Published February 2003 | Version v1
Journal article Metadata-only

Research progress of experiment on critical heat flux

Creators

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

Description

Critical heat flux (CHF) is an important restricted thermal parameter, which size directly affects safety and economy of reactors. The author presents experimental research progress on CHF for nuclear power plants in China, and compared with the experimental research progress on CHF in other countries, and points out the development direction of CHF experimental research in China which is to carry out full-length non-uniform heated rod bundle CHF experimental research

Additional details

Publishing Information

Journal Title
Nuclear Power Engineering
Journal Volume
24
Journal Issue
1
Journal Page Range
p. 24-27
ISSN
0258-0926

INIS

Country of Publication
China
Country of Input or Organization
China
INIS RN
34053649
Subject category
S42: ENGINEERING; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Descriptors DEI
BENCH-SCALE EXPERIMENTS; CHINA; CRITICAL HEAT FLUX; DEVELOPED COUNTRIES; DEVELOPING COUNTRIES; HEAT TRANSFER; HISTORICAL ASPECTS; HYDRAULICS; NUCLEAR POWER PLANTS; TEST FACILITIES
Descriptors DEC
ASIA; ENERGY TRANSFER; FLUID MECHANICS; HEAT FLUX; MECHANICS; NUCLEAR FACILITIES; POWER PLANTS; THERMAL POWER PLANTS