Published February 1983 | Version v1
Report

Compare containment subcompartment analysis code evaluation

  • 1. Los Alamos National Lab., NM

Description

Nuclear power plant subcompartment analyses are required to determine the containment pressure distribution that might result from a loss-of-coolant accident. The pressure distribution is used to calculate structural and mechanical design loads. The COMPARE code is used widely to perform subcompartment analysis. However, several simplifying assumptions are utilized to facilitate solution of the complex transient, two-phase, multidimensional flow problem. In particular, it is assumed that the flow is homogeneous, in thermodynamic equilibrium, and one-dimensional. In this study, these assumptions are evaluated by performing simplified transport and relaxation analyses. This results in definition of (a) geometric features and early-time periods that produce significant deviations from reality and (b) specific areas that require further study

Additional details

Additional titles

Augmented title (English)
PWR; BWR

Publishing Information

Imprint Title
Proceedings of the international meeting on thermal nuclear reactor safety. Vol. 3
Journal Page Range
p. 1583-1596.
Report number
NUREG/CP--0027-Vol.3

Conference

Title
International meeting on thermal nuclear reactor safety (ANS topical meeting).
Dates
29 Aug - 2 Sep 1982.
Place
Chicago, IL (USA).