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Department of Hot Laboratories
JAERI-Review 2005-047, 95 Pages, 2005/09
JAERI-Review-2005-047.pdf:6.27MB
This is an annual report in 2004 fiscal year that describes activities of the Reactor Fuel Examination Facility (RFEF), the Waste Safety Testing Facility (WASTEF), and the Research Hot Laboratory (RHL) in the Department of Hot laboratories. In RFEF, BWR fuel rods were withdrawn from a fuel assembly irradiated for 5 cycles in the Fukushima-2 Nuclear Power Station Unit-1 and PIEs including nondestructive examination of those rods were carried out. In WASTEF, Slow Strain Rate Tests for detecting the susceptibility to IASCC, the corrosion test of reprocessing plant materials, tests for evaluating barrier performance in terms of waste disposal were performed. A secondary system pipe from the Mihama Nuclear Power Station Unit-3 was accepted to inspect the ageing fracture of it. In RHL, 15 lead cells are dismantled under the decommissioning plan at JAERI Tokai. And an arrangement of the RHL facility was started to use the storage of unirradiated nuclear materials.
Ooka, Norikazu*; Ishii, Toshimitsu
Hihakai Kensa, 52(5), p.235 - 239, 2003/05
no abstracts in English
Ishii, Toshimitsu
Hihakai Kensa, 51(6), p.328 - 332, 2002/06
no abstracts in English
Ishii, Toshimitsu; Inagaki, Terumi*; Sakane, Taisuke*; Nakatani, Takahiko*; Ooka, Norikazu; Omi, Masao; Hoshiya, Taiji
Hihakai Kensa, 51(4), p.223 - 230, 2002/04
no abstracts in English
Yasuda, Ryo; Matsubayashi, Masahito; Nakata, Masahito; Harada, Katsuya
Journal of Nuclear Materials, 302(2-3), p.156 - 164, 2002/04
Times Cited Count：28 Percentile：83.24(Materials Science, Multidisciplinary)no abstracts in English
Yasuda, Ryo; Matsubayashi, Masahito; Nakata, Masahito; Harada, Katsuya; Amano, Hidetoshi; Ando, Hitoshi*; Sasajima, Fumio; Nishi, Masahiro; Horiguchi, Yoji
JAERI-Tech 2002-001, 23 Pages, 2002/02
JAERI-Tech-2002-001.pdf:3.79MB
Advanced neutron radiography techniques such as neutron imaging plate (NIP) and Computed Tomography (CT) methods have been investigated the practicality for Post Irradiation Examination (PIE). In this work, an unirradiated fuel rod was examined by NIP and CT methods in order to collect the fundamental data for applying these techniques to PIE.The fuel rod is composed of seven-enriched UO2 pellet and two-natural UO2 pellet that are loaded into a Zircaloy tube. There are somewhat difference in the size and shape among those UO2 pellets. A transmitted and cross-sectional images were obtained by NIP and CT methods, respectively.In the NIP image, the difference in the size, shape, and enrichment among the UO2 pellets is obviously recognized. In the case of CT method, the images clearly show the detailed shape of the cross section in the pellets, in addition, the difference in the enrichment between the natural and enriched pellets is recognized.
Kuramoto, Kenichi; Yamashita, Toshiyuki; Shiratori, Tetsuo
Progress in Nuclear Energy, 38(3-4), p.423 - 426, 2001/02
Times Cited Count：6 Percentile：44.09(Nuclear Science & Technology)no abstracts in English
; ; ; Matsumoto, Shinichiro
JNC TN9410 2000-009, 65 Pages, 2000/09
JNC-TN9410-2000-009.pdf:4.36MB
In order to evaluate irradiation behavior of(U, Pu) C and (U, Pu) N fuel using fast reactor, (U, Pu) C and (U, Pu) N fuel pins were irradiated in JOYO for the fist time in Japan. In this study, one (U, Pu) C fuel pin and two (U, Pu) N fuel pins were irradiated to maximum burn up about 40GWd/t. Post irradiation examination of (U, Pu) C and (U, Pu) N fuel pins started in Fuel Monitoring Facility (FMF) at JNC from October 1999, and it ended in March, 2000. The results of non-destructive post irradiation examination reported in this document. Main results are shown in the following. (1)The soundness of all (U,Pu) C and (U,Pu) N fuel pins were confirmed from the non-destructive examination result. (2)The fuel stack elongation of (U,Pu) C and (U,Pu) N is bigger than it of the MOX fuel for fast reactor. (3)The singular behavior from the gamma ray scanning measurement in the stack area was not confirmed. The migration of Cs137 to lower insulator pellet and outside of the pellet was confirmed in (U,Pu) N B9NO2 pin. In (U,Pu) C fuel, the migration of Cs137 was not confirmed. (4)In (U,Pu) C B9CO1 pin and (U,Pu) N B9NO2 pin in which the gap width was small, diameter of cladding increase around 50 
m in the stack area which originates for FCMI was confirmed. In (U,Pu) N B9NO1 pin in which the gap width was wide, the ovality which originates from the relocation of the pellet was confirmed. (5)Fission gas release rate of (U,Pu) N were 3.3% and 5.2%, and the low value compared to the MOX fuel was shown.
; Ooka, Norikazu; ; Saito, Junichi; Hoshiya, Taiji; *; Kobayashi, Hideo*
JAERI-Conf 99-009, p.163 - 172, 1999/09
no abstracts in English
; Ooka, Norikazu
Proc. of Joint EC-IAEA Specialists Meeting on NDT Methods for Monitoring Degradation, p.167 - 176, 1999/00
no abstracts in English
Nakata, Masahito; Amano, Hidetoshi; ; Nishi, Masahiro; Nakamura, Jinichi; Furuta, Teruo; ;
HPR-345, 0, 9 Pages, 1995/00
no abstracts in English
Yamahara, Takeshi
Nihon Gakujutsu Shinkokai Genshiro Zairyo Dai-122 Iinkai Shiryo; Heisei-6-Nendo Dai-4-Kai Iinkai Shiryo, 0, 8 Pages, 1994/00
no abstracts in English
JAERI-M 9762, 104 Pages, 1981/11
no abstracts in English
Secchaku, 17(4), p.150 - 154, 1981/00
no abstracts in English
Hihakai Kensa, 29(11), p.783 - 789, 1980/00
no abstracts in English
JAERI-M 8392, 16 Pages, 1979/08
no abstracts in English
