Overpressurization transient in a BWR [boiling water reactor] with multiple failures in safety systems
Creators
Description
After the accident at Chernobyl, the Finnish Centre for Radiation and Nuclear Safety, which is the Finnish Nuclear Energy Authority, enlarged the scope of reactivity-initiated accident analysis beyond that for design bases accidents to determine the real safety margins of nuclear power plants. In this connection, boiling water reactor (BWR) overpressurization events with multiple failures in safety systems have also been studied. Analyses have been performed at TVO 1 nuclear power plant, which is a 2,160-MW(thermal) BWR in Finland. The most probable overpressurization incident, pressure controller failure, was chosen for analysis. In this event, all turbine control valves close simultaneously, initiating an overpressurization transient in the pressure vessel. The objective of these overpressurization analyses was to find out how much reactivity it is possible to inject during an overpressurization transient with multiple failures in the safety systems
Additional details
Publishing Information
- Journal Title
- Transactions of the American Nuclear Society
- Journal Volume
- 61
- Series
- Trans. Am. Nucl. Soc.
- Journal Page Range
- 221-222
- ISSN
- 0003-018X
- CODEN
- TANSA
Conference
- Title
- American Nuclear Society annual meeting.
- Dates
- 10-14 Jun 1990.
- Place
- Nashville, TN (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 22034800
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CHERNOBYLSK-4 REACTOR; COMPUTERIZED SIMULATION; FAILURES; FINNISH ORGANIZATIONS; HEAT TRANSFER; HYDRAULICS; PRESSURIZATION; PRIMARY COOLANT CIRCUITS; REACTOR ACCIDENTS; REACTOR CONTROL SYSTEMS; REACTOR KINETICS; REACTOR PROTECTION SYSTEMS; REACTOR SAFETY; RELIEF VALVES; SAFETY ENGINEERING; SCRAM; TRANSIENTS; TVO-1 REACTOR
- Descriptors DEC
- ACCIDENTS; BWR TYPE REACTORS; CONTROL EQUIPMENT; CONTROL SYSTEMS; COOLING SYSTEMS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; EQUIPMENT; FLOW REGULATORS; GRAPHITE MODERATED REACTORS; KINETICS; LWGR TYPE REACTORS; NATIONAL ORGANIZATIONS; POWER REACTORS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTOR SHUTDOWN; REACTORS; SAFETY; SHUTDOWN; SIMULATION; THERMAL REACTORS; VALVES; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-900608--.