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Review Group on the Structure of the Spent Nuclear Fuel Transportation Casks for
JAERI-Review 2005-023, 133 Pages, 2005/07
JAERI-Review-2005-023.pdf:18.88MB
The Japan Atomic Energy Research Institute (JAERI) constructed two stainless steel transportation casks, JRC-80Y-20T, for spent nuclear fuels of research reactors and had utilized them for transportation since 1981. A modification of the design was applied to the USA for transportation of silicide fuels. Additional analyses employing the impact analysis code LS-DYNA that was often used for safety analysis were submitted by the JAERI to the USA to show integrity of the packages; the casks were still not approved, because inelastic deformation was occurred on the surface of the lid touching to the body. To resolve this problem on design approval of transportation casks, a review group was formed at the end of this June. The group examined the impact analyses by reviewing the input data and performing the sensitivity analyses. As the drop impact analyses were found to be practically reasonable, it was concluded that the approval of the USA for the transportation casks could not be obtained just by revising the analyses; therefore, remodelling the casks is required.
Sugiyama, Tomoyuki; Nakamura, Takehiko; Kusagaya, Kazuyuki*; Sasajima, Hideo; Nagase, Fumihisa; Fuketa, Toyoshi
JAERI-Research 2003-033, 76 Pages, 2004/01
JAERI-Research-2003-033.pdf:17.46MB
Boiling water reactor (BWR) fuels with burnups of 41 to 45 GWd/tU were pulse-irradiated in the Nuclear Safety Research Reactor (NSRR) to investigate fuel behavior under cold startup reactivity-initiated-accident (RIA) conditions. BWR fuel segment rods of 8
8BJ (STEP I) type from Fukushima-Daiichi Unit 3 nuclear power plant were refabricated into short test rods, and they were subjected to prompt enthalpy insertion from 293 to 607 J/g (70 to 145 cal/g) within about 20 ms. The fuel cladding had enough ductility against the prompt deformation due to pellet cladding mechanical interaction. The plastic hoop strain reached 1.5% at the peak location. The cladding surface temperature locally reached about 600 deg C. Recovery of irradiation defects in the cladding due to high temperature during the pulse irradiation was indicated via X-ray diffractometry. Fission gas release during the pulse irradiation was from 3.1% to 8.2%, depending on the peak fuel enthalpy and the normal operation conditions.
Nakamura, Takehiko; Sasajima, Hideo; Fuketa, Toyoshi; Ishijima, Kiyomi
Journal of Nuclear Science and Technology, 33(12), p.924 - 935, 1996/12
Times Cited Count：11 Percentile：68.15(Nuclear Science & Technology)no abstracts in English
Tanzawa, Sadamitsu; ;
Journal of Nuclear Science and Technology, 30(4), p.281 - 290, 1993/04
Times Cited Count：0 Percentile：0.00(Nuclear Science & Technology)no abstracts in English
Ishijima, Kiyomi; Tanzawa, Sadamitsu; Fuketa, Toyoshi;
Proc. on Safety of Thermal Reactors, p.577 - 583, 1991/00
no abstracts in English
Yanagisawa, Kazuaki; D.Chen*
JAERI-M 90-187, 23 Pages, 1990/10
no abstracts in English
Nuclear Technology, 73, p.361 - 377, 1986/00
Times Cited Count：2 Percentile：32.26(Nuclear Science & Technology)no abstracts in English
; ; ; ;
JAERI-M 9140, 40 Pages, 1980/10
no abstracts in English
; ; ; ; ; ; Inabe, Teruo;
Nihon Genshiryoku Gakkai-Shi, 20(9), p.651 - 661, 1978/09
Times Cited Count：7no abstracts in English
; ; ; ;
JAERI-M 7796, 85 Pages, 1978/08
no abstracts in English
JAERI-M 7711, 52 Pages, 1978/06
no abstracts in English
; ; ;
JAERI-M 6542, 30 Pages, 1976/05
no abstracts in English
Harayama, Yasuo; ;
Journal of Nuclear Science and Technology, 11(8), p.352 - 355, 1974/08
Times Cited Count：0no abstracts in English
