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Tanaka, Kosuke; Sato, Isamu*; Onishi, Takashi; Ishikawa, Takashi; Hirosawa, Takashi; Katsuyama, Kozo; Seino, Hiroshi; Ohno, Shuji; Hamada, Hirotsugu; Tokoro, Daishiro*; et al.
Journal of Nuclear Materials, 536, p.152119_1 - 152119_8, 2020/08
Times Cited Count：0 Percentile：0.01(Materials Science, Multidisciplinary)In order to obtain the release rate coefficients from fuels for fast reactors (FRs), heating tests and the subsequent analyses of the fission products (FPs) and actinides that are released were carried out using samples of uranium-plutonium mixed oxide (MOX) fuel pellets irradiated at the experimental fast reactor Joyo. Three heating tests targeting temperatures of 2773, 2973 and 3173 K were conducted using an FP release behavior test apparatus equipped with a high-frequency induction furnace and solid FP sampling systems consisting of a thermal gradient tube (TGT) and filters. Irradiated fuel pellets were placed into a tungsten crucible, then loaded into the induction furnace. The temperature was raised continuously at a heating rate of 10 K/s to the targeted temperature and maintained for 500 s in a flowing argon gas atmosphere. The FPs and actinides released from the MOX fuels and deposited in the TGT and filters were quantified by gamma-ray spectrometry and inductively coupled plasma mass spectrometry (ICP-MS) analysis. Based on the analysis, the release rates of radionuclides from MOX fuels for FR were obtained and compared with literature data for light water reactor (LWR) fuels. The release rate coefficients of FPs obtained in this study were found to be similar to or lower than the literature values for LWR fuels. It was also found that the release rate coefficient data for actinides were within the range of variation of literature values for LWR fuels.
Sakuraba, Naotoshi; Numata, Masami; Komiya, Tomokazu; Ichise, Kenichi; Nishi, Masahiro; Tomita, Takeshi; Usami, Koji; Endo, Shinya; Miyata, Seiichi; Kurosawa, Tatsuya; et al.
JAEA-Technology 2009-071, 34 Pages, 2010/03
JAEA-Technology-2009-071.pdf:21.07MB
As a part of maintenance technology of a large-sized glove box for handling of TRU nuclides, we developed replacement technology for front acrylic panels using the bag-in/bag-out method and applied this technology to replace the deteriorated front acrylic panels at Waste Safety Testing Facility (WASTEF) in Nuclear Science Research Institute of Japan Atomic Energy Agency (JAEA). As a consequence, we could safely replace the front acrylic panels under the condition of continuous negative pressure only with partial decontamination of the glove box. We also demonstrated that the present technology is highly effective in points of safety, workability and cost as compared to the usual replacement technology for front acrylic panels of a glove box, where workers in an air-line suit replace directly the front acrylic panels in a green house.
Oba, Toshihiro; Inoue, Hiromi*; Kikuchi, Taiji; Taka, Isamu; Chiba, Masaaki; Ishikawa, Kazuyoshi; Tsuda, Kazumi*; Takeyama, Tomonori; Isozaki, Futoshi*; Terunuma, Isao*; et al.
NIFS-MEMO-36, p.121 - 124, 2002/06
no abstracts in English
Oba, Toshihiro; Kikuchi, Taiji; Taka, Isamu; Isozaki, Futoshi*; Chiba, Masaaki; Ishikawa, Kazuyoshi; Inoue, Hiromi*; Terunuma, Isao*; Sawabe, Masaki*; Tsuda, Kazumi*; et al.
JAERI-Tech 2001-067, 29 Pages, 2001/11
JAERI-Tech-2001-067.pdf:1.93MB
no abstracts in English
Takehisa, Masaaki*; Tagawa, Seiichi*; Kashiwagi, Masayuki*; Tominaga, Hiroshi*; Ishikawa, Isamu*; Ooka, Norikazu; Kamada, Toshimitsu*; Hosobuchi, Kazunari*; Makuuchi, Keizo; Takeshita, Hidefumi; et al.
