Fabrication of irradiation capsule for IASCC irradiation tests, 2; Irradiation capsule for crack propagation test (Joint research)

Ide, Hiroshi; Matsui, Yoshinori; Kawamata, Kazuo; Taguchi, Taketoshi; Kanazawa, Yoshiharu; Onuma, Yuichi; Watanabe, Hiroyuki; Inoue, Shuichi; Izumo, Hironobu; Ishida, Takuya; et al.

JAEA-Technology 2008-012, 36 Pages, 2008/03

JAEA-Technology-2008-012.pdf:10.09MB

It is known that Irradiation Assisted Stress Corrosion Cracking (IASCC) occurs when austenitic stainless steel components used for light water reactor (LWR) are irradiated for a long period. In order to evaluate the high aging of the nuclear power plant, the study of IASCC becomes the important problem. The specimens irradiated in the reactor were evaluated by post irradiation examination in the past study. For the appropriate evaluation of IASCC, It is necessary to test it under the simulated LWR conditions; temperature, water chemistry and irradiation conditions. In order to perform in-pile SCC test, saturated temperature capsule (SATCAP) was developed. There are crack growth test, crack propagation test and so on for in-pile SCC test. In this report, SATCAP for crack propagation test is reported.

Decommissioning program and future plan for research hot laboratory

Umino, Akira; Saito, Mitsuo; Kanazawa, Hiroyuki; Koya, Toshio; Okamoto, Hisato; Sekino, Hajime*; Nishino, Yasuharu

Dekomisshoningu Giho, (32), p.2 - 12, 2005/09

http://www.randec.or.jp/publish/documents/gihou/Decommissioning%20gihou_32.pdf

The Research Hot Laboratory (RHL) in Japan Atomic Research Institute (JAERI) was constructed in 1961, as the first one in JAPAN, to perform the examinations of irradiated fuels and materials. RHL with two floors and a basement consists of 10 heavy concrete cells, and 38 lead cells (20 lead cells at present). The RHL had been contributed to research program in JAERI. However, RHL is the one of target 'A middle-range decommissioning plan for the facility in Tokai Research Establishment' as the rationalization program for decrepit facilities in JAERI. Therefore, all PIEs had been finished in March 2003 and the dismantling works of hot cells have been started. The 18 lead cells had been dismantled. The examinations performed in RHL will be succeeded to the RFEF and the WASTEF. The partial area of RHL facility will be used for the temporary storage of un-irradiated fuel samples used for our previous research works and radioactive device generated in proton accelerator facility (called J-PARC).

Development of fission gas measurement technique in the irradiated fuel pellet

Hatakeyama, Yuichi; Sudo, Kenji; Kanazawa, Hiroyuki

JAERI-Tech 2004-033, 29 Pages, 2004/03

JAERI-Tech-2004-033.pdf:1.65MB

The amount of fission gas (Kr, Xe) in irradiated fuel pellet increases with extending the burn up and that exerts a serious influence upon thermal and mechanical properties of light water reactor fuel. Therefore, the accumulation of the data on the release behavior of fission gas is important in the investigation program of safety and reliability for extended burn up fuel. In the post irradiation examination at the Reactor Fuel Examination Facility in JAERI,the fission gas which released into the plenum region from UO pellet during irradiation has been measured by puncturing test of irradiated fuel rod. The results of puncturing test show the most of fission gas remained in the pellet. It can be seen that the additional release of fission gas might occur under higher burn up and accident conditions. To know the fission gas release behavior from irradiated fuel, the Out Gas analyzer(OGA)which has the performance to heat up the UO pellet stepwise up to 2300C and to measure the released fission gas instantly from the pellet has been developed and installed at RFEF.

Density, porosity and grain size, 2; Irradiated ROX fuels to burn-up of 28%FIMA

Yanagisawa, Kazuaki; Yamashita, Toshiyuki; Kanazawa, Hiroyuki; Amano, Hidetoshi; Muromura, Tadasumi

Journal of Nuclear Science and Technology, 36(12), p.1153 - 1159, 1999/12

https://doi.org/10.3327/jnst.36.1153

no abstracts in English

Current status of VEGA program

Hidaka, Akihide; Nakamura, Takehiko; Nishino, Yasuharu; Kanazawa, Hiroyuki; Hashimoto, Kazuichiro; Harada, Yuhei; Kudo, Tamotsu; Uetsuka, Hiroshi; Sugimoto, Jun

JAERI-Conf 99-005, p.211 - 218, 1999/07

https://doi.org/10.11484/jaeri-conf-99-005

no abstracts in English

Research program (VEGA) on the fission product release from irradiated fuel

Nakamura, Takehiko; Hidaka, Akihide; Hashimoto, Kazuichiro; Harada, Yuhei; Nishino, Yasuharu; Kanazawa, Hiroyuki; Uetsuka, Hiroshi; Sugimoto, Jun

JAERI-Tech 99-036, 34 Pages, 1999/03

JAERI-Tech-99-036.pdf:1.55MB

no abstracts in English

Fission gas release from rock-like fuels, PuO-ZrO(Y){or ThO}-AlO-MgO at burn-up of 20 MWd/kg

Yanagisawa, Kazuaki; Omichi, Toshihiko; Kanazawa, Hiroyuki; Amano, Hidetoshi; Yamahara, Takeshi

JAERI-Research 97-085, 31 Pages, 1997/11

JAERI-Research-97-085.pdf:2.38MB

no abstracts in English

Thermal durability of modified synroc material as reactor fuel matrix

; Kanazawa, Hiroyuki; Togashi, Yoshihiro; ; Nishino, Yasuharu; ; Nakata, Masahito; Amano, Hidetoshi;

JAERI-Research 94-008, 20 Pages, 1994/08

JAERI-Research-94-008.pdf:1.8MB

no abstracts in English

Microstructural evolution of austenitic stainless steels irradiated in spectrally tailored experiment in ORR at 400°C

Sawai, Tomotsugu; P.J.Maziasz*; Kanazawa, Hiroyuki; Hishinuma, Akimichi

Journal of Nuclear Materials, 191-194, p.712 - 716, 1992/00

https://doi.org/10.1016/0022-3115(92)90565-3

no abstracts in English

Technical report: Technical development on silicide plate-type fuel experiment at Nuclear Safety Research Reactor

Yanagisawa, Kazuaki; Soyama, Kazuhiko; Ichikawa, Hiroki; ; Hoshino, Osamu; ; ; ; Kanazawa, Hiroyuki; Kimura, Yasuhiko; et al.

JAERI-M 91-114, 67 Pages, 1991/08

JAERI-M-91-114.pdf:4.28MB

no abstracts in English