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*; *; *; *
JNC TJ9440 2000-007, 43 Pages, 2000/03
JNC-TJ9440-2000-007.pdf:1.73MB
Planning of the plutonium utihzation in the Light water thermal reactor has been investigated to evaluate scenario for FBR development. Plans for MOX fuel utilization in the ABWR including Ooma plant are studied, and information of high burnup fuels for a future BWR is summarized based on public documents. Nuclear compositions of the present burnup fuel (45,000MWd/t) and a high burnup fue (60,000MWd/t) have been evaluated using an open code: SRAC. Results of the study are follows; (1)Surveying the status of MOX fuel utilization. The status of MOX and UO
fuel utilization in the present BWR and future BWR have been summarized based on public documents. (2)Evaluation of spent MOX and UO fuel composition. Nuclear compositions of spent MOX and UO fuels at 45,000MWd/t and 60,000MWd/t burnup have been evaluated and summarized for recycle scenarios by FBR.
Suzuki, Motoe; Saito, Hioraki*
JAERI-Data/Code 94-011, 178 Pages, 1994/09
JAERI-Data-Code-94-011.pdf:3.84MB
no abstracts in English
Sato, Makoto; Ichimura, Seiji; Suyama, Kenya; Tonoike, Kotaro; Kamohara, Keiko*; Suzuki, Norihisa*
no journal, ,
no abstracts in English
Ikusawa, Yoshihisa; Morimoto, Kyoichi; Kato, Masato; Uno, Masayoshi*
no journal, ,
The thermal conductivity of oxide fuel is one of the most important properties, since it affects temperature distribution in fuel during irradiation. It is well known that thermal conductivity strongly depends on the oxide-metal ratio (O/M) and burnup of the oxide fuel, and there have been many studies of UO fuel. On the other hand, the thermal conductivity of uranium-and-plutonium-mixed oxide (MOX) fuel is more complex than UO fuel because it is influenced by plutonium content and alpha damage in addition to the aforementioned factors. We have measured the thermal conductivity of various MOX fuels, such as stored samples, irradiated samples, and, several different plutonium content samples. In addition, plutonium content, alpha damage, and burnup effects on MOX fuel thermal conductivity were investigated from the result of these measurements.