Published May 2001 | Version v1
Miscellaneous

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

Part of:
Proceedings of the Korean Nuclear Society spring meeting

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