Published February 2013 | Version v1
Journal article Metadata-only

Preliminary study on SCWR fuel rod performance analysis code

Creators

  • 1. Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu (China)

Description

A SCWR fuel rod performance analysis code is developed in this paper, based on a PWR fuel rod performance analysis code, by analyzing its model and calculation method. The new code is developed on the basis of intensive analyses of SCWR characteristics, focused on the coolant-fuel rod outside surface heat transfer and cladding properties model. Lastly, the performance analysis code was successfully tested on fuel rod of 1/8 HPLWR fuel assembly, then the paper compares the results with that from the sub-channel analysis code ATHAS, which shows that the error is small. (authors)

Additional details

Publishing Information

Journal Title
Nuclear Power Engineering
Journal Volume
34
Journal Issue
1
Journal Page Range
p. 97-100, 120
ISSN
0258-0926

INIS

Country of Publication
China
Country of Input or Organization
China
INIS RN
47112215
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S97: MATHEMATICAL METHODS AND COMPUTING;
Descriptors DEI
CALCULATION METHODS; COMPARATIVE EVALUATIONS; COOLANTS; FUEL ASSEMBLIES; FUEL CANS; FUEL RODS; HEAT TRANSFER; PERFORMANCE; PWR TYPE REACTORS; S CODES; SUPERCRITICAL STATE; SURFACES; WATER COOLED REACTORS
Descriptors DEC
COMPUTER CODES; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; EVALUATION; FUEL ELEMENTS; POWER REACTORS; REACTOR COMPONENTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
7 figs., 3 tabs., 5 refs.