Evaluations and modifications of the EPRI-1 correlation on PWR critical heat flux predictions under normal and abnormal fuel conditions

Journal Article · Sat Nov 01 04:00:00 EST 1986 · Nucl. Technol.; (United States)

OSTI ID:5112137

Pei, B S; Chen, Y B; Shih, Y B; Lin, W S

The performance of the five critical heat flux (CHF) correlations with COBRA IIIC/MIT-1 code was evaluated. These correlations were evaluated against a data group comprised of 2943 axial nonuniform, rod bundle, first-order, and higher-rank CHF data points of pressurized water reactor (PWR) core geometries. Among these five CHF correlations, EPRI-1 is the most accurate and has the widest operating ranges. Two kinds of correction factors - cold-wall correction factors and the CHF local quality correction factor - were developed and introduced to EPRI-1 to improve its accuracy in PWR CHF predictions. An in-depth evaluation of the EPRI-1 correlation in the prediction of CHFs of three fuel element abnormalities was also performed. Heat flux spikes and blocked channel conditions have negligible effects on CHFs. For the adverse effects of rod bowing on CHFs, the severity of rod bowing effects depends on the percentage of gap closure between rods, and also on the presence of any thimble tube (cold wall) adjacent to the distorted subchannel. Rod bowing effect parameter correlations under cold-wall conditions were developed. These rod bowing effect parameters were tested; it was proved that they could closely describe the rod bowing effects with no apparent remaining residual trends.

• Research Organization: National Tsing-Hua Univ., Dept. of Nuclear Engineering, Hsinchu 300
• OSTI ID: 5112137
• Journal Information: Nucl. Technol.; (United States), Journal Name: Nucl. Technol.; (United States) Vol. 75:2; ISSN NUTYB
• Country of Publication: United States
• Language: English

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21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
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ACCURACY
C CODES
COMPUTER CODES
CORRECTIONS
CORRELATIONS
CRITICAL HEAT FLUX
FUEL ELEMENTS
HEAT FLUX
PWR TYPE REACTORS
REACTOR COMPONENTS
REACTOR CORES
REACTORS
ROD BUNDLES
STEADY-STATE CONDITIONS
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WATER MODERATED REACTORS