Published 1985 | Version v1
Book

Applicability of critical heat flux correlations at low flow/ low pressure conditions

Creators

  • 1. British Nuclear Fuels plc, Springfields Works, Salwick, Preston, Lancashire PR4 OXJ

Description

It is the intention of this paper to compare a number of critical heat flux (CHF) correlations for their ability to predict CHF at conditions of low flow and/or low pressure, such as may be predicted in certain fault conditions, e.g. steamline break. To this end, 36 data points from tests at such conditions on a standard Westinghouse 17 x 17 PWR fuel geometry have been analysed. In addition, since these data contain no guide thimble tubes, 25 data points from geometries pertaining to other fuel manufacturers have been analysed. It is found that the UK WSC-2 correlation performs well at such conditions and should be considered if the need for an accurate correlation exists, particularly at conditions of high quality

Additional details

Publishing Information

Publisher
American Nuclear Society.
Imprint Place
La Grange Park, IL (USA)
ISBN
0-89448-122-3
Imprint Title
Proceedings of third international topical meeting on reactor thermal hydraulics
Journal Page Range
p. 18B.1-18B.8.

Conference

Title
3. international meeting on reactor thermal hydraulics.
Dates
15-18 Oct 1985.
Place
Newport, RI (USA).