Analysis of a turbine trip test with a plant analyzer
Conference
·
· Transactions of the American Nuclear Society; (USA)
OSTI ID:5702399
To improve nuclear power plant safety, the Taiwan Power Company is using a plant analyzer developed by Brookhaven National Laboratory (BNL). The BNL boiling water reactor (BWR) plant analyzer program was converted and modified for the Chinshan power station using the ADSIM simulation language. The plant analyzer uses a special-purpose peripheral processor, the AD-100 from the 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 plant transients. To qualify this program, simulation results were benchmarked against power test data. During a power test a Chinshan unit 1, a 1175-MW(thermal) boiling water reactor (BWR), a turbine trip test was performed from a steady-state condition of 83% of rated core power and 80% of rated core flow. It was initiated by a manual trip of the turbine. The purpose of this work is to simulate the turbine trip transient with the plant analyzer and compare the results with plant test data.
- OSTI ID:
- 5702399
- Report Number(s):
- CONF-901101--
- Conference Information:
- Journal Name: Transactions of the American Nuclear Society; (USA) Journal Volume: 62
- Country of Publication:
- United States
- Language:
- English
Similar Records
Analysis of the turbine trip test performed at the Chin-Shan Power Station Unit 1 with plant analyzer
Analysis of a turbine trip transient with the Chinshan plant analyzer
Development of the Chinshan plant analyzer and its assessment with plant data
Conference
·
Sun Dec 31 23:00:00 EST 1989
· Transactions of the American Nuclear Society; (United States)
·
OSTI ID:6808008
Analysis of a turbine trip transient with the Chinshan plant analyzer
Journal Article
·
Thu Jul 01 00:00:00 EDT 1993
· Nuclear Technology; (United States)
·
OSTI ID:7369014
Development of the Chinshan plant analyzer and its assessment with plant data
Journal Article
·
Tue Jun 01 00:00:00 EDT 1993
· Nuclear Technology; (United States)
·
OSTI ID:6442223
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