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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.
Iijima, Shizuka; Uchida, Naoki; Taguchi, Katsuya; Washiya, Tadahiro
JAEA-Review 2015-018, 39 Pages, 2015/11
JAEA-Review-2015-018.pdf:3.95MB
There is a possibility that the fuel assemblies stored in the spent fuel pool (SFP) at Fukushima Daiichi NPS (or Nuclear Power Station) are not only exposed to seawater and concrete fragments, but also damaged by fallen rubbles. We checked the reprocessing experiences of leak fuels at Tokai Reprocessing Plant and overseas reprocessing facilities, and the storage conditions and the checked and inspected results of the fuel stored in the SFP at Fukushima Daiichi NPS, after that, we listed up the technological problems with reprocessing damaged nuclear fuels and selected elements of the research for the purpose of drawing indicators to make a judgmental decision of the possibility of damaged nuclear fuels reprocessing. And we drew the indicators to make a judgmental decision on the possibility of reprocessing based on the results of the examination and the study about elements of the research.
Omichi, Toshihiko
JAERI-Review 96-008, 13 Pages, 1996/07
JAERI-Review-96-008.pdf:0.92MB
no abstracts in English
W.Hering*; Minato, Kazuo; Nagase, Fumihisa
Nuclear Technology, 102, p.100 - 115, 1993/04
Times Cited Count：2 Percentile：29.78(Nuclear Science & Technology)no abstracts in English
;
JAERI-M 92-072, 194 Pages, 1992/05
no abstracts in English
Pellet;
JAERI-M 85-199, 16 Pages, 1985/12
no abstracts in English
JAERI-M 85-197, 95 Pages, 1985/12
no abstracts in English
; ; Murao, Yoshio; ; ; ; ; ; ; Ueda, Shuzo; et al.
JAERI-M 82-039, 201 Pages, 1982/05
no abstracts in English
Nishi, Yoshihisa*; Arai, Kenji*; Oikawa, Hirohide*; Fujii, Tadashi*; Umezawa, Shigemitsu*; Yamada, Hidetomo*; Nakamura, Hideo
no journal, ,
no abstracts in English
Oka, Hiroshi; Ikusawa, Yoshihisa; Otsuka, Satoshi; Kaito, Takeji
no journal, ,
Cm-doped nitride induced by self-irradiation damage at room temperatureTakano, Masahide; Takaki, Seiya
no journal, ,
To understand behavior of the nitride fuel for minor actinide transmutation, lattice and bulk expansion of the nitride fuel pellet induced by 
self-irradiation at room temperature was investigated. Lattice parameter and dimensions of the (Pu,Cm,Zr)N nitride fuel pellet were repeatedly measured at room temperature as a function of storage period, and their relationship was considered. The lattice expansion followed the model equation well, and saturated to 0.49%, which is greater than that for CmN. The higher density of metallic elements in (Pu,Cm,Zr)N can be the main cause of the greater expansion. On the other hand, both the pellet diameter and height increased with the expansion curve similar to the lattice expansion, and saturated approximately to 0.5%. From this similarity we have found that the main cause of the bulk expansion is the lattice expansion due to the accumulation of Frenkel defects.
