Thermal-hydraulic oscillations at LaSalle
Creators
- 1. Nuclear Regulatory Commission, Washington, DC (USA). Office of Nuclear Reactor Regulation
Description
This paper describes how, on March 9, 1988, LaSalle Unit 2 underwent a dual recirculation pump trip event. Trip of the recirculation pumps resulted in a flow decrease to natural circulation flow. As a consequence of the rapid power decrease which accompanied the flow decrease, the feedwater heater level control system began isolating extraction steam from the heaters. The cooler feedwater led to an increase in power and transition into a region of thermal-hydraulic instability. Approximately five minutes after the recirculation pump trip, large (25 percent peak-to-peak) neutron flux oscillations were observed. The oscillations increased in magnitude until a reactor trip occurred on high average power range neutron flux at 118 percent of full power. Although no fuel thermal or mechanical limits were exceeded during the event, the event caused concern relative to the adequacy of licensing analyses and potential violation of safety limits
Additional details
Publishing Information
- Publisher
- Society for Computer Simulation.
- Imprint Place
- San Diego, CA (USA)
- ISBN
- 0-911801-51-0
- Imprint Title
- Simulators 6
- Imprint Pagination
- 264 p.
- Journal Page Range
- p. 83-85.
Conference
- Title
- 22. annual simulation symposium.
- Dates
- 28-31 Mar 1989.
- Place
- Tampa, FL (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 22023334
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CLOSED-CYCLE SYSTEMS; FLOW MODELS; HYDRAULICS; LA SALLE COUNTY-2 REACTOR; PUMPS; REACTOR ACCIDENTS; REACTOR CONTROL SYSTEMS; REACTOR SAFETY; THERMODYNAMICS
- Descriptors DEC
- ACCIDENTS; BWR TYPE REACTORS; CONTROL SYSTEMS; ENRICHED URANIUM REACTORS; EQUIPMENT; MATHEMATICAL MODELS; POWER REACTORS; REACTORS; SAFETY; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-890360--.