Analysis of the turbine trip test performed at the Chin-Shan Power Station Unit 1 with plant analyzer
Creators
Description
In order to improve nuclear power plant safety, plant analyzer technology has been transferred to Taiwan Power Company (TPC) from Brookhaven National Laboratory (BNL). The BNL boiling water reactor (BWR) plant analyzer program was converted and modified for CHIN-SHAN power station with ADSIM simulation language. The plant analyzer incorporates the special purpose peripheral processor AD-100 of Applied Dynamic International Company and detailed mathematical models. With the fast computing features of the AD-100, the plant analyzer can carry out accurate and fast simulations of nuclear power pant transients. In order to qualify this program, simulation results are benchmarked against power test data. During a power test of CHIN-SHAN power station unit 1 of TPC, a 1,775-MW(thermal) BWR/4, a turbine trip test was performed. This test was performed from a steady-state condition of 83% rated core power and 80% rated core flow. It was initiated by manual trip of the turbine. This turbine trip transient is simulated with the plant analyzer and compared with plant test data. The simulation results show that the plant analyzer catches the trends of this transient very well
Additional details
Publishing Information
- Journal Title
- Transactions of the American Nuclear Society
- Journal Volume
- 62
- Journal Page Range
- p. 349.
- ISSN
- 0003-018X
- CODEN
- TANSAO
Conference
- Title
- American Nuclear Society (ANS) winter meeting.
- Dates
- 11-16 Nov 1990.
- Place
- Washington, DC (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 24038813
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ACCURACY; BNL; BYPASSES; CHINSHAN-1 REACTOR; COMPUTER CODES; COMPUTERIZED SIMULATION; EFFICIENCY; ELECTRIC UTILITIES; FILM BOILING; HEAT TRANSFER; HYDRAULICS; POWER DENSITY; PRESSURE VESSELS; PRIMARY COOLANT CIRCUITS; REACTIVITY; REACTOR KINETICS; REACTOR MONITORING SYSTEMS; REACTOR PROTECTION SYSTEMS; REACTOR SAFETY; SCRAM; THERMAL CONDUCTIVITY; TIME DEPENDENCE; TRANSIENTS; TWO-PHASE FLOW
- Descriptors DEC
- BOILING; BWR TYPE REACTORS; CONTAINERS; COOLING SYSTEMS; ELECTRIC POWER INDUSTRY; ENERGY TRANSFER; ENGINEERED SAFETY SYSTEMS; ENRICHED URANIUM REACTORS; FLUID FLOW; INDUSTRY; KINETICS; NATIONAL ORGANIZATIONS; PHASE TRANSFORMATIONS; PHYSICAL PROPERTIES; POWER REACTORS; PUBLIC UTILITIES; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTOR SHUTDOWN; REACTORS; SAFETY; SHUTDOWN; SIMULATION; THERMAL REACTORS; THERMODYNAMIC PROPERTIES; US AEC; US DOE; US ERDA; US ORGANIZATIONS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-901101--.