Published 1991 | Version v1
Report Restricted

An approach for assessing ALWR passive safety system reliability

Description

Many advanced light water reactor designs incorporate passive rather than active safety features for front-line accident response. A method for evaluating the reliability of these passive systems in the context of probabilistic risk assessment has been developed at Sandia National Laboratories. This method addresses both the component (e.g. valve) failure aspect of passive system failure, and uncertainties in system success criteria arising from uncertainties in the system's underlying physical processes. These processes provide the system's driving force; examples are natural circulation and gravity-induced injection. This paper describes the method, and provides some preliminary results of application of the approach to the Westinghouse AP600 design

Availability note (English)

MF available from INIS under the Report Number; OSTI as DE92004013; NTIS; INIS; US Govt. Printing Office Dep.

Files

Restricted

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

Additional details

Publishing Information

Imprint Pagination
17 p.
Report number
SAND--91-1459C

Conference

Title
19. Nuclear Regulatory Commission (NRC) water reactor safety information meeting.
Dates
28-30 Oct 1991.
Place
Bethesda, MD (United States).

Optional Information

Contract/Grant/Project number
Contract AC04-76DP00789
Funding organization
Nuclear Regulatory Commission, Washington, DC (United States).
Secondary number(s)
CONF-911079--15.