RIO: a program to determine reliability importance and allocate optimal reliability goals
Description
The designer of a nuclear plant must know the plant's associated risk limitations so that he can design the plant accordingly. To design a safety system, he must understand its importance and how it relates to the overall plant risk. The computer program RIO can aid the designer to understand a system's contribution to the plant's overall risk. The methodology developed and presented was sponsored by the Nuclear Research Applications Division of the Department of Energy for use in the Gas Cooled Fast Breeder Reactor (GCFR) Program. The principal motivation behind its development was the need to translate nuclear plants safety goals into reliability goals for systems which make up that plant. The method described herein will make use of the GCFR Accident Initiation and Progression Analyses (AIPA) event trees and other models in order to determine these reliability goals
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS., MF A01.
Files
Additional details
Additional titles
- Augmented title (English)
- In FORTRAN IV for CDC 7600
Publishing Information
- Imprint Pagination
- 87 p.
- Report number
- TREE--1287
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 10445270
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY;
- Descriptors DEI
- CDC COMPUTERS; FAULT TREE ANALYSIS; FORTRAN; NUCLEAR POWER PLANTS; R CODES; REACTOR SAFETY; RELIABILITY
- Descriptors DEC
- COMPUTER CODES; COMPUTERS; NUCLEAR FACILITIES; POWER PLANTS; PROGRAMMING LANGUAGES; SAFETY; SYSTEM FAILURE ANALYSIS; SYSTEMS ANALYSIS; THERMAL POWER PLANTS