Published April 1988
| Version v1
Report
RETRAN analysis of Safety Relief Valve setpoint - drift and tolerance evaluation for BWRs
Description
This study presents implications and guidelines for safety evaluations of Safety Relief Valve setpoint drift in a GE BWR/4 design reactor. The problem was investigated using the RETRAN02MOD003 code. The analysis demonstrated that margin to the safety limit pressure is maintained even for the extreme case of one SRV out-of-service with the remaining actuating at 5% above setpoint pressure
Additional details
Publishing Information
- Imprint Title
- Proceedings: Fifth International RETRAN conference
- Journal Page Range
- p. 19.1-19.16.
- Report number
- EPRI-NP--5781-SR
Conference
- Title
- 5. international RETRAN meeting.
- Dates
- 9-11 Nov 1987.
- Place
- Boston, MA (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 20030201
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- BWR TYPE REACTORS; COMPUTERIZED SIMULATION; HEAT TRANSFER; HYDRAULICS; LOSS OF COOLANT; R CODES; REACTOR SAFETY; RELIEF VALVES; SYSTEMS ANALYSIS; TEMPERATURE GRADIENTS; THERMODYNAMICS; TRANSIENTS
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; CONTROL EQUIPMENT; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; EQUIPMENT; FLOW REGULATORS; POWER REACTORS; REACTOR ACCIDENTS; REACTORS; SAFETY; SIMULATION; THERMAL REACTORS; VALVES; WATER COOLED REACTORS; WATER MODERATED REACTORS