tokai and Oarai in the 2006 fiscal year.

Oral presentation

Development of safety review method for hot laboratories, 3; Remote maintenance techniques for hot laboratories

Sakamoto, Naoki; Yoshikawa, Katsunori; Kushida, Naoya; Nagamine, Tsuyoshi; Sukegawa, Kiyoshi*

no journal, , 

no abstracts in English

Oral presentation

R&D project on irradiation damage management technology for structural materials of long-life nuclear plant, 2; Reports of coupling irradiation (JRR-3 and JOYO) and hot facilities work (WASTEF, JMTR-HL, MMF and FMF)

Matsui, Yoshinori; Takahashi, Hiroyuki; Ichise, Kenichi; Usami, Koji; Endo, Shinya; Iwamatsu, Shigemi; Yonekawa, Minoru; Ito, Kazuhiro; Yamamoto, Masaya; Soga, Tomonori; et al.

no journal, , 

"R&D Project on Irradiation Damage Management Technology for Structural Materials of Long-life Nuclear Plant" was carried out from 2006 fiscal year in a fund of a trust enterprise of the Ministry of Education, Culture, Sports, Science and Technology. The coupling irradiations or single irradiations by JOYO fast reactor and JRR-3 fission reactor were performed for about two years. The irradiation specimens are the very important materials to establish of "Evaluation of Irradiation Damage Indicator" in this research. For the acquisition of the examination specimens irradiated by the JOYO and JRR-3, we will present about the overall plan, work process and the results for the study to utilize these reactors and some facilities of hot laboratory (WASTEF, JMTR-HL, MMF and FMF) of the Oarai Research-and-Development Center and the Nuclear Science Research Institute in the Japan Atomic Energy Agency.

Oral presentation

R&D project on irradiation damage management technology for structural materials of long-life nuclear plant, 3; Assembly and disassembly techniques of JRR-3 re-irradiation capsule in WASTEF

Usami, Koji; Ichise, Kenichi; Numata, Masami; Endo, Shinya; Onozawa, Atsushi; Takahashi, Hiroyuki; Kikuchi, Taiji; Ishikawa, Kazuyoshi; Yoshikawa, Katsunori; Nakata, Masahito; et al.

no journal, , 

In the R&D Project on Irradiation Damage Management Technology for Structural Materials of Long-life Nuclear Plant, the specimens to be obtained by coupling irradiation between JOYO and JRR-3 is necessary to establish the evaluation method by using the irradiation damage indicator of them. Therefore, the techniques for assembling of JRR-3 re-irradiation capsule in the Waste Safety Testing Facility (WASTEF) were developed to perform the coupling irradiation. The techniques contributed to the first coupling irradiation in the world.

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