Genshiryoku Riyo No Keizai Kibo; NSA/Commentaries, No.9, 139 Pages, 2001/01
no abstracts in English
Minato, Kazuo; Ogawa, Toru; Sawa, Kazuhiro; Sekino, Hajime; Koya, Toshio; Kitagawa, Isamu; Ishikawa, Akiyoshi; Tomita, Takeshi;
Proc. of the Int. Conf. on Future Nuclear Systems (GLOBAL'99)(CD-ROM), 8 Pages, 1999/00
no abstracts in English
Ishikawa, Isamu
Radioisotopes, 46(9), p.657 - 663, 1997/09
no abstracts in English
Ishikawa, Isamu
Radioisotopes, 46(8), p.567 - 572, 1997/08
no abstracts in English
Ishikawa, Isamu
Radioisotopes, 45(10), p.646 - 651, 1996/10
no abstracts in English
Ishikawa, Isamu
Proc. of 11th KAIF/KNS Annual Conf., 0, p.611 - 619, 1996/00
no abstracts in English
Ishikawa, Isamu
Radioisotopes, 45(5), p.349 - 350, 1996/00
no abstracts in English
*; *; *; ; Ishikawa, Isamu
Proc. of 2nd Int. Topical Meeting on Neutron Radiography System Design and Characterization, 0, p.335 - 342, 1995/00
no abstracts in English
Tsukada, Takashi; Shiba, Kiyoyuki; Nakajima, Hajime; ; Kitagawa, Isamu; ; Sekino, Hajime; ; Itonaga, Fumio; Ishikawa, Akiyoshi
JAERI-M 92-169, 26 Pages, 1992/11
no abstracts in English
Shiba, Kiyoyuki; Tsukada, Takashi; Nakajima, Hajime; ; Kitagawa, Isamu; ; Sekino, Hajime; ; ; Itonaga, Fumio; et al.
JAERI-M 92-166, 27 Pages, 1992/11
no abstracts in English
Tominaga, Hiroshi; Ishikawa, Isamu
Nucl. Geophys., 5(1-2), p.137 - 140, 1991/00
no abstracts in English
Genka, Tsuguo; Kobayashi, Katsutoshi; Takeuchi, Norio; Ishikawa, Isamu; Hoizumi, Kiyoshi
Radioisotopes, 37(3), p.155 - 158, 1988/00
no abstracts in English
Ishikawa, Isamu; Tachikawa, Noboru; Okubo, Makio; Tominaga, Hiroshi
Transactions of the American Nuclear Society, 56(SUPPL.3), p.31 - 32, 1988/00
no abstracts in English
Niwa, Hajime; Kurisaka, Kenichi; Sato, Ikken; Tobita, Yoshiharu; Kamiyama, Kenji; Yamano, Hidemasa; Miyahara, Shinya; Ohno, Shuji; Seino, Hiroshi; Ishikawa, Hiroyasu; et al.
no journal, ,
In order to develop the core damage evaluation technology (level 2 PSA) for sodium-cooled fast reactors, we develop the new analysis codes of post accident material relocation phase and of ex-vessel events, and we develop the technical bases that is necessary for level 2 PSA. In this presentation, summary and scope of the entire study is introduced as a part of the 4 series presentations.
Seino, Hiroshi; Ohno, Shuji; Ishikawa, Hiroyasu; Nishimura, Masahiro; Sato, Isamu; Miyahara, Shinya
no journal, ,
no abstracts in English
Nakai, Ryodai; Kurisaka, Kenichi; Sato, Ikken; Tobita, Yoshiharu; Kamiyama, Kenji; Yamano, Hidemasa; Miyahara, Shinya; Ohno, Shuji; Seino, Hiroshi; Ishikawa, Hiroyasu; et al.
no journal, ,
To develop a core damage evaluation technology (level-2 PSA) in sodium-cooled fast reactors, a new analysis method is developed for core-material relocation phase and internal containment vessel event. This study also develop technical basis necessary for the level-2 PSA.
