Published August 1995 | Version v1
Journal article

Evaluation of the thermal margin in a KOFA-loaded core by a multichannel analysis methodology

  • 1. Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

Description

A study has been performed to investigate the thermal margin increase by replacing the single-channel analysis model with a multichannel analysis model. A new critical heat flux(CHF) correlation, which is applicable to a 17 x 17 Korean Fuel Assembly(KOFA)-loaded core, was developed on the basis of the local conditions predicted by the subchannel analysis code, TORC. The hot subchannel analysis was carried out by using one-stage analysis methodology with a prescribed nodal layout of the core. The result of the analysis showed that more than 5% of the thermal margin can be recovered by introducing the TORC/KRB-1 system(multichannel analysis model) instead of the PUMA/ERB-2 system(single-channel analysis model). The thermal margin increase was attributed not only to the effect of the local thermal hydraulic conditions in the hot subchannel predicted by the code, but also to the effect of the characteristics of the CHF correlation. 10 figs., 5 tabs., 22 refs. (Author)

Additional details

Publishing Information

Journal Title
Journal of the Korean Nuclear Society
Journal Volume
27
Journal Issue
4
Journal Page Range
p. 518-531.
ISSN
0372-7327
CODEN
WJHKAW

INIS

Country of Publication
Korea, Republic of
Country of Input or Organization
Korea, Republic of
INIS RN
27068674
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Descriptors DEI
CRITICAL HEAT FLUX; FLUID FLOW; FUEL CHANNELS; HOT CHANNEL; REACTOR CHANNELS; REACTOR CORES; THERMAL ANALYSIS
Descriptors DEC
HEAT FLUX; REACTOR COMPONENTS