Published October 2000 | Version v1
Journal article Metadata-only

In-core fuel management calculation for high flux engineering test reactor

Creators

  • 1. Xi'an Jiaotong Univ., xi'an (China)
  • 2. Nuclear Power Inst. of China, Chengdu (China)

Description

In-core fuel management for High Flux Engineering Test Reactor (HFETR) is studied. The code package HFETRFM is encoded for the in-core fuel management of HFETR based on the cell calculation code WIMS-D4-CNPRI and the three-dimensional nodal diffusion code (SIXTUS-3) in Hex-Z Geometry. The calculated results of the first cycle of HFETR are in good agreement with the experimental values

Additional details

Publishing Information

Journal Title
Nuclear Power Engineering
Journal Volume
21
Journal Issue
5
Journal Page Range
p. 389-392, 397
ISSN
0258-0926

INIS

Country of Publication
China
Country of Input or Organization
China
INIS RN
32016889
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Descriptors DEI
BURNUP; CALCULATION METHODS; FLOWSHEETS; FUEL MANAGEMENT; GROUP CONSTANTS; H CODES; HFETR REACTOR; POISONING; REACTOR CORES; XENON
Descriptors DEC
COMPUTER CODES; CROSS SECTIONS; DIAGRAMS; ELEMENTS; ENRICHED URANIUM REACTORS; FLUIDS; GASES; INFORMATION; IRRADIATION REACTORS; MANAGEMENT; MATERIALS TESTING REACTORS; NONMETALS; NUCLEAR MATERIALS MANAGEMENT; RARE GASES; REACTOR COMPONENTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS