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JAEA Reports

Investigation of utilizing plutonium as mixed oxide fuel (5); BWR for next generation

*; *; *; *

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$$_{2}$$ fuel utilization in the present BWR and future BWR have been summarized based on public documents. (2)Evaluation of spent MOX and UO$$_{2}$$ fuel composition. Nuclear compositions of spent MOX and UO$$_{2}$$ fuels at 45,000MWd/t and 60,000MWd/t burnup have been evaluated and summarized for recycle scenarios by FBR.

JAEA Reports

None

PNC-TJ1621 95-001, 112 Pages, 1995/03

PNC-TJ1621-95-001.pdf:7.78MB

no abstracts in English

JAEA Reports

None

*;

PNC-TN6510 94-001, 19 Pages, 1994/09

PNC-TN6510-94-001.pdf:0.65MB

no abstracts in English

JAEA Reports

H-3 Summary report research and development on geolgical disposal of high-level radioactive waste

PNC-TN1410 93-012, 24 Pages, 1992/09

PNC-TN1410-93-012.pdf:1.04MB

The "First progress report of research and development ongeological disposal of high level radioactive waste",H3 in short,is intended for the Japanese authorities. In accordance with the "Overall program for high level radioactive waste management" set forth by atomic energy commission, H3 is designed to clarify the current status of the research and development work performed by power reactor and nuclear fuel development corporation (PNC) up to the year 1991. H3 presents the updated knowledge on Japan's geological environment, the technology of geological disposal and the performance assessment of the multi-barrier system as a basis for further research and development with the objective of confirming scientific and technical feasibility of the geological disposal concept in Japan. The contents of H3 issummarized in this document.

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