Optimized core design of high converting pressure-tube type LWR
Description
An optimization of conceptual nuclear design was done for a high-converting pressure-tube type light water cooled reactor (HCPLWR) with an once-through thorium cycle. Thorium blanket fuel bundle are designed to stay about 10 years within a light water cooled pressure tube, whereas uranium driver fuel bundles are to be refueled by on-power refueling mode with about 780 EFPD discharge burnup rate. Fuel rod bundles are configured in hexagonal lattice array in a similar size of those of CANDU. Fuel pin size is the same with conventional PWR rod, however but the radius of blanket rod is a little lager than that of conventional PWR. Sixteen core design options were tested and the optimum design option was sought for. The optimized core design has 1 to 3 volume ratio of driver channel and blanket channel, which shows a higher conversion ratio than conventional LWR. Driver channels are loaded with U-10%Zr alloy fuels (enriched with 15 w/o U-235) and blanket channels are loaded with new fuels, which consist of pyrocarbon-coated UCO particles (enriched with 5 w/o U-235) and pyrocarbon-coated ThO2 particles in a graphite matrix
Additional details
Publishing Information
- Publisher
- KNS
- Imprint Place
- Taejon (Korea, Republic of)
- Imprint Title
- Proceedings of the Korean Nuclear Society autumn meeting
- Imprint Pagination
- [CD-ROM]
- Journal Page Range
- [8 p.]
Conference
- Title
- 1998 autumn meeting of the Korean Nuclear Society
- Dates
- 30-31 Oct 1998
- Place
- Seoul (Korea, Republic of)
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 32066902
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- BURNUP; CANDU TYPE REACTORS; CONVERSION RATIO; DESIGN; FUEL ELEMENT CLUSTERS; FUEL RODS; NUCLEAR FUELS; PRESSURE TUBES; PWR TYPE REACTORS; REACTOR CORES; THORIUM CYCLE
- Descriptors DEC
- ENERGY SOURCES; ENRICHED URANIUM REACTORS; FUEL ASSEMBLIES; FUEL CYCLE; FUEL ELEMENTS; FUELS; HEAVY WATER MODERATED REACTORS; MATERIALS; POWER REACTORS; PRESSURE TUBE REACTORS; REACTOR COMPONENTS; REACTOR MATERIALS; REACTORS; THERMAL REACTORS; TUBES; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 4 refs, 14 figs, 4 tabs