Analysis of the MSIV closure ATWS in a BWR/6
Conference
·
· Trans. Am. Nucl. Soc.; (United States)
OSTI ID:5781122
Anticipated transient without scram (ATWS) has received much attention since the beginning of the last decade. It has been recognized as a dominant accident sequence for possible core melt and containment damage in a boiling water reactor (BWR) power plant. In the literature, a great deal of study has been reported on the investigation of BWR behavior during an ATWS, especially for BWR/2 and BWR/4. The objective of this study is to assess reactor behavior during a main steam isolation valve (MSIV) closure ATWS for the Kuosheng nuclear power plant of Taiwan Power Company, which has two units of BWR/6 with Mark-III containment. The analyses were performed using RETRAN-02/MOD3, which solves a one-dimensional homogeneous equilibrium model of two-phase mixture. The relative motion between two phases is treated by the dynamic slip model. Due to the unavailability of appropriate three-dimensional neutronic codes, such as SIMULATE-E, in this country, the option of point kinetics has been adopted for calculations. This approach is not expected to give the exact power shape variation during the transient, but is believed to be appropriate for providing the accurate overall power level, which is the major concern for core and containment integrity.
- OSTI ID:
- 5781122
- 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
Similar Records
A long-term MAAP 3. 0B analysis of a severe anticipated transient without scram accident in a boiling water reactor
Analysis of high-pressure boiloff situation during an MSIV closure ATWS in a typical BWR/4
RETRAN02/MOD3 modeling of the Kuosheng Unit 1 MSIV full isolation startup test
Journal Article
·
Thu Oct 01 00:00:00 EDT 1992
· Nuclear Technology; (United States)
·
OSTI ID:6933322
Analysis of high-pressure boiloff situation during an MSIV closure ATWS in a typical BWR/4
Conference
·
Tue Dec 31 23:00:00 EST 1985
· Trans. Am. Nucl. Soc.; (United States)
·
OSTI ID:6623650
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
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
ACCIDENTS
ACCURACY
ATWS
BORON
BWR TYPE REACTORS
BYPASSES
COMPUTER CODES
COMPUTERIZED SIMULATION
CONTAINERS
CONTAINMENT
CONTAINMENT SYSTEMS
CONTROL EQUIPMENT
CONVECTION
COOLING SYSTEMS
CORE SPRAY SYSTEMS
ECCS
ELEMENTS
ENERGY SYSTEMS
ENERGY TRANSFER
ENGINEERED SAFETY SYSTEMS
ENRICHED URANIUM REACTORS
EQUIPMENT
FEEDWATER
FLOW RATE
FLOW REGULATORS
FLUID FLOW
FLUID MECHANICS
HEAT TRANSFER
HIGH PRESSURE COOLANT INJECTION
HYDRAULICS
HYDROGEN COMPOUNDS
KINETICS
KUOSHENG-1 REACTOR
MASS TRANSFER
MECHANICS
MELTDOWN
NATURAL CONVECTION
ONE-DIMENSIONAL CALCULATIONS
OXYGEN COMPOUNDS
POWER REACTORS
PRESSURE VESSELS
PRIMARY COOLANT CIRCUITS
PUMPS
R CODES
RCIC SYSTEMS
REACTIVITY
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR CORE DISRUPTION
REACTOR KINETICS
REACTOR PROTECTION SYSTEMS
REACTOR SAFETY
REACTORS
RELIEF VALVES
SAFETY
SAFETY INJECTION
SEMIMETALS
SIMULATION
STEAM SYSTEMS
THERMAL REACTORS
TWO-PHASE FLOW
VALVES
WATER
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
ACCIDENTS
ACCURACY
ATWS
BORON
BWR TYPE REACTORS
BYPASSES
COMPUTER CODES
COMPUTERIZED SIMULATION
CONTAINERS
CONTAINMENT
CONTAINMENT SYSTEMS
CONTROL EQUIPMENT
CONVECTION
COOLING SYSTEMS
CORE SPRAY SYSTEMS
ECCS
ELEMENTS
ENERGY SYSTEMS
ENERGY TRANSFER
ENGINEERED SAFETY SYSTEMS
ENRICHED URANIUM REACTORS
EQUIPMENT
FEEDWATER
FLOW RATE
FLOW REGULATORS
FLUID FLOW
FLUID MECHANICS
HEAT TRANSFER
HIGH PRESSURE COOLANT INJECTION
HYDRAULICS
HYDROGEN COMPOUNDS
KINETICS
KUOSHENG-1 REACTOR
MASS TRANSFER
MECHANICS
MELTDOWN
NATURAL CONVECTION
ONE-DIMENSIONAL CALCULATIONS
OXYGEN COMPOUNDS
POWER REACTORS
PRESSURE VESSELS
PRIMARY COOLANT CIRCUITS
PUMPS
R CODES
RCIC SYSTEMS
REACTIVITY
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR CORE DISRUPTION
REACTOR KINETICS
REACTOR PROTECTION SYSTEMS
REACTOR SAFETY
REACTORS
RELIEF VALVES
SAFETY
SAFETY INJECTION
SEMIMETALS
SIMULATION
STEAM SYSTEMS
THERMAL REACTORS
TWO-PHASE FLOW
VALVES
WATER
WATER COOLED REACTORS
WATER MODERATED REACTORS