Published 1992 | Version v1
Journal article

Applications of a systematic homogenization theory for nodal diffusion methods

  • 1. Univ. of Virginia, Charlottesville (United States)

Description

The authors recently have developed a self-consistent and systematic lattice cell and fuel bundle homogenization theory based on a multiple spatial scales asymptotic expansion of the transport equation in the ratio of the mean free path to the reactor characteristics dimension for use with nodal diffusion methods. The mathematical development leads naturally to self-consistent analytical expressions for homogenized diffusion coefficients and cross sections and flux discontinuity factors to be used in nodal diffusion calculations. The expressions for the homogenized nuclear parameters that follow from the systematic homogenization theory (SHT) are different from those for the traditional flux and volume-weighted (FVW) parameters. The calculations summarized here show that the systematic homogenization theory developed recently for nodal diffusion methods yields accurate values for keff and assembly powers even when compared with the results of a fine mesh transport calculation. Thus, it provides a practical alternative to equivalence theory and GET (Ref. 3) and to simplified equivalence theory, which requires auxiliary fine-mesh calculations for assemblies embedded in a typical environment to determine the discontinuity factors and the equivalent diffusion coefficient for a homogenized assembly

Additional details

Publishing Information

Journal Title
Transactions of the American Nuclear Society
Journal Volume
66
Journal Page Range
p. 497-499.
ISSN
0003-018X
CODEN
TANSAO

Conference

Title
past, present, and future.
Acronym
Joint American Nuclear Society (ANS)/European Nuclear Society (ENS) international meeting on fifty years of controlled nuclear chain reaction
Dates
15-20 Nov 1992.
Place
Chicago, IL (United States).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
24050551
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
CROSS SECTIONS; HOMOGENIZATION METHODS; MATHEMATICAL MODELS; NEUTRON DIFFUSION EQUATION; NEUTRON FLUX; NEUTRON TRANSPORT THEORY; NODAL EXPANSION METHOD; REACTOR LATTICES
Descriptors DEC
CALCULATION METHODS; RADIATION FLUX; TRANSPORT THEORY

Optional Information

Secondary number(s)
CONF-921102--.