Published December 1991 | Version v1
Journal article Metadata-only

An evaluation model of core fuel management for research and test reactors

Creators

  • 1. China Nuclear Power Inst. (China)

Description

An evaluation model of core fuel management for research and test reactors has been suggested. For reactors loaded with fuel assemblies of different burnup, the evaluation model can be used to calculate core physical parameters such as core neutron multiplication factor, burnup increment, etc. This model can be used for in-core refuelling scheme comparison

Additional details

Publishing Information

Journal Title
Chinese Journal of Nuclear Science and Engineering
Journal Volume
11
Journal Issue
4
Series
Chin. J. Nucl. Sci. Eng.
Journal Page Range
294-307
ISSN
0258-0918
CODEN
HYGOD

INIS

Country of Publication
China
Country of Input or Organization
China
INIS RN
23076067
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Descriptors DEI
BURNUP; FUEL MANAGEMENT; MATHEMATICAL MODELS; MULTIPLICATION FACTORS; REACTOR CORES; REACTOR FUELING; RESEARCH AND TEST REACTORS; THERMAL NEUTRONS
Descriptors DEC
BARYONS; ELEMENTARY PARTICLES; FERMIONS; HADRONS; MANAGEMENT; NEUTRONS; NUCLEAR MATERIALS MANAGEMENT; NUCLEONS; REACTOR COMPONENTS; REACTORS