Published August 2002 | Version v1
Book Metadata-only

Direction and region dependent cross sections for use to MOX fuel analysis

Creators

  • 1. Osaka University, Department of Nuclear Engineering, Suita, Osaka (Japan)

Description

When the continuous energy transport equation is integrated over an energy interval, the total cross section for the energy group becomes region and angular dependent, because the angular dependent neutron flux must be used as a weight. Usually the angular dependence is neglected. We investigate the approximation, and show that the error is proportional to the product of the neutron current and the difference between the flux weighted total cross section and the current weighted total cross section. The formulation of angular dependent cross section is derived in 1-dimensional slab geometry based on the multiband method. The numerical results are shown for UO2 and MOX fueled cells. (author)

Availability note (English)

Available from the Internet at URL https://doi.org/10.1080/00223131.2002.10875284
Part of:
Proceedings of the international conference on nuclear data for science and technology

Additional details

Identifiers

DOI
10.1080/00223131.2002.10875284;

Publishing Information

Publisher
Atomic Energy Society of Japan
Imprint Place
Tokyo (Japan)
Imprint Title
Proceedings of the international conference on nuclear data for science and technology
Imprint Pagination
1547 p.
Journal Page Range
p. 1057-1060

Conference

Title
International conference on nuclear data for science and technology
Acronym
ND 2001
Dates
7-12 Oct 2001
Place
Tsukuba, Ibaraki (Japan)

INIS

Country of Publication
Japan
Country of Input or Organization
Japan
INIS RN
51063322
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
ANGULAR DISTRIBUTION; CROSS SECTIONS; ENERGY TRANSFER; FUEL CELLS; MIXED OXIDE FUELS; MODERATORS; NEUTRON FLUX; NEUTRON SPECTRA; REACTOR CORES; THERMAL REACTORS; TOTAL CROSS SECTIONS; URANIUM 238; URANIUM DIOXIDE
Descriptors DEC
ACTINIDE COMPOUNDS; ACTINIDE NUCLEI; ALPHA DECAY RADIOISOTOPES; CHALCOGENIDES; CROSS SECTIONS; DIRECT ENERGY CONVERTERS; DISTRIBUTION; ELECTROCHEMICAL CELLS; ENERGY SOURCES; EVEN-EVEN NUCLEI; FUELS; HEAVY NUCLEI; ISOTOPES; MATERIALS; NUCLEAR FUELS; NUCLEI; OXIDES; OXYGEN COMPOUNDS; RADIATION FLUX; RADIOISOTOPES; REACTOR COMPONENTS; REACTOR MATERIALS; REACTORS; SOLID FUELS; SPECTRA; SPONTANEOUS FISSION RADIOISOTOPES; URANIUM COMPOUNDS; URANIUM ISOTOPES; URANIUM OXIDES; YEARS LIVING RADIOISOTOPES

Optional Information

Notes
4 refs., 6 figs., 1 tab.; This record replaces 34024871 Imprint:Published as supplement 2 of Journal of Nuclear Science and Technology in 2 volumes