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Nagase, Fumihisa; Otomo, Takashi; Uetsuka, Hiroshi*
Nuclear Technology, 208(3), p.484 - 493, 2022/03
Times Cited Count:2 Percentile:30.55(Nuclear Science & Technology)An Ag-In-Cd control rod alloy was heated in argon or oxygen at 1073-1673 K for 60-3600 s and the release behavior of the elements was examined. Complete liquefaction of the alloy occurred between 1123 and 1173 K, and elemental release was quite limited below the liquefaction temperature. In argon, almost all of the Cd content was released within 3600 s at 1173 K and within 60 s at 1573 K, while the released fractions of Ag and In were 3% and 8%, respectively. In oxygen, the release of Cd, which was quite small at temperatures up to 1573 K, drastically increased to 30-50% at 1673 K for short periods. Releases of Ag and In were also small in oxygen under the examined conditions. Comparison with the experimental data suggests that conventional empirical release models may underestimate the Cd release at lower temperatures just after control rod failure in severe accidents.
Khatib-Rahbar, M.*; Barrachin, M.*; Denning, R.*; Gabor, J.*; Gauntt, R.*; Herranz, L. E.*; Hobbins, R.*; Jacquemain, D.*; Maruyama, Yu; Metcalf, J.*; et al.
NUREG/CR-7282, ERI/NRC 21-204 (Internet), 160 Pages, 2021/04
Miradji, F.; Suzuki, Chikashi; Nakajima, Kunihisa; Osaka, Masahiko
Journal of Physics and Chemistry of Solids, 136, p.109168_1 - 109168_9, 2020/01
Times Cited Count:2 Percentile:12.54(Chemistry, Multidisciplinary)Itoi, Tatsuya*; Iwaki, Chikako*; Onuki, Akira*; Kito, Kazuaki*; Nakamura, Hideo; Nishida, Akemi; Nishi, Yoshihisa*
Nihon Genshiryoku Gakkai-Shi ATOMO, 60(4), p.221 - 225, 2018/04
no abstracts in English
Fuel Safety Research Laboratory
JAERI-Conf 2002-009, 491 Pages, 2002/08
Fuel Safety Research Specialists' Meeting, which was organized by Japan Atomic Energy Research Institute, was held on March 4-5, 2002 at JAERI in Tokai Establishment. Purposes of the Meeting are to exchange information and views on LWR fuel safety topics among the specialist participants from domestic and foreign organizations, and to discuss the recent and future fuel research activities in JAERI. In the Meeting, presentations were given and discussions were made on general report of fuel safety research activities, fuel behaviors in normal operation and accident conditions, FP release behaviors in severe accident conditions, and JAERI's “Advanced LWR Fuel Performance & Safety Research Program". A poster exhibition was also carried out. The Meeting significantly contributed to planning future program and cooperation in fuel research. This proceeding integrates all the pictures and papers presented in the Meeting.
Fuel Safety Research Laboratory
JAERI-Conf 2001-010, 303 Pages, 2001/09
The 24th NSRR Technical Review Meeting was held at Tranomon Pastoral, Tokyo, on November 13 and 14, 2000. The purpose of the meeting was to present and discuss the recent progress of the NSRR program and other LWR fuel safety researches at JAERI. Twenty-one papers, including five by foreign institutes, were presented and discussed regarding fuel behavior during normal operation, reactivity initiated accident (RIA) and loss-of-coolant accident (LOCA) and FP release behavior during severe accident. The meeting was a great help in planning future research and promoting research cooperation. This proceeding contains the papers presented in the meeting.
Nagase, Fumihisa; Otomo, Takashi; Uetsuka, Hiroshi
JAERI-Research 2001-009, 21 Pages, 2001/03
no abstracts in English
Uetsuka, Hiroshi; Nagase, Fumihisa;
Journal of Nuclear Materials, 246(2-3), p.180 - 188, 1997/00
Times Cited Count:13 Percentile:70.31(Materials Science, Multidisciplinary)no abstracts in English
Kosaka, Atsuo; ; Sugimoto, Jun
10th Pacific Basin Nuclear Conf. (10-PBNC), 1, p.341 - 346, 1996/00
no abstracts in English
Uetsuka, Hiroshi; Nagase, Fumihisa;
JAERI-Research 95-086, 20 Pages, 1995/12
no abstracts in English
Ichikawa, Michio; Kosaka, Atsuo;
Proc. of the 9th Pacific Basin Nuclear Conf., Vol. 2, 0, p.583 - 588, 1994/00
no abstracts in English
Uetsuka, Hiroshi; Nagase, Fumihisa;
Transactions of the American Nuclear Society, 69, p.309 - 310, 1993/00
no abstracts in English
Nihon Genshiryoku Gakkai-Shi, 33(12), p.1112 - 1120, 1991/12
no abstracts in English
Nakamura, Hideo; Arai, Kenji*; Oikawa, Hirohide*; Fujii, Tadashi*; Umezawa, Shigemitsu*; Onuki, Akira*; Nishi, Yoshihisa*; Abe, Yutaka*; Sugimoto, Jun*; Koshizuka, Seiichi*; et al.
no journal, ,
Nakamura, Hideo
no journal, ,
no abstracts in English
Osaka, Masahiko
no journal, ,
Fundamental study on fission product chemistry under LWR severe accident conditions conducted by JAEA is presented.
Nakamura, Hideo
no journal, ,
no abstracts in English