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Uwaba, Tomoyuki; Nemoto, Junichi*; Ito, Masahiro*; Ishitani, Ikuo*; Doda, Norihiro; Tanaka, Masaaki; Otsuka, Satoshi
Nuclear Technology, 207(8), p.1280 - 1289, 2021/08
Times Cited Count:3 Percentile:34.82(Nuclear Science & Technology)Computer codes for irradiation behavior analysis of a fuel pin and a fuel pin bundle and for coolant thermal hydraulics analysis were coupled into an integrated code system. In the system, each code provides data required by other codes and the analyzed results are shared among them. The system allows for the synthesizing of analyses of thermal, chemical and mechanical behaviors in a fuel subassembly under irradiation. A test analysis was made for a fuel subassembly containing a mixed oxide fuel pin bundle irradiated in a fast reactor. The results of the analysis were presented with transverse cross-sectional images of the fuel subassembly and three-dimensional images of a fuel pin and fuel pin bundle models. For detailed evaluation, various irradiation behaviors of all fuel pins in the subassembly were analyzed and correlated with irradiation conditions.
Sasajima, Hideo; Sugiyama, Tomoyuki; Nakamura, Takehiko*; Fuketa, Toyoshi
JAERI-Research 2004-022, 113 Pages, 2004/12
Results from power burst tests, GK-1 and GK-2, conducted at the NSRR, are summarized. The tests were performed on a 1414 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.
Harada, Katsuya; Nakata, Masahito; Harada, Akio; Nihei, Yasuo; Yasuda, Ryo; Nishino, Yasuharu
JAERI-Tech 2004-034, 13 Pages, 2004/03
The Department of Hot Laboratories has been aiming the establishment of the melting temperature measuring technique for small samples obtained from the micro-region of irradiated fuel pellet. Due to the modification of the shape of tungsten capsule contained sample and the improvement of the detection method for melting temperature from indistinct thermal arrest point owing to small sample, it is possible to determine the melting temperature of small sample and to utilize effectively for the irradiated fuel pellet by using the existing apparatus. This paper describes the technique of the melting temperature measurement for small sample and the experimental results by using tantalum, molybdenum, hafnium oxide and un-irradiated UO pellet.
Nemoto, Yoshiyuki; Miwa, Yukio; Tsuji, Hirokazu; Tsukada, Takashi
Proceedings of 11th International Conference on Nuclear Engineering (ICONE-11) (CD-ROM), 7 Pages, 2003/04
Irradiation assisted stress corrosion cracking (IASCC) of austenitic stainless steel has been studied as main concern of an aging problem of light water reactor (LWR) materials. It is essential to evaluate corrosion behavior of irradiated materials for mechanistic understanding of IASCC. The aim of this work is to evaluate the corrosion behavior of ion irradiated materials using atomic force microscope (AFM), and evaluate the influence of radiation temperature, radiation damage, H and He implantation.
Nemoto, Yoshiyuki; Miwa, Yukio; Tsuji, Hirokazu; Tsukada, Takashi
Dai-12-Kai MAGDA Konfarensu (Oita) Koen Rombunshu, p.191 - 196, 2003/00
Development and research about analytical method for the study of corrosion behavior of austenitic stainless steel after irradiation was conducted from the point of view for basic study of IASCC (Irradiation Assisted Stress Corrosion Cracking). Ion irradiations were conducted with several irradiation conditions these were irradiation temperature, radiation damage, the contents of helium (He) implantation. AFM (Atomic Force Microscope) was used to evaluate surface condition of irradiated specimens after corrosion procedure. Corrosion condition was developed to obtain good surface condition of irradiated specimens to evaluate corrosion behavior by AFM. It was succeeded and corrosion behavior at inside of grains and grain boundaries of irradiated specimens was obtained. EBSP (Electron Backscatter Diffraction Pattern) was used to evaluate relation of corrosion behavior with grain boundary character. Moreover, relations of corrosion behavior with irradiation condition were discussed.
Harada, Katsuya; Nakata, Masahito; Yasuda, Ryo; Nishino, Yasuharu; Amano, Hidetoshi
HPR-356, 11 Pages, 2001/00
no abstracts in English
Shiratori, Tetsuo; Serizawa, Hiroyuki; Fukuda, Kosaku; Fujino, Takeo*; Sato, Nobuaki*; Yamada, Kota*
JAERI-Research 2000-045, 74 Pages, 2000/09
no abstracts in English
Otomo, Takashi; Nagase, Fumihisa; Uetsuka, Hiroshi
JAERI-Tech 99-071, p.25 - 0, 1999/10
no abstracts in English
Nagase, Fumihisa; ; Uetsuka, Hiroshi
JAERI-Research 98-064, 25 Pages, 1998/11
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
Katanishi, Shoji; Ishijima, Kiyomi
Journal of Nuclear Science and Technology, 32(11), p.1098 - 1107, 1995/11
Times Cited Count:2 Percentile:28.04(Nuclear Science & Technology)no abstracts in English
Yanagisawa, Kazuaki; Ugajin, Mitsuhiro; *
Kaku Nenryo Kogaku; Genjo To Tembo, p.285 - 304, 1993/11
no abstracts in English
Yanagisawa, Kazuaki
JAERI-M 91-152, 195 Pages, 1991/10
no abstracts in English
Takamura, Saburo; Hoshiya, Taiji; ; *
Japanese Journal of Applied Physics, 28(8), p.L1395 - L1397, 1989/08
Times Cited Count:3 Percentile:23.67(Physics, Applied)no abstracts in English
; *; ; ;
Proceedings of International Conference on Martensitic Transformations, p.685 - 690, 1986/00
no abstracts in English
Tanase, Masakazu; Yamaguchi, Koichi; Tanaka, Kichizo
Radioisotopes, 31, p.571 - 578, 1982/00
no abstracts in English
JAERI-M 7267, 36 Pages, 1977/09
no abstracts in English
Iwamoto, K.
Nihon Genshiryoku Gakkai-Shi, 15(2), p.86 - 101, 1973/02
Times Cited Count:0no abstracts in English
Ohgama, Kazuya; Ota, Hirokazu*; Ikusawa, Yoshihisa; Oki, Shigeo; Ogata, Takanari*
no journal, ,
no abstracts in English