Published June 2008 | Version v1
Journal article Metadata-only

Research on natural radiating heat in small reactor

Creators

  • 1. Institute of Naval Architecture and Power, Navy Univ. of Engineering, Wuhan (China)

Description

An analysis code of thermal-hydraulic parameters is developed for calculating natural radiating heat during reactor maintenance. The calculating results and experiment results are compared and it shows that the calculated results are precise and reliable. The code is a very important tool for obtaining the rule of thermal-hydraulic parameters when the core cooling ability is lost, and provides scientific and reliable technical basis for nuclear safety during maintenance. (authors)

Additional details

Publishing Information

Journal Title
Chinese Journal of Nuclear Science and Engineering
Journal Volume
28
Journal Issue
2
Journal Page Range
p. 163-166
ISSN
0258-0918

INIS

Country of Publication
China
Country of Input or Organization
China
INIS RN
42023115
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Descriptors DEI
COOLING; HEAT; HEAT TRANSFER; NATURAL CONVECTION; POWER REACTORS; RADIATION PROTECTION; REACTOR CORES; REACTOR MAINTENANCE; THERMAL HYDRAULICS; THERMAL RADIATION
Descriptors DEC
CONVECTION; ELECTROMAGNETIC RADIATION; ENERGY; ENERGY TRANSFER; FLUID MECHANICS; HEAT TRANSFER; HYDRAULICS; MAINTENANCE; MASS TRANSFER; MECHANICS; RADIATIONS; REACTOR COMPONENTS; REACTORS

Optional Information

Notes
6 figs., 3 refs.