Inter-assembly thermal flux gradient correction of homogenization parameters based on one-dimensional heterogeneous interface model
- 1. Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)
- 2. Korea Advanced Institute of Science and Technology, Taejon (Korea, Republic of)
Description
To remedy the deficiency of single assembly homogenization with zero current boundary condition, proposed is a new approach solving a simple few-region one-dimensional one-group model consisting of pin columns of two adjacent assemblies. The cross-sections representing each pin column come from the single assembly homogenization. After solving analytically for the thermal flux across each interface of materials by the integral transport method, equivalence theory parameters or form factors are corrected during the nodal diffusion calculation to take into account the effect of the thermal flux gradient. The accuracy and the applicability of the proposed method were tested against a small benchmark problem consisting of MOX fuel and bare water reflector. The result shows that the method solving the one-dimensional model consisting of only six regions per interface can reduce significantly the errors in reconstructed pin powers near strong material interfaces
Additional details
Publishing Information
- Publisher
- KNS
- Imprint Place
- Taejon (Korea, Republic of)
- Imprint Title
- Proceedings of the Korean Nuclear Society spring meeting
- Imprint Pagination
- [ONE CDROM]
- Journal Page Range
- [15 p.]
Conference
- Title
- 2001 spring meeting of the Korean Nuclear Society
- Dates
- 24-25 May 2001
- Place
- Cheju (Korea, Republic of)
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 33040213
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- BENCHMARKS; CROSS SECTIONS; DIFFUSION; ERRORS; FUEL ASSEMBLIES; HEAT FLUX; HOMOGENIZATION METHODS; INTERFACES; MIXED OXIDE FUELS
- Descriptors DEC
- CALCULATION METHODS; ENERGY SOURCES; FUELS; MATERIALS; NUCLEAR FUELS; REACTOR MATERIALS; SOLID FUELS
Optional Information
- Notes
- 4 refs, 5 figs