Abstract
Empirical Critical Heat Flux (CHF) correlations PI-3 having the widest range of validity for flow conditions in both hexagonal and square rod bundle geometries and compared with published CHF correlations are presented. They are valid for vertical water upflow through rod bundles with relatively wide and very tight rod lattices, and include axial and radial non-uniform heating. The correlations were developed with the use of more than 6000 data obtained from 119 electrically heated rod bundles. Comprehensive results of statistical evaluations of the new correlations are presented for various data bases. Also presented is a comparison of statistical evaluations of several well-known CHF correlations in the experimental data base used. A procedure which makes it possible to directly determine the probability that CHF does not occur is described for the purpose of nuclear safety assessment. (author) 8 tabs., 32 figs., 11 refs.
Pernica, R;
[1]
Cizek, J
[2]
- Ustav Jaderneho Vyzkumu CSKAE, Rez (Czechoslovakia)
- Statni Vyzkumny Ustav pro Stavbu Stroju, Prague (Czechoslovakia)
Citation Formats
Pernica, R, and Cizek, J.
PI-3 correlations and statistical evaluation results.
Serbia and Montenegro: N. p.,
1992.
Web.
Pernica, R, & Cizek, J.
PI-3 correlations and statistical evaluation results.
Serbia and Montenegro.
Pernica, R, and Cizek, J.
1992.
"PI-3 correlations and statistical evaluation results."
Serbia and Montenegro.
@misc{etde_10157685,
title = {PI-3 correlations and statistical evaluation results}
author = {Pernica, R, and Cizek, J}
abstractNote = {Empirical Critical Heat Flux (CHF) correlations PI-3 having the widest range of validity for flow conditions in both hexagonal and square rod bundle geometries and compared with published CHF correlations are presented. They are valid for vertical water upflow through rod bundles with relatively wide and very tight rod lattices, and include axial and radial non-uniform heating. The correlations were developed with the use of more than 6000 data obtained from 119 electrically heated rod bundles. Comprehensive results of statistical evaluations of the new correlations are presented for various data bases. Also presented is a comparison of statistical evaluations of several well-known CHF correlations in the experimental data base used. A procedure which makes it possible to directly determine the probability that CHF does not occur is described for the purpose of nuclear safety assessment. (author) 8 tabs., 32 figs., 11 refs.}
place = {Serbia and Montenegro}
year = {1992}
month = {Jan}
}
title = {PI-3 correlations and statistical evaluation results}
author = {Pernica, R, and Cizek, J}
abstractNote = {Empirical Critical Heat Flux (CHF) correlations PI-3 having the widest range of validity for flow conditions in both hexagonal and square rod bundle geometries and compared with published CHF correlations are presented. They are valid for vertical water upflow through rod bundles with relatively wide and very tight rod lattices, and include axial and radial non-uniform heating. The correlations were developed with the use of more than 6000 data obtained from 119 electrically heated rod bundles. Comprehensive results of statistical evaluations of the new correlations are presented for various data bases. Also presented is a comparison of statistical evaluations of several well-known CHF correlations in the experimental data base used. A procedure which makes it possible to directly determine the probability that CHF does not occur is described for the purpose of nuclear safety assessment. (author) 8 tabs., 32 figs., 11 refs.}
place = {Serbia and Montenegro}
year = {1992}
month = {Jan}
}