Published 1986 | Version v1
Report Restricted

SCDAP/RELAP5 update and applications

Description

The integrated SCDAP/RELAP5 code is being developed by the Office of Nuclear Regulatory Research of the USNRC for the purpose of calculating the core damage and fission product transport within the RCS during LWR severe accidents events. Activities since October 1985 were concentrated in three areas. The first area, code and model development, resulted in the addition of a B4C control rod model and a two-dimensional (axial-radial) heat conduction analysis of fuel and control rods. The second area, developmental assessment, evaluated code models using the results of the OECD LOFT FP-2 test and the PBF and ACRR severe fuel damage tests. The third area, user and NRC technical support, resulted in application of the code to analyses of severe accidents in BWRs and PWRs. 8 refs

Availability note (English)

Available from NTIS, PC A02/MF A01; 1 as DE87012434.

Files

Restricted

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

Additional details

Publishing Information

Imprint Pagination
6 p.
Report number
EGG-M--22186

Conference

Title
14. water reactor safety information meeting.
Dates
27-31 Oct 1986.
Place
Gaithersburg, MD (USA).

Optional Information

Notes
Portions of this document are illegible in microfiche products.
Secondary number(s)
CONF-8610135--65.