Preliminary Assessment of PWR Steam Generator Modelling in RELAP5/MOD3 (NUREG/IA-0113)
On this page:
Download complete document
This page includes links to files in non-HTML format. See Plugins, Viewers, and Other Tools for more information.
Publication Information
Date Published: July 1993
Prepared by:
R. J. Preece, J. M. Putney
National Power
Technology and Environmental Centre
Kelvin Avenue
Leatherhead, Surrey
KT22 7SE, United Kingdom
Prepared as part of:
The Agreement on Research Participation and Technical Exchange
under the International Thermal-Hydraulic Code Assessment
and Application Program (ICAP)
Office of Nuclear Regulatory Research
U.S. Nuclear Regulatory Commission
Washington, DC 20555-0001
Summary
A preliminary assessment of Steam Generator (SG) modelling in the PWR
thermal-hydraulic code RELAP5/MOD3 is presented. The study is based on
calculations against a series of steady-state commissioning tests carried out on the
Wolf Creek PWR over a range of load conditions. Data from the tests are used to
assess the modelling of primary to secondary side heat transfer and, in particular, to
examine the effect of reverting to the standard form of the Chen heat transfer
correlation in place of the modified form applied in RELAP5/MOD2. Comparisons
between the two versions of the code are also used to show how the new interphase
drag model in RELAP5/MOD3 affects the calculation of SG liquid inventory and the
void fraction profile in the riser.
