Published 1982 | Version v1
Report Restricted

Compare containment subcompartment analysis code evaluation

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

Availability note (English)

MF available from INIS under the Report Number; Available from NTIS., PC A02/MF A01 as DE82020828.

Files

Restricted

The record is publicly accessible, but files are restricted to users with access.

Additional details

Additional titles

Augmented title (English)
PWR; BWR

Publishing Information

Imprint Pagination
14 p.
Report number
LA-UR--82-2522

Conference

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

Optional Information

Secondary number(s)
CONF-820802--8.