Published February 2012 | Version v1
Journal article Metadata-only

Neutronics calculation of fusion-fission hybrid breeding thorium fuel assembly

Creators

  • 1. School of Nuclear Science and Technology, North China Electric Power University, Beijing (China)

Description

A preliminary comparative study of the physical properties among 17 × 17 fuel assembly in PWRs for prototype between uranium assembly and hybrid breeding thorium-based assembly has been investigated respectively using the DRAGON software. The parameters such as fuel temperature coefficient, moderator temperature coefficient and that variation as a function of operation period have been investigated. Results show that the neutron properties of uranium-based assembly and hybrid breeding thorium-based assembly are similitude, but MA mass of hybrid breeding thorium-based assembly is evidently less than those of the uranium assembly. (authors)

Additional details

Publishing Information

Journal Title
Nuclear Power Engineering
Journal Volume
33
Journal Issue
1
Journal Page Range
p. 129-133
ISSN
0258-0926

INIS

Country of Publication
China
Country of Input or Organization
China
INIS RN
45102764
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Descriptors DEI
BREEDING; COMPUTER CODES; FISSION; FUEL ASSEMBLIES; HYBRID REACTORS; HYBRIDIZATION; MASS; MODERATORS; NEUTRONS; NUCLEAR FUELS; OPERATION; PHYSICAL PROPERTIES; PWR TYPE REACTORS; TEMPERATURE COEFFICIENT; THORIUM; URANIUM; VARIATIONS
Descriptors DEC
ACTINIDES; BARYONS; ELEMENTARY PARTICLES; ELEMENTS; ENERGY SOURCES; ENRICHED URANIUM REACTORS; FERMIONS; FUELS; HADRONS; MATERIALS; METALS; NUCLEAR FUEL CONVERSION; NUCLEAR REACTIONS; NUCLEONS; POWER REACTORS; REACTIVITY COEFFICIENTS; REACTOR MATERIALS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
11 figs., 2 tabs., 12 refs.