Results of the Level 1 probabilistic risk assessment (PRA) of internal events for heavy water production reactors
A full-scope probabilistic risk assessment (PRA) is being performed for the Savannah River site (SRS) production reactors. The Level 1 PRA for the K Reactor has been completed and includes the assessment of reactor systems response to accidents and estimates of the severe core melt frequency (SCMF). The internal events spectrum includes those events related directly to plant systems and safety functions for which transients or failures may initiate an accident. The SRS PRA has three principal objectives: improved understanding of SRS reactor safety issues through discovery and understanding of the mechanisms involved. Improved risk management capability through tools for assessing the safety impact of both current standard operations and proposed revisions. A quantitative measure of the risks posed by SRS reactor operation to employees and the general public, to allow comparison with declared goals and other societal risks.
- Research Organization:
- Westinghouse Savannah River Co., Aiken, SC (USA)
- Sponsoring Organization:
- DOE/DP
- DOE Contract Number:
- AC09-89SR18035
- OSTI ID:
- 6396692
- Report Number(s):
- WSRC-RP-89-1405; CONF-900917-28; ON: DE91004257; TRN: 90-037674
- Resource Relation:
- Conference: American Nuclear Society topical meeting on safety of non-commercial nuclear reactor research and irradiation facilities, Boise, ID (USA), 30 Sep - 3 Oct 1990
- Country of Publication:
- United States
- Language:
- English
Similar Records
Response of structures to energetic events for the Savannah River Site production reactors probabilistic risk assessment
Savannah River Reactor Operation: Indices of risk for emergency planning
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
HEAVY WATER COOLED REACTORS
RISK ASSESSMENT
PRODUCTION REACTORS
SAVANNAH RIVER PLANT
FAILURE MODE ANALYSIS
HEAT TRANSFER
HYDRAULICS
LOSS OF COOLANT
MELTDOWN
REACTOR SAFETY
TRANSIENTS
ACCIDENTS
ENERGY TRANSFER
FLUID MECHANICS
MECHANICS
NATIONAL ORGANIZATIONS
REACTOR ACCIDENTS
REACTORS
SAFETY
SYSTEM FAILURE ANALYSIS
SYSTEMS ANALYSIS
US AEC
US DOE
US ERDA
US ORGANIZATIONS
220900* - Nuclear Reactor Technology- Reactor Safety
220700 - Nuclear Reactor Technology- Plutonium & Isotope Production Reactors