Published 2009 | Version v1
Miscellaneous

Study on characteristic of CHF in the narrow channel

  • 1. North China Electricity Power University, Beijing (Korea, Republic of)

Description

The narrow channel is used in the advanced PWR (pressurized water reactor). The CHF (critical heat flux) that happens in the PWR is directly related to the characteristic of thermal-hydraulic. The results of the calculation under the same conditions are compared, through research of the calculating models about CHF especially applied in the narrow channel in the world. The influence on the CHF is analyzed, which caused by the geometry parameters in the narrow channel, flow characteristic and heating parameters. The characteristic of the CHF in the narrow channel is put out. The exact description that CHF happened in the narrow channel is established. So the safety of the advanced reactor is ensured

Part of:
Proceedings for the Fourth Korea-China Workshop on Nuclear Reactor Thermal-Hydraulics (WORTH-4)

Additional details

Publishing Information

Publisher
KAERI
Imprint Place
Daejeon (Korea, Republic of)
Imprint Title
Proceedings for the Fourth Korea-China Workshop on Nuclear Reactor Thermal-Hydraulics (WORTH-4)
Imprint Pagination
534 p.
Journal Page Range
p. 521-523

Conference

Title
4. Korea-China Workshop on Nuclear Reactor Thermal-Hydraulics
Dates
18-20 May 2009
Place
Jeju (Korea, Republic of)

INIS

Country of Publication
Korea, Republic of
Country of Input or Organization
Korea, Republic of
INIS RN
40082040
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
COMPUTER CALCULATIONS; CRITICAL HEAT FLUX; GEOMETRY; PWR TYPE REACTORS; THERMAL HYDRAULICS
Descriptors DEC
ENRICHED URANIUM REACTORS; FLUID MECHANICS; HEAT FLUX; HYDRAULICS; MATHEMATICS; MECHANICS; POWER REACTORS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
6 refs, 3 figs, 1 tab