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Kitamura, Akira; Akahori, Kuniaki; Nagata, Masanobu*
Genshiryoku Bakkuendo Kenkyu (CD-ROM), 27(2), p.83 - 93, 2020/12
Direct disposal of spent nuclear fuel (SNF) in deep underground repositories (hereafter "direct disposal") is a concept that disposal canisters stored fuel assemblies dispose without reprocessing. Behavior of radionuclide release from SNF must be different from that from vitrified glass. The present study established a methodology on determination of instant release fraction (IRF) of radionuclides from SNF, which is the one of the parameters on radionuclide release based on the latest safety assessment reports in other countries, especially for IRF values proportional to a fission gas release ratio (FGR). Recommended and maximum values of FGR have been estimated using the fuel performance code FEMAXI-7 after collecting FGR values on Japanese SNFs. Furthermore, recommended and maximum values of IRF for Japanese SNFs used in a pressurized water reactor (PWR) have been estimated using the presently obtained FGR values and experimentally obtained IRF values on foreign SNFs. The recommended and maximum IRF values obtained in the present study have been compared with those of the latest safety assessment reports in other countries.
Yamane, Yuichi; Amano, Yuki; Tashiro, Shinsuke; Abe, Hitoshi; Uchiyama, Gunzo; Yoshida, Kazuo; Ishikawa, Jun
Journal of Nuclear Science and Technology, 53(6), p.783 - 789, 2016/06
Times Cited Count：6 Percentile：43.12(Nuclear Science & Technology)The release behavior of radioactive materials from high active liquid waste (HALW) has been experimentally investigated under boiling accident conditions. In the experiments using HALW obtained through laboratory scale reprocessing, release ratio was measured for the FP nuclides such as Ru, 
Tc, Cs, Sr, Nd, Y, Mo, Rh and actinides such as 
Cm, 
Am. As a result, the release ratio was 0.20 for Ru and 1
for the FP and Ac nuclides. Ru was released into the gas phase in the form of both mist and gas. For its released amount, weak dependency was found to the initial concentration in the test solution. The release ratio decreased with the initial concentration. For other FP nuclides and actinides as non-volatile, released into the gas phase in the form of mist, the released amount increased with the initial concentration. The release ratio of Ru and NOx concentration increased with temperature of the test solutions. They were released almost at the same temperature between 200 and 300
C. Size distribution of the mist and other particle was measured.
Uchiyama, Gunzo; Tashiro, Shinsuke; Amano, Yuki; Abe, Hitoshi; Yamane, Yuichi; Yoshida, Kazuo; Ishikawa, Jun
Proceedings of 21st International Conference & Exhibition; Nuclear Fuel Cycle for a Low-Carbon Future (GLOBAL 2015) (USB Flash Drive), p.1056 - 1063, 2015/09
The experimental study for source term data of radioactive materials has been conducted at a boiling accident of high active liquid waste (HALW) in reprocessing plants. In the study, three kinds of tests have been conducted including a cold small scale test, a cold engineering scale test and a hot small scale test. The following results were obtained: Ruthenium and Technetium were released into the gas phase in the form of both mist and gas under the boiling accident conditions of a simulated HALW. Non-volatile fission products (FPs) such as Nd and Cs were released into the gas phase in the form of mist. The release ratios of non-volatile FPs from a vessel of the simulated HALW were about 10
. The release ratios of actinide nuclides such as Am were almost the same as those of non-volatile FPs.
Tashiro, Shinsuke; Uchiyama, Gunzo; Amano, Yuki; Abe, Hitoshi; Yamane, Yuichi; Yoshida, Kazuo
Nuclear Technology, 190(2), p.207 - 213, 2015/05
Times Cited Count：8 Percentile：51.03(Nuclear Science & Technology)The release behavior of radioactive materials from high active liquid waste (HALW) has been investigated under boiling accident conditions. Results of the experiment using a nonradioactive simulated HALW found Ru to be a volatile element under the accident conditions and to be released into the gas phase in the form of both mist and gas. The Ru release rate and the apparent Ru volatilization rate constant were obtained under the boiling conditions of simulated HALW. The other fission product elements such as Cs were found to be nonvolatile and to be released into the gasphase in the form of mist. The mist size distribution near the surface of the simulated HALW in the reactor vessel was found to range from 0.05 to 20 
m with a peak diameter of 
2 m.
Fuel Safety Research Laboratory
JAERI-Review 2004-021, 226 Pages, 2004/10
JAERI-Review-2004-021.pdf:14.4MB
Fuel Safety Research Meeting 2004, which was organized by Japan Atomic Energy Research Institute, was held on March 1-2, 2004 at Toranomon Pastoral, Tokyo. Purposes of the meeting are to present and discuss results of experiments and analyses on reactor fuel safety and to exchange views and experiences among the participants. Technical topics of the meeting covered status of fuel safety research activities, fuel behavior under RIA and LOCA conditions, high burnup fuel behavior, and radionuclides release under severe accident conditions. This proceeding contains all the papers presented in the meeting.
Fuel Safety Research Laboratory
JAERI-Conf 2001-010, 303 Pages, 2001/09
JAERI-Conf-2001-010.pdf:59.22MB
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.
Fuketa, Toyoshi; Sasajima, Hideo; *; Ishijima, Kiyomi
Journal of Nuclear Materials, 248, p.249 - 256, 1997/00
Times Cited Count：46 Percentile：93.78(Materials Science, Multidisciplinary)no abstracts in English
Fuketa, Toyoshi; Sasajima, Hideo; *; *; Nakamura, Takehiko; Ishijima, Kiyomi
Proc. of 1997 Int. Topical Meeting on LWR Fuel Performance, 0, p.669 - 676, 1997/00
no abstracts in English
Fuketa, Toyoshi; Nagase, Fumihisa; Ishijima, Kiyomi;
Nucl. Saf., 37(4), p.328 - 342, 1996/00
no abstracts in English
Fuketa, Toyoshi; *; Sasajima, Hideo; Ishijima, Kiyomi;
NEA/CSNI/R(95)22, 0, p.59 - 85, 1995/00
no abstracts in English
Saeki, Masakatsu
Journal of Nuclear Materials, 99(1), p.100 - 106, 1981/00
Times Cited Count：10 Percentile：75.8(Materials Science, Multidisciplinary)no abstracts in English
; Nakashima, Mikio; Tachikawa, Enzo
Journal of Nuclear Materials, 101(1), p.9 - 15, 1981/00
Times Cited Count：6 Percentile：62.77(Materials Science, Multidisciplinary)no abstracts in English
Yamamoto, Katsumune; ; Okagawa, Seigo; Yokouchi, Iichiro;
Journal of Nuclear Science and Technology, 17(1), p.67 - 76, 1980/00
Times Cited Count：1 Percentile：22.79(Nuclear Science & Technology)no abstracts in English
; ; ; Wadachi, Yoshiki; ;
Nihon Genshiryoku Gakkai-Shi, 20(1), p.42 - 45, 1978/01
Times Cited Count：0no abstracts in English
Iwamoto, K.
Nihon Genshiryoku Gakkai-Shi, 15(2), p.86 - 101, 1973/02
Times Cited Count：0no abstracts in English
