Thermal hydraulic conceptual design of KALIMER breeder core with its configuration development
Creators
- 1. Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)
Description
Coolant flow distributions to the assemblies by flow grouping and coolant/fuel temperature calculations, especially the peak pin temperatures in each assembly, is the major work in an LMR core thermal hydraulic conceptual design and analysis. In the KALIMER core thermal hydraulic design, sodium coolant flow is distributed to each assembly with the overall goal of equalizing the peak cladding midwall temperatures, thus pin cladding damage accumulation and pin reliability. KALIMER breeder core configuration development work is summarized in this paper. The conceptual design procedure and methodology used for the KALIMER core thermal hydraulic design are also explained. The major thermal hydraulic calculation results of the KALIMER breeder equilibrium core, a heterogeneous core fueled with U-Pu-Zr ternary alloy fuel, are shown and compared to those of the KALIMER core fueled with U-Zr binary alloy metallic fuels. (author)
Additional details
Publishing Information
- Publisher
- Atomic Energy Society of Japan
- Imprint Place
- Tokyo (Japan)
- Imprint Title
- Proceedings of NTHAS2: Second Japan-Korea symposium on nuclear thermal hydraulics and safety
- Imprint Pagination
- 800 p.
- Journal Page Range
- p. 104-109
Conference
- Title
- 2. Japan-Korea symposium on nuclear thermal hydraulics and safety
- Acronym
- NTHAS2
- Dates
- 15-18 Oct 2000
- Place
- Fukuoka (Japan)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 32004688
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CLADDING; CONFIGURATION; DESIGN; EVALUATION; FUEL RODS; HYDRAULICS; LMFBR TYPE REACTORS; PERFORMANCE; PLUTONIUM ALLOYS; REACTOR CORES; REACTOR SAFETY; SAFETY ANALYSIS; TEMPERATURE DISTRIBUTION; TERNARY ALLOY SYSTEMS; THERMODYNAMICS; URANIUM ALLOYS; ZIRCONIUM ALLOYS
- Descriptors DEC
- ACTINIDE ALLOYS; ALLOY SYSTEMS; ALLOYS; BREEDER REACTORS; DEPOSITION; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; FLUID MECHANICS; FUEL ELEMENTS; LIQUID METAL COOLED REACTORS; MECHANICS; REACTOR COMPONENTS; REACTORS; SAFETY; SURFACE COATING; TRANSITION ELEMENT ALLOYS
Optional Information
- Notes
- 19 refs., 4 figs., 2 tabs.