Published 2012 | Version v1
Book

Feasibility of wavelet expansion methods to treat the energy variable

  • 1. Research Inst. of Nuclear Engineering, Univ. of Fukui, Kanawa-cho 1-2-4, 914-0055, Fukui-ken, Tsuruga-shi (Japan)

Description

This paper discusses the use of the Discrete Wavelet Transform (DWT) to implement a functional expansion of the energy variable in neutron transport. The motivation of the work is to investigate the possibility of adapting the expansion level of the neutron flux in a material region to the complexity of the cross section in that region. If such an adaptive treatment is possible, 'simple' material regions (e.g., moderator regions) require little effort, while a detailed treatment is used for 'complex' regions (e.g., fuel regions). Our investigations show that in fact adaptivity cannot be achieved. The most fundamental reason is that in a multi-region system, the energy dependence of the cross section in a material region does not imply that the neutron flux in that region has a similar energy dependence. If it is chosen to sacrifice adaptivity, then the DWT method can be very accurate, but the complexity of such a method is higher than that of an equivalent hyper-fine group calculation. The conclusion is thus that, unfortunately, the DWT approach is not very practical. (authors)

Additional details

Publishing Information

Publisher
American Nuclear Society - ANS
Imprint Place
La Grange Park, IL (United States)
ISBN
978-0-89448-085-9
Imprint Pagination
12 p.

Conference

Title
Conference on Advances in Reactor Physics - Linking Research, Industry, and Education
Acronym
PHYSOR 2012
Dates
15-20 Apr 2012
Place
Knoxville, TN (United States)

INIS

Country of Publication
United States
Country of Input or Organization
France
INIS RN
44063539
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
CROSS SECTIONS; ENERGY DEPENDENCE; EXPANSION; MODERATORS; NEUTRON FLUX; NEUTRON TRANSPORT; NUCLEAR FUELS
Descriptors DEC
ENERGY SOURCES; FUELS; MATERIALS; NEUTRAL-PARTICLE TRANSPORT; RADIATION FLUX; RADIATION TRANSPORT; REACTOR MATERIALS

Optional Information

Notes
4 refs.