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Oka, Hiroshi*; Kaito, Takeji; Ikusawa, Yoshihisa; Otsuka, Satoshi
Nuclear Engineering and Design, 370, p.110894_1 - 110894_8, 2020/12
Times Cited Count：0 Percentile：0.01(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.
Ueta, Shohei; Emori, Koichi; Tobita, Tsutomu*; Takahashi, Masashi*; Kuroha, Misao; Ishii, Taro*; Sawa, Kazuhiro
JAERI-Research 2003-025, 59 Pages, 2003/11
JAERI-Research-2003-025.pdf:2.53MB
In the safety design requirements for the High Temperature Engineering Test Reactor (HTTR) fuel, it is determined that "the as-fabricated failure fraction shall be less than 0.2%" and "the additional failure fraction shall be small through the full service period". Therefore the failure fraction should be quantitatively evaluated during the HTTR operation. In order to measure the primary coolant activity, primary coolant radioactivity signals the in safety protection system, the fuel failure detection (FFD) system and the primary coolant sampling system are provided in the HTTR. The fuel and fission product behavior was evaluated based on measured data in the rise-to-power tests (1) to (4). The measured fractional releases are constant at 2
10
up to 60% of the reactor power, and then increase to 710 at full power operation. The prediction shows good agreement with the measured value. These results showed that the release mechanism varied from recoil to diffusion of the generated fission gas from the contaminated uranium in the fuel compact matrix.
Sawa, Kazuhiro; Ueta, Shohei; Sumita, Junya; Verfondern, K.*
Journal of Nuclear Science and Technology, 38(6), p.411 - 419, 2001/06
Times Cited Count：17 Percentile：74.75(Nuclear Science & Technology)no abstracts in English
Sawa, Kazuhiro; Tobita, Tsutomu*; Ueta, Shohei; Suzuki, Shuichi*; Sumita, Junya; Sekita, Kenji; Aoki, Kazunori*; Ouchi, Hiroshi
JAERI-Research 2001-002, 33 Pages, 2001/02
JAERI-Research-2001-002.pdf:1.42MB
no abstracts in English
Sawa, Kazuhiro; Yoshimuta, Shigeharu*; Tobita, Tsutomu*;
JAERI-Research 97-036, 23 Pages, 1997/05
JAERI-Research-97-036.pdf:0.72MB
no abstracts in English
Sawa, Kazuhiro
JAERI-Research 95-072, 20 Pages, 1995/11
JAERI-Research-95-072.pdf:0.65MB
no abstracts in English
Shiratori, Tetsuo; Akabori, Mitsuo; Fukuda, Kosaku; Tsuruta, Harumichi
JAERI-M 90-144, 64 Pages, 1990/09
no abstracts in English
; ; ; Ikawa, Katsuichi; Iwamoto, K.; Yamamoto, Katsumune; ;
JAERI-M 84-054, 65 Pages, 1984/03
no abstracts in English
; ; ; Minato, Kazuo; Ikawa, Katsuichi; Iwamoto, K.;
JAERI-M 83-232, 67 Pages, 1984/01
no abstracts in English
; ; ; Minato, Kazuo; ; Ikawa, Katsuichi
Nihon Genshiryoku Gakkai-Shi, 26(1), p.57 - 74, 1984/00
Times Cited Count：1 Percentile：19.12(Nuclear Science & Technology)no abstracts in English
; Minato, Kazuo; Ikawa, Katsuichi; ;
Journal of Nuclear Science and Technology, 18(11), p.887 - 894, 1982/00
Times Cited Count：4 Percentile：52.53(Nuclear Science & Technology)no abstracts in English
; ; ; Ikawa, Katsuichi; Iwamoto, K.; Yamamoto, Katsumune
Journal of Nuclear Science and Technology, 19(11), p.889 - 902, 1982/00
Times Cited Count：2 Percentile：32.87(Nuclear Science & Technology)no abstracts in English
; ; ; Ikawa, Katsuichi; Iwamoto, K.;
JAERI-M 9644, 50 Pages, 1981/09
no abstracts in English
;
JAERI-M 9306, 40 Pages, 1981/02
no abstracts in English
