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Journal Articles

Fabrication and short-term irradiation behaviour of Am-bearing MOX fuels

Kihara, Yoshiyuki; Tanaka, Kosuke; Koyama, Shinichi; Yoshimochi, Hiroshi; Seki, Takayuki; Katsuyama, Kozo

NEA/NSC/R(2017)3, p.341 - 350, 2017/11

In order to investigate the effect of the addition of americium to MOX fuels on the irradiation behaviour, the "Am-1" program is being conducted at the JAEA. The Am-1 program consists of two short-term irradiation tests of 10-min and 24-h irradiation periods, and a steady-state irradiation test. The short-term irradiation tests and their post irradiation examinations (PIEs) have been successfully completed. To date, the data for PIE of the Am-MOX fuels focused on the microstructural evolution and redistribution behaviour of Am at the initial stage of irradiation have been obtained and reported. In this paper, the results obtained from the Am-1 program are reviewed and detailed descriptions of the fabrication and inspection techniques for the Am-MOX fuels prepared for the program are provided. PIE data for the Am-MOX fuels at the initial stage of irradiation have been accumulated. In this paper, unpublished PIE data for the Am-MOX fuels are also presented.

Journal Articles

Fuel restructuring behavior analysis of MA-bearing MOX fuels irradiated in a fast reactor

Ozawa, Takayuki; Ikusawa, Yoshihisa; Kato, Masato

Transactions of the American Nuclear Society, 113(1), p.622 - 624, 2015/10

A recycle system for minor actinides (MAs), in which MAs are recycled by reprocessing and irradiating them in a fast reactor, is studied to reduce the degree of hazard and the amount of high-level radioactive wastes. MAs would be used as mixed oxide (MOX) fuels with plutonium and uranium in fast reactors. Since MA content of MA-bearing MOX (MA-MOX) to be used in fast reactors is assumed to reach $$sim$$5 wt%HM, the effects on not only fuel properties but also fuel behaviors have to be estimated to use MA-MOX as fast reactor fuels. As the MOX fuels to be used will be irradiated at a comparably high linear power and the fuel center temperature would be assumed to be over 2,273 K during irradiation in the fast reactors, fuel restructuring would take place due to void migration towards the fuel center under the radial temperature gradient, and a central void would be formed. Since the fuel center temperature would be decreased by the effect of formation of the central void, the fuel restructuring is one of the most important behaviors for fast reactor fuels. In this study, the effect of MA content on fuel restructuring behavior was estimated from the results of irradiation experiments such as B11 and B14 performed in Joyo to study the irradiation behaviors of MA-MOX and the calculation results using a fuel restructuring model which can take into account MA-MOX dependence on vapor pressure.

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

Current status of researches on the plutonium rock-like oxide fuel and its burning in light water reactors

Yamashita, Toshiyuki; Akie, Hiroshi; Nakano, Yoshihiro; Kuramoto, Kenichi; Nitani, Noriko; Nakamura, Takehiko

Progress in Nuclear Energy, 38(3-4), p.327 - 330, 2001/02

 Times Cited Count:11 Percentile:34.22

no abstracts in English

JAEA Reports

lrradiation behavior and performance model of nitride fuel

; ;

JNC-TN9400 2000-041, 29 Pages, 2000/03

JNC-TN9400-2000-041.pdf:1.18MB

Irradiation behavior and performance models were investigated in order to apply for nitride fuel options in feasibility study on fast breeder reactor and related recycle systems. (1)MechanicaI design of nitride fuel pin: The behaviors of fission gas release (increase of internal Pressure) and fuel-to-cladding chemical interaction (decrease of cladding thickness) are needed to evaluate cumulative damage fraction in case of fuel pin mechanical design. The behaviors of fission gas release and fuel-to-cladding chemical interaction were investigated from the past studies up to high burnuP, since the lower fission gas release in nitride fuel than in oxide fuel could contribute to reduce the plenum volume and result in the shortening of fuel Pin length. (2)Fuel pin smear density: The higher fuel smear density is preferred for the higher fissile density to improve the core characteristic. The behaviors of fuel pellet swelling were investigated from the past studies up to higher burnup, since the larger fuel pellet swelling in nitride fuel than in oxide fuel would restrict high burunp capability due to fuel-cladding mechanical interaction. (3)Compatibility of nitride fuel with high Temperature water: Compatibility of nitride fuel with high temperature water were investigated from the past studies to contribute water cooled fast breeder reactor options.

