Published February 2003 | Version v1
Report Metadata-only

Investigation of utilizing plutonium as mixed oxide fuel. 6. Evaluation of burn-up characteristics of PWR fuels

Creators

  • 1. Advanced Reactor Technology Co., Ltd. (Japan)

Description

Burn-up characteristics of PWR fuels have been investigated for scenario study of FBR introduction and the other studies on practical use of FBR. Nuclear compositions, radioactivity and thermal power of actinides and fission products in the spent fuel of present burn-up (49GWd/t) and high burn-up (60GWd/t) have been evaluated using the burn-up calculation code ORIGEN-2. This study was carried out as a part of JNC's feasibility study on commercialized FBR cycle system. Main conditions and results of this study are follows; (1) Evaluation code: ORIGEN-2 (open code). (2) fuel enrichment. (3) Evaluation items. Decay change in nuclear compositions, radioactivity and thermal power of actinides and fission products during 1000 years (0,1,2,3,4,5,6,10,,50,100,1000,10000y after burn-up). (author)

Availability note (English)

Available from JICST Library (JICST: Japan Science and Technology Corporation, Information Center for Science and Technology), P.O. Box 10 Hikarigaoka, Tokyo 179-9810 Japan, FAX: +81-3-3979-2210, JICST Service Homepage: www.jst.go.jp/EN/JICST/ServiceGuide

Additional details

Publishing Information

Imprint Pagination
50 p.
Report number
JNC-TJ--9420-2002-008

INIS

Country of Publication
Japan
Country of Input or Organization
Japan
INIS RN
35018096
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Non-conventional Literature
Descriptors DEI
ACTINIDES; BURNUP; COMMERCIALIZATION; FBR TYPE REACTORS; FEASIBILITY STUDIES; FISSION PRODUCTS; MIXED OXIDE FUELS; O CODES; PERFORMANCE TESTING; PLUTONIUM; PWR TYPE REACTORS; RADIOACTIVITY; REACTOR CORES; REACTOR KINETICS; SPENT FUEL ELEMENTS; THERMODYNAMIC PROPERTIES; URANIUM DIOXIDE
Descriptors DEC
ACTINIDE COMPOUNDS; ACTINIDES; BREEDER REACTORS; CHALCOGENIDES; COMPUTER CODES; ELEMENTS; ENERGY SOURCES; ENRICHED URANIUM REACTORS; EPITHERMAL REACTORS; FAST REACTORS; FUEL ELEMENTS; FUELS; ISOTOPES; KINETICS; MATERIALS; METALS; NUCLEAR FUELS; OXIDES; OXYGEN COMPOUNDS; PHYSICAL PROPERTIES; POWER REACTORS; RADIOACTIVE MATERIALS; REACTOR COMPONENTS; REACTOR MATERIALS; REACTORS; SOLID FUELS; TESTING; THERMAL REACTORS; TRANSURANIUM ELEMENTS; URANIUM COMPOUNDS; URANIUM OXIDES; WATER COOLED REACTORS; WATER MODERATED REACTORS