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Journal Articles

Development methodology on determination of instant release fractions for generic safety assessment for direct disposal of spent nuclear fuel

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.

Journal Articles

Release of radioactive materials from high active liquid waste in small-scale hot test for boiling accident in reprocessing plant

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:3 Percentile:60.48(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, $$^{99}$$Tc, Cs, Sr, Nd, Y, Mo, Rh and actinides such as $$^{242}$$Cm, $$^{241}$$Am. As a result, the release ratio was 0.20 for Ru and 1$$times$$$$10^{-4}$$ 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$$^{circ}$$C. Size distribution of the mist and other particle was measured.

Journal Articles

Experimental study on boiling accident of high active liquid waste in reprocessing

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$$^{-4}$$. The release ratios of actinide nuclides such as Am were almost the same as those of non-volatile FPs.

Journal Articles

Release of radioactive materials from simulated high level liquid waste at boiling accident in reprocessing plant

Tashiro, Shinsuke; Uchiyama, Gunzo; Amano, Yuki; Abe, Hitoshi; Yamane, Yuichi; Yoshida, Kazuo

Nuclear Technology, 190(2), p.207 - 213, 2015/05

 Times Cited Count:4 Percentile:56.57(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 $$mu$$m with a peak diameter of $$sim$$ 2 $$mu$$m.

JAEA Reports

Summary of Fuel Safety Research Meeting 2004; March 1-2, 2004, Tokyo

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.

JAEA Reports

Proceedings of the 24th NSRR Technical Review Meeting; Tokyo, November 13-14, 2000

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.

Journal Articles

Fuel failure and fission gas release in high burnup PWR fuels under RIA conditions

Fuketa, Toyoshi; Sasajima, Hideo; *; Ishijima, Kiyomi

Journal of Nuclear Materials, 248, p.249 - 256, 1997/00

 Times Cited Count:41 Percentile:6.9(Materials Science, Multidisciplinary)

no abstracts in English

Journal Articles

NSRR/RIA experiments with high burnup PWR fuels

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

Journal Articles

NSRR/RIA experiments with high-burnup PWR fuels

Fuketa, Toyoshi; Nagase, Fumihisa; Ishijima, Kiyomi;

Nucl. Saf., 37(4), p.328 - 342, 1996/00

no abstracts in English

Journal Articles

Behavior of high burnup PWR fuel under a simulated RIA condition in the NSRR

Fuketa, Toyoshi; *; Sasajima, Hideo; Ishijima, Kiyomi;

NEA/CSNI/R(95)22, 0, p.59 - 85, 1995/00

no abstracts in English

Journal Articles

Release behavior of tritium from graphite heavily irradiated by neutrons

Saeki, Masakatsu

Journal of Nuclear Materials, 99(1), p.100 - 106, 1981/00

 Times Cited Count:8 Percentile:28.92(Materials Science, Multidisciplinary)

no abstracts in English

Journal Articles

Chemical forms of tritium on the release from aluminium

; Nakashima, Mikio; Tachikawa, Enzo

Journal of Nuclear Materials, 101(1), p.9 - 15, 1981/00

 Times Cited Count:6 Percentile:36.54(Materials Science, Multidisciplinary)

no abstracts in English

Journal Articles

Behavior of iodine-131 during rinsing in-pile loop with demineralized water after fission product release experiment

Yamamoto, Katsumune; ; Okagawa, Seigo; Yokouchi, Iichiro;

Journal of Nuclear Science and Technology, 17(1), p.67 - 76, 1980/00

 Times Cited Count:1 Percentile:76.92(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Fixation of radioactive materials released from reactor cooling water by sandy soil

; ; ; Wadachi, Yoshiki; ;

Nippon Genshiryoku Gakkai-Shi, 20(1), p.42 - 45, 1978/01

 Times Cited Count:0

no abstracts in English

Journal Articles

Outline and currect research status on coated particle fuels

Iwamoto, K.

Nippon Genshiryoku Gakkai-Shi, 15(2), p.86 - 101, 1973/02

 Times Cited Count:0

no abstracts in English

15 (Records 1-15 displayed on this page)
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