JAEA Reports

Development of pellet melting temperature measurement apparatus

Harada, Katsuya; Nishino, Yasuharu; Mita, Naoaki; Amano, Hidetoshi

JAERI-Tech 2000-031, p.27 - 0, 2000/03

JAERI-Tech-2000-031.pdf:2.95MB

no abstracts in English

Journal Articles

ROX-LWR system for almost complete burning of plutonium

Yamashita, Toshiyuki; Akie, Hiroshi; Kimura, Hideo; Takano, Hideki; Muromura, Tadasumi

IAEA-TECDOC-1122, p.309 - 320, 1999/11

no abstracts in English

Journal Articles

Development and application of PIE apparatuses for high-burnup LWR fuels

; Mita, Naoaki; Nishino, Yasuharu; Amano, Hidetoshi

JAERI-Conf 99-009, p.103 - 111, 1999/09

no abstracts in English

JAEA Reports

None

*; *

JNC-TJ8440 99-003, 156 Pages, 1999/03

JNC-TJ8440-99-003.pdf:2.72MB

no abstracts in English

Journal Articles

Current status of the development of low-activation ferritic steels

Shiba, Kiyoyuki; Hishinuma, Akimichi

Purazuma, Kaku Yugo Gakkai-Shi, 74(5), p.436 - 441, 1998/05

no abstracts in English

Journal Articles

Recent progress of research on nitride fuel cycle in JAERI

Suzuki, Yasufumi; Ogawa, Toru; Arai, Yasuo; Mukaiyama, Takehiko

Actinide and Fission Product Partitioning and Transmutation, p.213 - 221, 1998/00

no abstracts in English

Journal Articles

Plutonium and actinide fuel, 4.4; Nitride and carbide fuel

Suzuki, Yasufumi; Arai, Yasuo

Purutoniumu Nenryo Kogaku; Nihon Genshiryoku Gakkai "Jisedai Nenryo" Kenkyu Semmon Iinkai, p.260 - 291, 1998/00

no abstracts in English

Journal Articles

Performance of uranium-plutonium mixed carbide fuel under irradiation

Suzuki, Yasufumi; Arai, Yasuo; Iwai, Takashi; Nakajima, Kunihisa

Proc. of Int. Conf. on Future Nuclear Systems (Global'97), 1, p.522 - 527, 1997/00

no abstracts in English

JAEA Reports

None

; ; ; ; ; ;

PNC-TN8410 96-198, 224 Pages, 1996/06

PNC-TN8410-96-198.pdf:11.86MB

None

Journal Articles

Development of re-instrumentation technique of pressure gauge and thermocouple for irradiated fuel rod

; ; ; Oyamada, Rokuro; Saito, Minoru

Proc. of 4th Asian Symp. on Research Reactors, 10 Pages, 1993/00

no abstracts in English

Journal Articles

Improved graphite damage model for predicting property changes of HTGR graphites under isothermal and nonisothermal irradiations

; H.Cords*; H.Nickel*

Journal of Nuclear Science and Technology, 29(9), p.851 - 858, 1992/09

no abstracts in English

JAEA Reports

None

PNC-TN8020 91-003, 49 Pages, 1990/12

PNC-TN8020-91-003.pdf:1.18MB

no abstracts in English

Journal Articles

In-situ tritium recovery experiment from lithium oxide under hign neutron fluence

Kurasawa, T.; ; ; ; ; ; ; Naruse, Yuji

Journal of Nuclear Materials, 133-134, p.196 - 200, 1985/00

 Times Cited Count:15 Percentile:14.81

no abstracts in English

JAEA Reports

30 (Records 1-20 displayed on this page)