Basic data generation and pressure loss coefficient evaluation for HANARO core thermal-hydraulic analyses
Description
MATRA-h, a HANARO subchannel analysis computer code, is used to evaluate thermal margin of the HANARO fuel. It's capability includes the assessments of CHF, ONB margin, and fuel temperature. In this report, basic input data and core design parameters required to perform the subchannel analysis with MATRA-h code are collected. These data include the subchannel geometric data, thermal-hydraulic correlations, empirical constants and material properties. The friction and form loss coefficients of the fuel assemblies were determined based on the results of the pressure drop test. At the same time, different form loss coefficients at the end plates and spacers are evaluated for various subchannels. The adequate correlations are applied to the evaluation of the form loss coefficients for various subchannels, which are corrected by measured values in order to have a same pressure drop at each flow channel. These basic input data and design parameters described in this report will be applied usefully to evaluate the thermal margin of the HANARO fuel. (author). 11 refs., 13 tabs., 11 figs
Availability note (English)
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30056145.pdf
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Additional details
Publishing Information
- Imprint Pagination
- 55 p.
- Report number
- KAERI/TR--1344/99
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 30056145
- Subject category
- S42: ENGINEERING; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- CRITICAL HEAT FLUX; FUEL ASSEMBLIES; HYDRAULICS; M CODES; PRESSURE COEFFICIENT; PRESSURE DROP; REACTOR CORES; RESEARCH AND TEST REACTORS; THERMAL ANALYSIS
- Descriptors DEC
- COMPUTER CODES; HEAT FLUX; REACTIVITY COEFFICIENTS; REACTOR COMPONENTS; REACTORS