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Si/FeSi
artificial latticesSakai, Kenichiro*; Noda, Yuta*; Takeda, Kaoru*; Takeda, Masayasu; Yoshitake, Tsuyoshi*
Physica Status Solidi (C), 10(12), p.1862 - 1865, 2013/12
Times Cited Count：1 Percentile：0.01(Nanoscience & Nanotechnology)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.
Yoshitake, Tsunemitsu; Omori, Tsuyoshi; Sakamoto, Naoki; Ukai, Shigeharu
PNC TN9410 96-281, 81 Pages, 1996/09
The estimation of the life of fuel claddings at thermal transient event is important for evaluating of the fuel claddings validity under the loss of coolant flow (LOF) accident. In order to estimate the life time of the fuel claddings corresponding to any temperature rising condition, the instrumental technique was first improved in the post-irradiation examination and the temperature-transient-to-burst tests were extensively conducted on PNC316 claddings which were irradiated in JOYO as a fuel test assembly PFC030M and a driver fuel assembly PFD304. The life time evaluation of the irradiated PNC316 fuel claddings was carried out, based on these test results. The results obtained in this work are as follows; (1) As a result of the improvement in the temperature-transient-to-burst testing, the diametral change data and higher hoop stress data were obtained. And the highly accurate measurement of rupture temperature was also achieved. (2) The temperature-transient-to-burst test results showed that the rupture temperature of the irradiated PNC316 cladding was equal to that of unirradiated one up to present neutron fluence in LOF stress condition. It was indicated that the temperature-transient-to-burst property of PNC316 was not influenced by irradiation in lower hoop stress region. (3) The life time of the irradiated PNC316 cladding at any thermal transient condition was evaluated by means of LMP-Life Fraction Rule method. Consequently, the result of estimation for failure temperature of heavily irradiated PNC316 showed the possibility for rising the design limit of the cladding highest temperature for MONJU.
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.
