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Sakurai, Junya*; Torigata, Keisuke*; Matsunaga, Manabu*; Takanashi, Naoto*; Hibino, Shinya*; Kizu, Kenichi*; Morita, Akira*; Inomoto, Masahiro*; Shimohata, Nobuaki*; Toyota, Kodai; et al.
Tetsu To Hagane, 111(5), p.246 - 262, 2025/04
Oka, Hiroshi*; Kaito, Takeji; Ikusawa, Yoshihisa; Otsuka, Satoshi
Nuclear Engineering and Design, 370, p.110894_1 - 110894_8, 2020/12
Times Cited Count：1 Percentile：8.72(Nuclear Science & Technology)The objective of this study is to evaluate the reliability of a cumulative damage fraction (CDF) analysis for the prediction of fuel pin breach in fast rector using experimentally obtained fuel pin breach data for the first time. Six breached fuel pins were obtained from steady state irradiation in the EBR-II. Post irradiation examinations revealed that FP gas pressure was the main cause of creep damage in cladding, and that the stress contribution from FCMI was negligible. CDFs evaluated for these pins using in-reactor creep rupture equation, taking into account the irradiation history of cladding temperature and hoop stress due to FP gas pressure, were in the range of 0.7 to 1.4 at the occurrence of breach. This shows clearly that fuel pin breach occurs when the CDF approaches 1.0. The results indicate that CDF analysis would be a reliable method for the prediction of fuel pin breach when appropriate material strength and environmental effects are adopted.
Onizawa, Takashi; Hashidate, Ryuta
Mechanical Engineering Journal (Internet), 6(1), p.18-00477_1 - 18-00477_15, 2019/02
Aiming at enhancing its economic competitiveness and reducing radioactive waste, JAEA has proposed an attractive plant concept and made great efforts to demonstrate the applicability of some innovative technologies to the plant. One of the most practical means is to extend the design life to 60 years. Accordingly, the material strength standards set by JSME have to be extended from 300,000 to 500,000 hours but this extension requires more precise estimation of creep rupture strength and creep strain of the materials in the long term. This paper describes the development of creep property equations of 316FR stainless steel and Mod.9Cr-1Mo steel considering changes in creep mechanisms at high temperatures in the long term based on evaluations of long-term creep properties of the materials. The creep property equations developed in this study will provide more precise estimation of the creep properties in the long term than the present creep property equations of JSME.
Sugawara, Takanori; Tsujimoto, Kazufumi
JAEA-Research 2017-011, 35 Pages, 2017/10
JAEA-Research-2017-011.pdf:4.88MB
The construction of Transmutation Physics Experimental Facility (TEF-P) is planned in the J-PARC project. TEF-P is a critical assembly and it will treat minor actinide (MA) fuel in the experiment. The temperature when the air cooling for the TEF-P core would stop was estimated but there were no data to evaluate the soundness of the MA fuel pin. To set a tentative limit temperature for the TEF-P core, cladding tube burst experiment was performed. As the result, the cladding tube burst occurred at 660
C as the severest case. Through these results and the estimation of creep rupture time, the tentative limit temperature for the TEF-P core was set to 600C.
; Saito, T.*; Tsuji, Hirokazu; Takatsu, T.*; Shindo, Masami; Nakajima, Hajime
JAERI-Research 97-032, 20 Pages, 1997/05
JAERI-Research-97-032.pdf:1.78MB
no abstracts in English
; Tsuji, Hirokazu; Shindo, Masami; Nakajima, Hajime
Journal of Nuclear Materials, 246(2-3), p.196 - 205, 1997/00
Times Cited Count：19 Percentile：79.41(Materials Science, Multidisciplinary)no abstracts in English
; ; ; Tsuji, Hirokazu; ; Shindo, Masami
Mater. Sci. Eng., A, 234-236, p.1087 - 1090, 1997/00
no abstracts in English
Kurata, Yuji; Nakajima, Hajime
Journal of Nuclear Materials, 228, p.176 - 183, 1996/00
Times Cited Count：12 Percentile：69.89(Materials Science, Multidisciplinary)no abstracts in English
Kurata, Yuji; ; ; Shindo, Masami; Nakajima, Hajime;
Journal of Nuclear Science and Technology, 32(11), p.1108 - 1117, 1995/11
Times Cited Count：4 Percentile：42.72(Nuclear Science & Technology)no abstracts in English
Kurata, Yuji; ; ; Shindo, Masami; Nakajima, Hajime;
Tainetsu Kinzoku Zairyo Dai-123-Iinkai Kenkyu Hokoku, 36(2), p.149 - 156, 1995/07
no abstracts in English
Kurata, Yuji; ; ; Shindo, Masami; Nakajima, Hajime;
JAERI-Research 95-037, 42 Pages, 1995/06
JAERI-Research-95-037.pdf:2.04MB
no abstracts in English
Kurata, Yuji; Nakajima, Hajime
Journal of Nuclear Science and Technology, 32(6), p.539 - 546, 1995/06
Times Cited Count：7 Percentile：58.67(Nuclear Science & Technology)no abstracts in English
Kurata, Yuji; Nakajima, Hajime
JAERI-Research 94-004, 30 Pages, 1994/08
JAERI-Research-94-004.pdf:2.99MB
no abstracts in English
Kurata, Yuji; Nakajima, Hajime
JAERI-M 94-022, 28 Pages, 1994/02
no abstracts in English
Kurata, Yuji; Hamada, Shozo; Nakajima, Hajime
Proc. of 10th Int. Conf. on Strength of Materials; ICSMA 10, 0, p.677 - 680, 1994/00
no abstracts in English
Nakajima, Hajime; ; Watanabe, Katsutoshi; Kondo, Tatsuo
Computer Aided Innovation of New Materials, p.827 - 830, 1991/00
no abstracts in English
; Ogawa, Yutaka; Nakajima, Hajime
Trans.Iron Steel Inst.Jpn., 27, P. 81, 1987/00
no abstracts in English
; ; ; ; Kondo, Tatsuo
Proc.Int.Conf.on Creep, p.97 - 102, 1986/00
no abstracts in English
; Ogawa, Yutaka; Kondo, Tatsuo
Nuclear Technology, 66, p.250 - 259, 1984/00
Times Cited Count：10 Percentile：70.25(Nuclear Science & Technology)no abstracts in English
Ueda, Shuzo; ;
Int.J.Press.Vessels Piping, 10, p.465 - 480, 1982/00
Times Cited Count：1 Percentile：61.38(Engineering, Multidisciplinary)no abstracts in English
