Published July 2006 | Version v1
Journal article Metadata-only

Parameters calculation of fuel assembly with complex geometry

Creators

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

Description

The code DRAGON was developed for CANDU reactor by Ecole Polytechnique de Montreal of Canada. In order to validate the DRAGON code's applicability for complex geometry fuel assembly calculation, the rod shape fuel assembly of PWR benchmark problem and the plate shape fuel assembly of MTR benchmark problem were analyzed by DRAGON code. Some other shape fuel assemblies were also discussed simply. Calculation results show that the DRAGON code can be used to calculate variform fuel assembly and the precision is high. (authors)

Additional details

Publishing Information

Journal Title
Atomic Energy Science and Technology
Journal Volume
40
Journal Issue
4
Journal Page Range
p. 433-438
ISSN
1000-6931

INIS

Country of Publication
China
Country of Input or Organization
China
INIS RN
38057029
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Descriptors DEI
ACCURACY; BENCHMARKS; CANDU TYPE REACTORS; D CODES; FUEL ASSEMBLIES; FUEL PLATES; FUEL RODS; GEOMETRY; MTR REACTOR; PARAMETRIC ANALYSIS; PWR TYPE REACTORS; SHAPE; VALIDATION
Descriptors DEC
COMPUTER CODES; ENRICHED URANIUM REACTORS; FUEL ELEMENTS; HEAVY WATER MODERATED REACTORS; IRRADIATION REACTORS; MATERIALS TESTING REACTORS; MATHEMATICS; POWER REACTORS; PRESSURE TUBE REACTORS; REACTOR COMPONENTS; REACTORS; TANK TYPE REACTORS; TESTING; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS