RETRAN02/MOD3 modeling of the Kuosheng Unit 1 MSIV full isolation startup test

Conference · Fri Jan 01 04:00:00 EST 1988 · Trans. Am. Nucl. Soc.; (United States)

OSTI ID:5782914

Wang, Jongrong; Chen, Yisheng; Wang, Songfeng

Kuosheng nuclear power plant, the second nuclear power station of Taiwan Power Company (TPC), has two units of a General Electric Company designed boiling water reactor BWR/6 with a rated core thermal power of 2894 MW and rated core flow of 3.832 x 10/sup 4/ t/h (2.347 x 10/sup 4/ lb/s). The nuclear steam supply system consists of two recirculation loops and four main steam lines. Before the plant went into commercial operation, a series of power tests were conducted at both units to ensure the design adequacy of the system. The main steam isolation valve full isolation (MSIVFI) was one of the tests designed to (a) functionally check the proper operation of the MSIVs at selected power levels, (b) determine reactor transient behavior during and following simultaneous full closure of all MSIVs, and (c) determine the closure time of the MSIVs. The MSIV isolation was initiated by pulling fuses F6A and F6B in the control room panel. Test data were recorded by the plant transient recorder (STARTREC) and were adopted for comparisons. The objective of the present study was to simulate the Kuosheng Unit 1 MSIVFI test using the RETRAN02/MOD3 code as part of the overall qualification efforts of the plant model. In addition to data comparison, parameters sensitive to plant-specific RETRAN model development were also investigated.

• OSTI ID: 5782914
• Report Number(s): CONF-881011-
• Conference Information: Journal Name: Trans. Am. Nucl. Soc.; (United States) Journal Volume: 57
• 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
42 ENGINEERING
420400 -- Engineering-- Heat Transfer & Fluid Flow
99 GENERAL AND MISCELLANEOUS
990220 -- Computers
Computerized Models
& Computer Programs-- (1987-1989)
BUBBLES
BWR TYPE REACTORS
BYPASSES
COMPUTER CODES
CONTROL EQUIPMENT
CONTROL ROOMS
COOLING SYSTEMS
ENERGY SYSTEMS
ENERGY TRANSFER
ENRICHED URANIUM REACTORS
EQUIPMENT
FEEDWATER
FLOW RATE
FLOW REGULATORS
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
HYDROGEN COMPOUNDS
KINETICS
KUOSHENG-1 REACTOR
MATHEMATICAL MODELS
MECHANICS
MOTORS
OPERATION
OXYGEN COMPOUNDS
PARAMETRIC ANALYSIS
PERFORMANCE TESTING
POWER REACTORS
PRIMARY COOLANT CIRCUITS
R CODES
RCIC SYSTEMS
REACTIVITY
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR CORES
REACTOR KINETICS
REACTOR MONITORING SYSTEMS
REACTOR OPERATION
REACTOR SHUTDOWN
REACTOR START-UP
REACTORS
RELIEF VALVES
SCRAM
SENSITIVITY
SEPARATION EQUIPMENT
SHUTDOWNS
SIMULATION
START-UP
STEAM SEPARATORS
STEAM SYSTEMS
TESTING
THERMAL REACTORS
TRANSIENTS
VALVES
VAPOR SEPARATORS
WATER
WATER COOLED REACTORS
WATER MODERATED REACTORS