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Prediction of critical heat flux in fuel assemblies using a CHF table method

Abstract

A CHF table method has been assessed in this study for rod bundle CHF predictions. At the conceptual design stage for a new reactor, a general critical heat flux (CHF) prediction method with a wide applicable range and reasonable accuracy is essential to the thermal-hydraulic design and safety analysis. In many aspects, a CHF table method (i.e., the use of a round tube CHF table with appropriate bundle correction factors) can be a promising way to fulfill this need. So the assessment of the CHF table method has been performed with the bundle CHF data relevant to pressurized water reactors (PWRs). For comparison purposes, W-3R and EPRI-1 were also applied to the same data base. Data analysis has been conducted with the subchannel code COBRA-IV-I. The CHF table method shows the best predictions based on the direct substitution method. Improvements of the bundle correction factors, especially for the spacer grid and cold wall effects, are desirable for better predictions. Though the present assessment is somewhat limited in both fuel geometries and operating conditions, the CHF table method clearly shows potential to be a general CHF predictor. 8 refs., 3 figs., 3 tabs. (Author)
Authors:
Chun, Tae Hyun; Hwang, Dae Hyun; Bang, Je Geon; [1]  Baek, Won Pil; Chang, Soon Heung [2] 
  1. Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)
  2. Korea Advance Institute of Science and Technology, Taejon (Korea, Republic of)
Publication Date:
Dec 31, 1997
Product Type:
Conference
Report Number:
ETDE/KR-99732628; CONF-9710296-
Reference Number:
SCA: 420400; 220300; PA: KR-99:000310; EDB-99:037436; SN: 99002059937
Resource Relation:
Conference: Korean Nuclear Society autumn meeting, Taegu (Korea, Republic of), 24-25 Oct 1997; Other Information: PBD: 1997; Related Information: Is Part Of Proceedings of the korean nuclear society autumn meeting vol I, October 24-25, 1997 Taegu, Korea; PB: 797 p.
Subject:
42 ENGINEERING NOT INCLUDED IN OTHER CATEGORIES; 22 NUCLEAR REACTOR TECHNOLOGY; CRITICAL HEAT FLUX; HEAT TRANSFER; FUEL ASSEMBLIES; FUEL ELEMENTS; FORECASTING; EVALUATION; FUEL ELEMENT CLUSTERS; THERMAL ANALYSIS; HYDRAULICS; SAFETY; CORRECTIONS; PWR TYPE REACTORS; COMPARATIVE EVALUATIONS; C CODES; SPACERS; WALL EFFECTS
OSTI ID:
324146
Research Organizations:
Korean Nuclear Society, Taejon (Korea, Republic of)
Country of Origin:
Korea, Republic of
Language:
English
Other Identifying Numbers:
Other: ON: DE99732628; TRN: KR9900310
Availability:
OSTI as DE99732628
Submitting Site:
KR
Size:
pp. 534-539
Announcement Date:

Citation Formats

Chun, Tae Hyun, Hwang, Dae Hyun, Bang, Je Geon, Baek, Won Pil, and Chang, Soon Heung. Prediction of critical heat flux in fuel assemblies using a CHF table method. Korea, Republic of: N. p., 1997. Web.
Chun, Tae Hyun, Hwang, Dae Hyun, Bang, Je Geon, Baek, Won Pil, & Chang, Soon Heung. Prediction of critical heat flux in fuel assemblies using a CHF table method. Korea, Republic of.
Chun, Tae Hyun, Hwang, Dae Hyun, Bang, Je Geon, Baek, Won Pil, and Chang, Soon Heung. 1997. "Prediction of critical heat flux in fuel assemblies using a CHF table method." Korea, Republic of.
@misc{etde_324146,
title = {Prediction of critical heat flux in fuel assemblies using a CHF table method}
author = {Chun, Tae Hyun, Hwang, Dae Hyun, Bang, Je Geon, Baek, Won Pil, and Chang, Soon Heung}
abstractNote = {A CHF table method has been assessed in this study for rod bundle CHF predictions. At the conceptual design stage for a new reactor, a general critical heat flux (CHF) prediction method with a wide applicable range and reasonable accuracy is essential to the thermal-hydraulic design and safety analysis. In many aspects, a CHF table method (i.e., the use of a round tube CHF table with appropriate bundle correction factors) can be a promising way to fulfill this need. So the assessment of the CHF table method has been performed with the bundle CHF data relevant to pressurized water reactors (PWRs). For comparison purposes, W-3R and EPRI-1 were also applied to the same data base. Data analysis has been conducted with the subchannel code COBRA-IV-I. The CHF table method shows the best predictions based on the direct substitution method. Improvements of the bundle correction factors, especially for the spacer grid and cold wall effects, are desirable for better predictions. Though the present assessment is somewhat limited in both fuel geometries and operating conditions, the CHF table method clearly shows potential to be a general CHF predictor. 8 refs., 3 figs., 3 tabs. (Author)}
place = {Korea, Republic of}
year = {1997}
month = {Dec}
}