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JAEA Reports

Report on the evaluation of research and development activities in FY2014; Issue: "Research and Development on Reprocessing of Nuclear Fuel Materials" (Ex-post evaluation)

Tokai Reprocessing Technology Development Center

JAEA-Evaluation 2015-012, 83 Pages, 2015/12

JAEA-Evaluation-2015-012.pdf:6.67MB

Japan Atomic Energy Agency (hereafter referred as "JAEA") consulted the "Evaluation Committee of Research and Development Activities for Fast Reactor Cycle" to assess the issue on "Research and Development on Reprocessing of Nuclear Fuel Materials" conducted by JAEA during the period from FY2010 to FY2014. In response to the JAEA's request, the committee assessed the R&D programs and the activities of JAEA related to the issue and concluded the mission was accomplished. This evaluation was performed based on the "General guideline for the evaluation of government R&D activities", the "Guideline for evaluation of R&D in Ministry of Education, Culture, Sports, Science and Technology (MEXT)" and the "Operational rule for evaluation of R&D activities" by JAEA.

Journal Articles

NSRR RIA-simulating experiments on high burnup LWR fuels

Fuketa, Toyoshi; Sugiyama, Tomoyuki; Sasajima, Hideo; Nagase, Fumihisa

Proceedings of 2005 Water Reactor Fuel Performance Meeting (CD-ROM), p.633 - 645, 2005/10

LWR fuel behaviors during a reactivity initiated accident (RIA) are being studied in the NSRR program. Results from recent NSRR experiments, no failures in Tests OI-10 and -12 and the higher failure enthalpy in Test OI-11, reflect the better performance of the new cladding materials in terms of corrosion during PWR operations. Accordingly, these rods with improved corrosion resistance have larger safety margin than conventional Zircaloy-4 rods. In addition, the smaller inventory of inter-granular gas in the large grain pellet could reduce the fission gas release in RIA as observed in the OI-10. Test VA-1 was conducted with an MDA sheathed 78 MWd/kgU PWR fuel rod. Despite of the higher burnup and thicker oxide layer of $$sim$$81$$mu$$m, the enthalpy at failure remained in a same level as those for rods with of $$sim$$40$$mu$$m-oxide at 50 - 60 MWd/kgU. This result suggests high burnup structure (rim structure) in pellet periphery does not have strong effect on the failure enthalpy reduction because the PCMI load is produced primarily by solid thermal expansion of the pellet.

Journal Articles

LOCA and RIA studies at JAERI

Sugiyama, Tomoyuki; Nagase, Fumihisa; Nakamura, Jinichi; Fuketa, Toyoshi

HPR-362, Vol.2, 12 Pages, 2004/05

To provide a data base for the regulatory guide of light water reactors, behavior of reactor fuels during off-normal and postulated accident conditions such as loss of coolant accident (LOCA) and reactivity-initiated accident (RIA) is being studied at the Japan Atomic Energy Research Institute (JAERI). The LOCA program consists of integral thermal shock tests and other separate tests for oxidation rate and mechanical property of fuel claddings. Prior to the tests on irradiated claddings, the tests have been conducted on non-irradiated claddings to examine separate effects of corrosion and hydrogen absorption during reactor operation. The tests on irradiated claddings have recently been started and results have been obtained. As for an RIA study, a series of experiments with high burnup fuel rods is being performed by using pulse irradiation capability of the NSRR. This paper presents recent results obtained from the LOCA and RIA studies at JAERI.

JAEA Reports

Fuel irradiation research of Japan at Halden reactor; Achievement of cooperative researches between JAERI and several organizations in the period from 2000 to 2002 (Joint research)

Committee of the Halden Joint Research Programme

JAERI-Tech 2004-023, 38 Pages, 2004/03

JAERI-Tech-2004-023.pdf:1.85MB

JAERI has performed cooperative researches with several Japanese organizations utilizing the Halden Boiling Heavy Water Reactor(HBWR) which is located at Halden in Norway. These researches are carried out based on the contracts of the cooperative researches, which are revised every three years, in accordance with the renewal of the participation of JAERI to the OECD Halden Reactor Project. This report summarizes the objectives, contents and the outlines of the achievements of the cooperative researches during the three years from 2000 January to 2002 December. During the period, seven cooperative researches had been carried out. Two of them had been completed and other five researches have been continued to the next three years period. Most of them are irradiation test researches of advanced fuel and cladding in order to prepare the higher burnup utilization and introduction of LWR fuel and MOX fuel in LWRs of Japan.

Journal Articles

Advanced irradiation experiments technique for nuclear fuels in the JMTR

Komori, Yoshihiro

Saishin Kaku Nenryo Kogaku; Kodoka No Genjo To Tembo, p.241 - 250, 2001/06

no abstracts in English

JAEA Reports

JAEA Reports

Annual report on operation, utilization and technical development of Hot Laboratories; From April 1, 1998 to March 31, 1999

Department of Hot Laboratories

JAERI-Review 99-026, p.118 - 0, 1999/11

JAERI-Review-99-026.pdf:9.93MB

no abstracts in English

JAEA Reports

JAEA Reports

JAEA Reports

JAEA Reports

Fission gas release during power change; Re-irradiation test of LWR fuel rod at JMTR

Nakamura, Jinichi; Endo, Yasuichi; ; ; Furuta, Teruo

JAERI-Research 95-083, 38 Pages, 1995/11

JAERI-Research-95-083.pdf:1.42MB

no abstracts in English

Journal Articles

Properties of MOX fuels

Nippon Genshiryoku Gakkai-Shi, 37(10), p.919 - 921, 1995/00

no abstracts in English

JAEA Reports

Basic safety research for high burnup fuels in light water reactors

Furuta, Teruo

JAERI-Tech 94-027, 152 Pages, 1994/11

JAERI-Tech-94-027.pdf:6.45MB

no abstracts in English

Journal Articles

World trend in the LWR fuel development

Ichikawa, Michio

Genshiryoku Kogyo, 39(5), p.8 - 16, 1993/00

no abstracts in English

Journal Articles

Fuel Reliability Laboratory

Furuta, Teruo

Kaku Nenryo, (17), p.17_44 - 17_45, 1992/06

no abstracts in English

Journal Articles

Analytical method and behavior of volatile nuclides in dissolution of spent LWR fuels

Komaki, Yoshihide; ; ; ; Sakurai, Tsutomu; ; Kobayashi, Yoshii; Adachi, Takeo

Nippon Genshiryoku Gakkai-Shi, 33(5), p.489 - 497, 1991/05

 Times Cited Count:0 Percentile:100(Nuclear Science & Technology)

no abstracts in English

Journal Articles

LWR fuel behavior under transient power condition

Furuta, Teruo

Genshiryoku Kogyo, 35(5), p.45 - 50, 1989/05

no abstracts in English

Journal Articles

Study of pellet-cladding interaction on light water reactor fuel, (II); BWR type fuel rod

; H.Devold*

Nippon Genshiryoku Gakkai-Shi, 28(8), p.771 - 782, 1986/00

 Times Cited Count:2 Percentile:66.7(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Fuel Centerline Temperature Measuring Experiment Using the BOCA Capsules(80F-1J,2J)

; Kawamura, Hiroshi; ; ; ; ;

JAERI-M 85-087, 23 Pages, 1985/07

JAERI-M-85-087.pdf:0.84MB

no abstracts in English

39 (Records 1-20 displayed on this page)