Published June 2013 | Version v1
Journal article Metadata-only

Sensitivity study of feedback parameters for thermal-hydraulic coupling code

Creators

  • 1. Wuhan 2nd Ship Design and Research Institute, Wuhan (China)
  • 2. College of Nuclear Science and Technology, Harbin Engineering University, Harbin (China)

Description

Thermal-hydraulic coupling code is important for reactor core design. In this paper, the reactor core of Qinshan-II nuclear power plant was selected as study object. CASMO4E was used to calculate the assembly homogenized parameters. The sensitivity study of independent parameters used in thermal-hydraulic coupling code was finished. Two kinds of cross-section tables were established, and the error analysis of these two cross section tables was finished. (authors)

Additional details

Publishing Information

Journal Title
Atomic Energy Science and Technology
Journal Volume
47
Journal Issue
suppl
Journal Page Range
p. 283-286
ISSN
1000-6931

INIS

Country of Publication
China
Country of Input or Organization
China
INIS RN
48069003
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Descriptors DEI
C CODES; COUPLING; CROSS SECTIONS; DATA; DESIGN; ERRORS; FEEDBACK; NUCLEAR POWER PLANTS; QINSHAN-2-1 REACTOR; REACTOR CORES; REACTOR PHYSICS; SENSITIVITY ANALYSIS; THERMAL HYDRAULICS
Descriptors DEC
COMPUTER CODES; ENRICHED URANIUM REACTORS; FLUID MECHANICS; HYDRAULICS; INFORMATION; MECHANICS; NUCLEAR FACILITIES; PHYSICS; POWER PLANTS; POWER REACTORS; PWR TYPE REACTORS; REACTOR COMPONENTS; REACTORS; THERMAL POWER PLANTS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
1 fig., 3 tabs., 3 refs.