Verification of feedwater system models of the Kuosheng plant analyzer

Journal Article · Wed Jun 01 04:00:00 EDT 1994 · Nuclear Technology; (United States)

OSTI ID:7202263

Wang, S J; Chien, C S; Chang, S H ^[1]; Jeng, S C ^[2]

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1. Institute of Nuclear Energy Research, Taoyuan (Taiwan, Province of China)
2. Taiwan Power Co., Taipei (Taiwan, Province of China)

Based on the boiling water reactor plant analyzer of Brookhaven National Laboratory and the Chinshan plant analyzer of Taiwan Power Company, the Kuosheng plant analyzer was developed for the Kuosheng nuclear power station. This work verifies the feedwater system models with a downcomer level setpoint change transient. A transient induced by a step change in the downcomer level setpoint is simulated with the Kuosheng plant analyzer and is compared with test data. Discrepancies are found in the response of the feedwater system. Mathematical models of the feedwater system. Mathematical models of the feedwater system are revised, and the associated key parameters are identified from plant data with the simplex search method. After revision, the predicted results show good agreement with the test data.

• OSTI ID: 7202263
• Journal Information: Nuclear Technology; (United States), Journal Name: Nuclear Technology; (United States) Vol. 106:3; ISSN 0029-5450; ISSN NUTYBB
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100* -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
BWR TYPE REACTORS
CONTROL SYSTEMS
COOLING SYSTEMS
DATA
ENERGY SYSTEMS
ENRICHED URANIUM REACTORS
FEEDWATER
FLOW RATE
HYDROGEN COMPOUNDS
INFORMATION
KUOSHENG-1 REACTOR
KUOSHENG-2 REACTOR
MATHEMATICAL MODELS
NUMERICAL DATA
OXYGEN COMPOUNDS
POWER REACTORS
REACTOR COMPONENTS
REACTOR CONTROL SYSTEMS
REACTOR COOLING SYSTEMS
REACTORS
THEORETICAL DATA
THERMAL REACTORS
TRANSIENTS
WATER
WATER COOLED REACTORS
WATER MODERATED REACTORS