Effective utilization of uranium and plutonium in LWR cores - plutonium utilization improvements in BWR cores
- 1. Toshiba Corp., Kanagawa (Japan)
- 2. Hitachi Ltd., Ibaraki (Japan)
- 3. Nuclear Power Engineering Corp., Tokyo (Japan)
- 4. Univ. of Tokyo (Japan)
Description
To determine effective utilization of plutonium in a mixed-oxide (MOX) core, which is defined as one in which all uranium fuels are replaced with MOX Fuel, the Nuclear Power Engineering Corporation has studied the high-moderation core (HMC), which reduces plutonium inventory, and the low-moderation core (LMC), which reduces the plutonium consumption ratio by increasing the fissile conversion ratio (FCR) (the ratio of residual fissile in discharged fuel to fissile inventory in loaded fuel). It has also evaluated the plutonium inventory savings of the HMC and the FCR increase of the LMC and compared with a reference MOX core, which is a full MOX core based on a 1350-MW(electric) advanced boiling water reactor. In this study, the so-called large square lattice core (LSLC) concept was developed as the LMC with as little plant system modification as possible. The hexagonal lattice core (HLC) concept was developed, which allows modification of the plant system for increasing FCR
Additional details
Publishing Information
- Journal Title
- Transactions of the American Nuclear Society
- Journal Volume
- 66
- Journal Page Range
- p. 463-464.
- ISSN
- 0003-018X
- CODEN
- TANSAO
Conference
- Title
- past, present, and future.
- Acronym
- Joint American Nuclear Society (ANS)/European Nuclear Society (ENS) international meeting on fifty years of controlled nuclear chain reaction
- Dates
- 15-20 Nov 1992.
- Place
- Chicago, IL (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 24050721
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BWR TYPE REACTORS; CONVERSION RATIO; DESIGN; FUEL CYCLE; FUEL MANAGEMENT; JAPAN; MIXED OXIDE FUELS; PLUTONIUM; REACTOR CORES; REACTOR LATTICES; REACTOR PHYSICS; RESEARCH PROGRAMS
- Descriptors DEC
- ACTINIDES; ASIA; DEVELOPED COUNTRIES; ELEMENTS; ENERGY SOURCES; ENRICHED URANIUM REACTORS; FUELS; MANAGEMENT; MATERIALS; METALS; NUCLEAR FUELS; NUCLEAR MATERIALS MANAGEMENT; POWER REACTORS; REACTOR COMPONENTS; REACTOR MATERIALS; REACTORS; SOLID FUELS; THERMAL REACTORS; TRANSURANIUM ELEMENTS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-921102--.