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Improvement of analysis system for core thermal hydraulic field and CHF

Technical Report:

Abstract

The objectives of this research are to establish the analysis system of thermal hydraulic field of KOFA(Korean Fuel Assembly) core using the multichannel analysis code TORC, and to improve the analysis system for critical heat flux (CHF) according to the multichannel analysis system. The thermal hydraulic models included in TORC code were reviewed, and the value of turbulent mixing parameter, which was found to be the most sensitive parameter to the variation of fuel assembly geometry, was determined from the thermal mixing test data of KOFA. The performance of the existing CHF correlations were evaluated through the CHF test data of KOFA using the TORC code models which were adjusted to KOFA. Furthermore, new CHF correlations were developed to improve the performance of CHF analysis system by using TORC code. In addition, the model for the evaluation of transition core DNBR penalty using TORC code was developed, and the application of that model for Ulchin 1/2 mixed core of KOFA and FRA-STD FA shows that about 2% of DNBR margin can be recovered in the transition core. (Author).
Authors:
Hwang, Dae Hyun; Park, Jong Ryul; Chun, Tae Hyun; Hong, Seung Dug; Kwon, Hyuk Sung [1] 
  1. Korea Atomic Energy Research Inst., Daeduk (Korea, Republic of)
Publication Date:
Mar 01, 1991
Product Type:
Technical Report
Report Number:
KAERI/RR-980/90
Reference Number:
SCA: 420400; 220300; PA: AIX-23:014742; SN: 92000646876
Resource Relation:
Other Information: PBD: Mar 1991
Subject:
42 ENGINEERING; 22 GENERAL STUDIES OF NUCLEAR REACTORS; CRITICAL HEAT FLUX; THERMAL ANALYSIS; HYDRAULICS; REACTOR CORES; COMPUTER CODES; EVALUATION; FUEL ASSEMBLIES; THERMAL DIFFUSION; TURBULENT FLOW; 420400; 220300; HEAT TRANSFER AND FLUID FLOW; FUEL ELEMENTS
OSTI ID:
10113168
Research Organizations:
Korea Atomic Energy Research Inst., Daeduk (Korea, Republic of)
Country of Origin:
Korea, Republic of
Language:
Korean
Other Identifying Numbers:
Other: ON: DE92615043; TRN: KR9100130014742
Availability:
OSTI; NTIS (US Sales Only); INIS
Submitting Site:
INIS
Size:
100 p.
Announcement Date:
Jun 30, 2005

Technical Report:

Citation Formats

Hwang, Dae Hyun, Park, Jong Ryul, Chun, Tae Hyun, Hong, Seung Dug, and Kwon, Hyuk Sung. Improvement of analysis system for core thermal hydraulic field and CHF. Korea, Republic of: N. p., 1991. Web.
Hwang, Dae Hyun, Park, Jong Ryul, Chun, Tae Hyun, Hong, Seung Dug, & Kwon, Hyuk Sung. Improvement of analysis system for core thermal hydraulic field and CHF. Korea, Republic of.
Hwang, Dae Hyun, Park, Jong Ryul, Chun, Tae Hyun, Hong, Seung Dug, and Kwon, Hyuk Sung. 1991. "Improvement of analysis system for core thermal hydraulic field and CHF." Korea, Republic of.
@misc{etde_10113168,
title = {Improvement of analysis system for core thermal hydraulic field and CHF}
author = {Hwang, Dae Hyun, Park, Jong Ryul, Chun, Tae Hyun, Hong, Seung Dug, and Kwon, Hyuk Sung}
abstractNote = {The objectives of this research are to establish the analysis system of thermal hydraulic field of KOFA(Korean Fuel Assembly) core using the multichannel analysis code TORC, and to improve the analysis system for critical heat flux (CHF) according to the multichannel analysis system. The thermal hydraulic models included in TORC code were reviewed, and the value of turbulent mixing parameter, which was found to be the most sensitive parameter to the variation of fuel assembly geometry, was determined from the thermal mixing test data of KOFA. The performance of the existing CHF correlations were evaluated through the CHF test data of KOFA using the TORC code models which were adjusted to KOFA. Furthermore, new CHF correlations were developed to improve the performance of CHF analysis system by using TORC code. In addition, the model for the evaluation of transition core DNBR penalty using TORC code was developed, and the application of that model for Ulchin 1/2 mixed core of KOFA and FRA-STD FA shows that about 2% of DNBR margin can be recovered in the transition core. (Author).}
place = {Korea, Republic of}
year = {1991}
month = {Mar}
}