Analysis of fuel temperature coefficient of reactivity with two-region core system
Creators
- 1. Power Reactor and Nuclear Fuel Development Corp., Oarai, Ibaraki (Japan). Oarai Engineering Center
Description
Fuel temperature coefficients of reactivity have been analysed for DCA core with a central channel of raised temperature. The present model for the analysis of the experiment is based on the following two considerations ; (1) a large difference of nuclear characteristics between the central channel that is made of stainless steel and the outer channels of aluminum in the driver region, (2) a slight change in neutron temperature of the high temperature region where there is no moderating material. The present analysis explains successfully the qualitative features of the experiment, including dependencies of temperature coefficients on fuel enrichment and temperature range, and the linear coefficient of cladding material. The quantitative agreement, however, is not so good except for 1.5% UO2 fuel. (JPN.)
Availability note (English)
MF available from INIS under the Report Number.
Files
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Additional details
Publishing Information
- Imprint Pagination
- 31 p.
- Report number
- PNC-N--941-75-59
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 8281642
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Descriptors DEI
- ACCURACY; DCA REACTOR; FUEL ASSEMBLIES; GROUP CONSTANTS; HETEROGENEOUS EFFECTS; N CODES; REACTIVITY; REACTOR CORES; SLIGHTLY ENRICHED URANIUM; TEMPERATURE COEFFICIENT; TEMPERATURE DEPENDENCE; THERMAL EXPANSION; THERMAL NEUTRONS
- Descriptors DEC
- ACTINIDES; BARYONS; COMPUTER CODES; CROSS SECTIONS; ELEMENTARY PARTICLES; ELEMENTS; ENRICHED URANIUM; EXPANSION; EXPERIMENTAL REACTORS; FERMIONS; HADRONS; HEAVY WATER COOLED REACTORS; HEAVY WATER MODERATED REACTORS; ISOTOPE ENRICHED MATERIALS; METALS; NEUTRONS; NUCLEONS; REACTIVITY COEFFICIENTS; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; TANK TYPE REACTORS; URANIUM; ZERO POWER REACTORS