A comparison of two nodal codes : Advanced nodal code (ANC) and analytic function expansion nodal (AFEN) code
Creators
- 1. Korea Nuclear Fuel Co. Ltd., Taejeon (Korea, Republic of)
Description
Modern nodal methods usually employs the transverse integration technique in order to reduce a multi-dimensional diffusion equation to one-dimensional diffusion equations. The use of the transverse integration technique requires two major approximations such as a transverse leakage approximation and a one-dimensional flux approximation. Both the transverse leakage and the one-dimensional flux are approximated by polynomials. ANC (Advanced Nodal Code) developed by Westinghouse employs a modern nodal expansion method for the flux calculation, the equivalence theory for the homogenization error reduction and a group theory for pin power recovery. Unlike the conventional modern nodal methods, AFEN (Analytic Function Expansion Nodal) method expands homogeneous flux distributions within a node into non-separable analytic basis functions, which eliminate two major approximations of the modern nodal methods. A comparison study of AFEN with ANC has been performed to see the applicability of AFEN to commercial PWR and different types of reactors such as MOX fueled reactor. The qualification comparison results demonstrate that AFEN methodology is accurate enough to apply for commercial PWR analysis. The results show that AFEN provides very accurate results (core multiplication factor and assembly power distribution) for cores that exhibit strong flux gradients as in a MOX loaded core. (author)
Additional details
Publishing Information
- Imprint Title
- International conference on the physics of reactors PHYSOR96, vol. 1
- Imprint Pagination
- 615 p.
- Journal Page Range
- p. A/288-A/293.
Conference
- Title
- international conference on the physics of reactors 1996.
- Acronym
- PHYSOR96
- Dates
- 16-20 Sep 1996.
- Place
- Mito (Japan).
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 28021771
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- A CODES; COMPARATIVE EVALUATIONS; ERRORS; FUEL PINS; NEUTRON DIFFUSION EQUATION; NEUTRON LEAKAGE; NODAL EXPANSION METHOD; POLYNOMIALS; POWER DISTRIBUTION; PWR TYPE REACTORS; REACTOR CORES
- Descriptors DEC
- CALCULATION METHODS; COMPUTER CODES; DISTRIBUTION; ENRICHED URANIUM REACTORS; EVALUATION; FUEL ELEMENTS; FUNCTIONS; POWER REACTORS; REACTOR COMPONENTS; REACTORS; SPATIAL DISTRIBUTION; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- Imprint:Published in 4 volumes.