RSAS
Creators
- 1. Idaho National Engineering Lab., Idaho Falls, ID (United States)
- 2. Nuclear Regulatory Commission, Washington, DC (United States)
- 3. Maryland Univ., Baltimore, MD (United States)
Description
This paper reports on the Reactor Safety assessment System (RSAS) which is an expert system being developed by the Idaho National Engineering Laboratory (INEL) and the United States Nuclear Regulatory Commission (NRC) for the NRC Operations Center. RSAS is intended to aid the Reactor Safety Team at the Operations Center to monitor and project core status during an emergency at a licensed nuclear power plant. The foundation of the RSAS knowledge base is a Goal Tree-Success Tree (GTST) model. Critical safety functions appear as upper level goals in the GTST model. Success trees represent the functionality of systems and equipment required to achieve the desired goals. A dependency matrix is utilized to account for functional dependencies among various systems and equipment. RSAS objectives are obtained by the monitoring of the critical safety functions, identification of success path status, and timely provision of vital information
Additional details
Additional titles
- Subtitle (English)
- A reactor safety assessment system
Publishing Information
- Publisher
- University of Tennessee at Knoxville.
- Imprint Place
- Knoxville, TN (United States)
- Imprint Title
- Proceedings of the 7th power plant dynamics, control and testing symposium
- Imprint Pagination
- vp.
- Journal Page Range
- p. 69.01-69.12.
Conference
- Title
- 7. power plant dynamics, control and testing symposium.
- Dates
- 15-17 May 1989.
- Place
- Knoxville, TN (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 23059207
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- EMERGENCY PLANS; EQUIPMENT; EXPERT SYSTEMS; FAULT TREE ANALYSIS; IDAHO NATIONAL ENGINEERING LAB; MATRICES; MONITORING; NUCLEAR POWER PLANTS; REACTOR ACCIDENTS; REACTOR CORES; REACTOR SAFETY; RISK ASSESSMENT; US NRC
- Descriptors DEC
- ACCIDENTS; NATIONAL ORGANIZATIONS; NUCLEAR FACILITIES; POWER PLANTS; REACTOR COMPONENTS; SAFETY; SYSTEM FAILURE ANALYSIS; SYSTEMS ANALYSIS; THERMAL POWER PLANTS; US DOE; US ERDA; US ORGANIZATIONS
Optional Information
- Secondary number(s)
- CONF-890555--.