Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Sasajima, Hideo; Sugiyama, Tomoyuki; Nakamura, Takehiko*; Fuketa, Toyoshi
JAERI-Research 2004-022, 113 Pages, 2004/12
JAERI-Research-2004-022.pdf:47.48MB
Results from power burst tests, GK-1 and GK-2, conducted at the NSRR, are summarized. The tests were performed on a 14
14 PWR fuel rod irradiated to a burnup of 42 MWd/kgU in the Genkai unit #1 of Kyushu Electric Power Co., Inc. The instrumented test fuel rod in a double-container-type capsule was subjected to the pulse-irradiation with stagnant water cooling condition at 0.1 MPa and 293 K. Deposited energy and peak fuel enthalpy were 505 J/g and 389 J/g in the Test GK-1, and 490 J/g and 377 J/g in the Test GK-2, respectively. During the pulse-irradiations, DNB occurred and the cladding surface temperature reached 581 K and 569 K in the Tests GK-1 and -2, respectively. The maximum cladding hoop strain was 2.7% in the Test GK-1 and 1.2% in the Test GK-2. However, the test fuel rods did not fail. Estimated fission gas releases during the pulse-irradiations were 11.7% and 7.0% in the Tests GK-1 and -2, respectively.
Sasajima, Hideo; Sugiyama, Tomoyuki; Nakamura, Takehiko; Fuketa, Toyoshi; Uetsuka, Hiroshi
Proceedings of 7th International Topical Meeting on Research Reactor Fuel Management (ENS RRFM2003), p.109 - 113, 2003/03
Uranium-zirconium hydride (U-ZrHx) fuel has been widely utilized in the world as TRIGA reactor fuel. In order to obtain the fuel performance data under accident conditions and to enhance accountability of the safety assessment of the reactors using the fuel, irradiation tests under power burst type accident conditions have been conducted in the NSRR. Five pulse irradiation tests have been performed at peak fuel enthalpies ranging from 187 J/g to 483 J/g. Cladding surface temperature increased rapidly at the pulse and DNB occurred in peak fuel enthalpy over 187 J/g in the tests. The DNB occurred at lower fuel enthalpy in the U-ZrH1.6 fuel than in the UO
fuel rods. The rod internal pressure rose up to as high as 1MPa in the transient heating tests, suggesting considerable release of the hydrogen decomposed from the fuel. The peak pressure was lower than equilibrium hydrogen pressure of 1.5MPa at the peak temperature, suggesting the transient effect. Considerable PCMI was observed in the tests, through cladding elongation up to 3.3 mm synchronized to the pellet stack deformation.
Nakamura, Takehiko; Kusagaya, Kazuyuki*; Yoshinaga, Makio; Uetsuka, Hiroshi; Yamashita, Toshiyuki
Progress in Nuclear Energy, 38(3-4), p.379 - 382, 2001/02
Times Cited Count：8 Percentile：52.36(Nuclear Science & Technology)no abstracts in English
Fuketa, Toyoshi; Sasajima, Hideo; Sugiyama, Tomoyuki
Nuclear Technology, 133(1), p.50 - 62, 2001/01
Times Cited Count：67 Percentile：96.81(Nuclear Science & Technology)no abstracts in English
Nakamura, Takehiko; Ikeda, Yoshikazu; Yachi, Shigeyasu; Ogawara, Masami; Yoshinaga, Makio; Takariko, Isao; Toyokawa, Shunji; Katanishi, Shoji; Sobajima, Makoto
JAERI-Tech 2000-019, p.162 - 0, 2000/03
JAERI-Tech-2000-019.pdf:6.02MB
no abstracts in English
Nagao, Yoshiharu; Nakamichi, Masaru; Kawamura, Hiroshi
Journal of Nuclear Science and Technology, 37(Suppl.1), p.423 - 426, 2000/03
no abstracts in English
Utsumi, Takayuki*; Sasaki, Akira; Kunugi, Tomoaki*; Fujii, Sadao*; Akamatsu, Mikio*
Proceedings of 13th International Conference on High-Power Particle Beams (BEAMS 2000) (CD-ROM), 4 Pages, 2000/00
no abstracts in English
fuel under reactivity initiated accident conditionsSasajima, Hideo; Nakamura, Jinichi; Fuketa, Toyoshi; Uetsuka, Hiroshi
Journal of Nuclear Science and Technology, 36(11), p.1101 - 1104, 1999/11
Times Cited Count：2 Percentile：21.18(Nuclear Science & Technology)no abstracts in English
Otomo, Takashi; Nagase, Fumihisa; Uetsuka, Hiroshi
JAERI-Tech 99-071, p.25 - 0, 1999/10
no abstracts in English
*; Sasaki, Akira; Kunugi, Tomoaki*; *; *
Computational Fluid Dynamics Journal, 8(1), p.128 - 134, 1999/04
no abstracts in English
Nagase, Fumihisa; ; Uetsuka, Hiroshi
JAERI-Research 98-064, 25 Pages, 1998/11
JAERI-Research-98-064.pdf:2.17MB
no abstracts in English
Fuketa, Toyoshi; Nakamura, Takehiko; Ishijima, Kiyomi
NUREG/CP-0162, 2, p.179 - 198, 1998/00
no abstracts in English
Fuketa, Toyoshi; Nagase, Fumihisa; Nakamura, Takehiko; Uetsuka, Hiroshi; Ishijima, Kiyomi
NUREG/CP-0166, 3, p.223 - 241, 1998/00
no abstracts in English
Nagase, Fumihisa; Uetsuka, Hiroshi
Proc. of Int. Topical Meeting on LWR Fuel Performance, 0, p.677 - 684, 1997/03
no abstracts in English
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
Ishijima, Kiyomi; *; Fuketa, Toyoshi; Sasajima, Hideo
NEA/CSNI/R(95)22, 0, p.87 - 105, 1996/00
no abstracts in English
Nakamura, Takehiko; ; Ishijima, Kiyomi; ; Yamahara, Takeshi; ; Ito, Tadaharu
JAERI-Research 95-080, 92 Pages, 1995/11
JAERI-Research-95-080.pdf:8.22MB
no abstracts in English
Katanishi, Shoji; Ishijima, Kiyomi
Journal of Nuclear Science and Technology, 32(11), p.1098 - 1107, 1995/11
Times Cited Count：2 Percentile：28.12(Nuclear Science & Technology)no abstracts in English
Nakamura, Takehiko; ; Sobajima, Makoto; Ishijima, Kiyomi;
Nuclear Technology, 108, p.45 - 60, 1994/10
Times Cited Count：14 Percentile：75.32(Nuclear Science & Technology)no abstracts in English
Nakamura, Takehiko; *; *
JAERI-M 94-031, 156 Pages, 1994/03
no abstracts in English
