Kuosheng BWR/6 instability analysis with RETRANO2/MOD3
Conference
·
· Transactions of the American Nuclear Society; (United States)
OSTI ID:5854557
- National Tsing Hua Univ., Hsinchu (Taiwan)
The objective of this study is to investigate the stability characteristics for Kuosheng nuclear power plant (KNPP), which has two units of General Electric Company-designed boiling water reactor/6 with a rated core thermal power of 2,894 MW and a rated core flow of 3,832 {times} 10{sup 4} t/h. The approach to investigating the instability of KNPP has two steps. The first step includes three types of stability analysis: total plant stability, core reactivity stability, and channel hydrodynamic stability. The Electric Power Research Institute's methodology is adopted in this step. The second step is to establish the instability map under natural circulation conditions. This methodology is quite useful in identifying the stability safety margin and the setup of stability criteria during a nuclear reactor transient. In this study, the recirculation pump trip (RPT) transients with isolated feedwater heater were investigated and plotted on an instability map.
- OSTI ID:
- 5854557
- Report Number(s):
- CONF-910603--
- Conference Information:
- Journal Name: Transactions of the American Nuclear Society; (United States) Journal Volume: 63
- Country of Publication:
- United States
- Language:
- English
Similar Records
Kuosheng BWR/6 recirculation pump trip transient analysis with the RETRAN02/MOD5 code
RETRAN02/MOD3 modeling of the Kuosheng Unit 1 MSIV full isolation startup test
The dynamics of a turbine-driven reactor feedwater pump and identification of related parameters in the Kuosheng power station
Conference
·
Tue Dec 31 23:00:00 EST 1991
· Transactions of the American Nuclear Society; (United States)
·
OSTI ID:6983593
RETRAN02/MOD3 modeling of the Kuosheng Unit 1 MSIV full isolation startup test
Conference
·
Thu Dec 31 23:00:00 EST 1987
· Trans. Am. Nucl. Soc.; (United States)
·
OSTI ID:5782914
The dynamics of a turbine-driven reactor feedwater pump and identification of related parameters in the Kuosheng power station
Journal Article
·
Wed Sep 01 00:00:00 EDT 1993
· Nuclear Technology; (United States)
·
OSTI ID:6169443
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
BWR TYPE REACTORS
CALIBRATION
COMPUTER CODES
COMPUTERIZED SIMULATION
COOLING SYSTEMS
ENERGY TRANSFER
ENRICHED URANIUM REACTORS
FLOW RATE
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
KINETICS
KUOSHENG-1 REACTOR
KUOSHENG-2 REACTOR
MECHANICS
OPERATION
POWER REACTORS
PRIMARY COOLANT CIRCUITS
R CODES
REACTIVITY
REACTOR CHANNELS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR CORES
REACTOR KINETICS
REACTOR OPERATION
REACTOR SAFETY
REACTOR STABILITY
REACTORS
SAFETY
SIMULATION
STABILITY
THERMAL REACTORS
TIME DEPENDENCE
TRANSIENTS
VOID FRACTION
WATER COOLED REACTORS
WATER MODERATED REACTORS
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
BWR TYPE REACTORS
CALIBRATION
COMPUTER CODES
COMPUTERIZED SIMULATION
COOLING SYSTEMS
ENERGY TRANSFER
ENRICHED URANIUM REACTORS
FLOW RATE
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
KINETICS
KUOSHENG-1 REACTOR
KUOSHENG-2 REACTOR
MECHANICS
OPERATION
POWER REACTORS
PRIMARY COOLANT CIRCUITS
R CODES
REACTIVITY
REACTOR CHANNELS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR CORES
REACTOR KINETICS
REACTOR OPERATION
REACTOR SAFETY
REACTOR STABILITY
REACTORS
SAFETY
SIMULATION
STABILITY
THERMAL REACTORS
TIME DEPENDENCE
TRANSIENTS
VOID FRACTION
WATER COOLED REACTORS
WATER MODERATED REACTORS