United States Nuclear Regulatory Commission - Protecting People and the Environment

Analysis and Computational Predictions of CHF Position and Post-CHF Heat Transfer (NUREG/IA-0236)

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Publication Information

Date Published: May 2010

Prepared by:
B. Belhouachi, S.P. Walker, G.F. Hewitt

Nuclear Research Group
Mechanical Engineering Department
Imperial College
London SW7 2BX
UK

Prepared as part of:
The Agreement on Research Participation and Technical Exchange
Under the Thermal-Hydraulic Code Applications and Maintenance Program (CAMP)

A. Calvo, NRC Project Manager

Office of Nuclear Regulatory Research
U.S. Nuclear Regulatory Commission
Washington, DC 20555-0001

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Abstract

The objective of the current study is to investigate the capability of the US NRC TRACE code to predict the Critical Heat Flux (CHF) position and temperature profiles for different axial heat flux distributions in the reflooding of a hot single tube. Measurements of each of Bennett, Keeys and Becker were used for this.

Hydrodynamic and post-dryout heat transfer calculations were performed using TRACE Code. CHF and critical quality correlations (based on the ‘look-up’ tables of Groeneveld, the ‘local conditions’ hypothesis, and the boiling length/quality relationship) are usually implemented in system codes. Each of these has been used to analyze the experiments. These simulations showed that generally the CHF position was well predicted whereas the estimation of the wall temperature was not correct for particular ranges of mass and heat fluxes. This is investigated and possible causes, associated with ‘local conditions’ issues, are proposed.

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