RETRAN simulation of Oyster Creek MSIV closure and bypass valve tests
Description
A series of benchmarks against start-up tests have been performed on the Oyster Creek boiling water reactor unit 2 RETRAN model in support of developing an in-house reload capability. The liquid and the pressure regulator models have been benchmarked against level and pressure setpoint changes, where small setpoint perturbations were made at rated power. The purpose of the present benchmark is to check the liquid level behavior during a severe level drop as during void collapse following a scram and to size the bypass valves by benchmarking the valves' contraction coefficient. The main steam isolation valves (MSIVs) closure start-up test was chosen for the former, while the bypass valve test was chosen for the latter. The two benchmarks complete the qualification of the upper downcomer liquid level for small and large level changes and the pressure regulator system for the Oyster Creek RETRAN model
Additional details
Publishing Information
- Journal Title
- Trans. Am. Nucl. Soc.
- Journal Volume
- 54
- Series
- Trans. Am. Nucl. Soc.
- Journal Page Range
- 322-324
- ISSN
- 0003-018X
- CODEN
- TANSA
Conference
- Title
- Annual meeting of the American Nuclear Society.
- Dates
- 7-11 Jun 1987.
- Place
- Dallas, TX (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 19046136
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BENCHMARKS; COMPUTERIZED SIMULATION; FORKED RIVER-1 REACTOR; LEVEL INDICATORS; PRESSURE MEASUREMENT; R CODES; REACTOR COOLING SYSTEMS; REACTOR START-UP; SCRAM; STEAM; TESTING; VALVES
- Descriptors DEC
- COMPUTER CODES; CONTROL EQUIPMENT; COOLING SYSTEMS; ENRICHED URANIUM REACTORS; EQUIPMENT; FLOW REGULATORS; MEASURING INSTRUMENTS; POWER REACTORS; PWR TYPE REACTORS; REACTOR COMPONENTS; REACTOR SHUTDOWN; REACTORS; SHUTDOWN; SIMULATION; START-UP; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-870601--.