Published 2006 | Version v1
Book

Impact of Different Correlations on TRACEv4.160 Predicted Critical Heat Flux

  • 1. Laboratory for Reactor Physics and Systems Behaviour, Paul Scherrer Institute (Switzerland)

Description

This paper presents an independent assessment of the Critical Heat Flux (CHF) models implemented in TRACEv4.160 with data from the experiments carried out at the Royal Institute of Technology (RIT) in Stockholm, Sweden, with single vertical uniformly heated 7.0 m long tubes. In previous CHF assessment studies with TRACE, it was noted that, although the overall code predictions in long single tubes with inner diameters of 1.0 to 2.49 cm agreed rather well with the results of experiments (with r.m.s. error being 25.6%), several regions of pressure and coolant mass flux could be identified, in which the code strongly under-predicts or over-predicts the CHF. In order to evaluate the possibility of improving the code performance, some of the most widely used and assessed CHF correlations were additionally implemented in TRACEv4.160, namely Bowring, Levitan - Lantsman, and Tong-W3. The results obtained for the CHF predictions in single tubes with uniform axial heat flux by using these correlations, were compared to the results produced with the standard TRACE correlations (Biasi and CISE-GE), and with the experimental data from RIT, which covered a broad range of pressures (3-20 MPa) and coolant mass fluxes (500-3000 kg/m2s). Several hundreds of experimental points were calculated to cover the parameter range mentioned above for the evaluation of the newly implemented correlations in the TRACEv4.160 code. (author)

Part of:
Validation of the TRACE Code Against Post-Dryout Experiments in Tubes and Annuli

Additional details

Publishing Information

Publisher
American Nuclear Society - ANS
Imprint Place
La Grange Park (United States)
ISBN
0-89448-698-5
Imprint Title
Proceedings of the 2006 international congress on advances in nuclear power plants - ICAPP'06
Imprint Pagination
2734 p.
Journal Page Range
p. 1608-1615

Conference

Title
2006 International congress on advances in nuclear power plants - ICAPP'06
Dates
4-8 Jun 2006
Place
Reno - Nevada (United States)

INIS

Country of Publication
United States
Country of Input or Organization
France
INIS RN
39042897
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
COOLANTS; CORRELATIONS; CRITICAL HEAT FLUX; ERRORS; EVALUATION; FORECASTING; PERFORMANCE; SWEDEN; TUBES
Descriptors DEC
DEVELOPED COUNTRIES; EUROPE; HEAT FLUX; SCANDINAVIA; WESTERN EUROPE

Optional Information

Notes
8 refs.