Reactivity transients during a blowdown in a MSIV closure ATWS
Conference
·
· Transactions of the American Nuclear Society; (USA)
OSTI ID:5655347
- Brookhaven National Lab., Upton, NY (USA)
Anticipated transients without scram (ATWS) events have received considerable attention in the past and are still a subject of great interest in severe-accident analysis. Of special interest is the effect of the low-pressure emergency core cooling system (ECCS) on the plant response following a blowdown by the automatic depressurization system (ADS). There is a potential for positive reactivity insertion due to the cold water injection of the low-pressure coolant injection (LPCI) system and the low-pressure core spray system in a boiling water reactor (BWR)/4. The main concern is whether a power excursion and pressure oscillation can occur in such an event. Furthermore, since thermal-hydraulic feedback plays an important role in these accidents, the uncertainty of the reactivity feedback coefficients used can impact the outcome of the analysis for such a power excursion. The objectives of the work reported in this paper are to study the consequences of the reactivity transients during a blowdown in an ATWS event with closure of the main steam isolation valves (MSIVs) and to evaluate the effect of the LPCI system and the sensitivity of plant response to the feedback coefficients. This work was performed with the Brookhaven National Laboratory plant analyzer.
- OSTI ID:
- 5655347
- Report Number(s):
- CONF-881011--
- Conference Information:
- Journal Name: Transactions of the American Nuclear Society; (USA) Journal Volume: 57
- Country of Publication:
- United States
- Language:
- English
Similar Records
Reactivity transients during a blowdown in a MSIV (Main Steam Isolation Valves) closure ATWS (Anticipated Transients Without Scram)
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Thu Dec 31 23:00:00 EST 1987
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· Trans. Am. Nucl. Soc.; (United States)
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Sat Nov 09 23:00:00 EST 2013
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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
ATWS
BLOWDOWN
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BWR TYPE REACTORS
CONTROL SYSTEMS
CORE SPRAY SYSTEMS
ECCS
ENERGY TRANSFER
ENGINEERED SAFETY SYSTEMS
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HEAT TRANSFER
HYDRAULICS
KINETICS
LOSS OF COOLANT
LOW PRESSURE COOLANT INJECTION
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NATIONAL ORGANIZATIONS
PRESSURE SUPPRESSION
REACTIVITY
REACTIVITY INSERTIONS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR CONTROL SYSTEMS
REACTOR CORES
REACTOR KINETICS
REACTOR PROTECTION SYSTEMS
REACTOR SAFETY
REACTORS
SAFETY
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TWO-PHASE FLOW
US AEC
US DOE
US ERDA
US ORGANIZATIONS
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
ATWS
BLOWDOWN
BNL
BWR TYPE REACTORS
CONTROL SYSTEMS
CORE SPRAY SYSTEMS
ECCS
ENERGY TRANSFER
ENGINEERED SAFETY SYSTEMS
FLUID FLOW
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
KINETICS
LOSS OF COOLANT
LOW PRESSURE COOLANT INJECTION
MECHANICS
NATIONAL ORGANIZATIONS
PRESSURE SUPPRESSION
REACTIVITY
REACTIVITY INSERTIONS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR CONTROL SYSTEMS
REACTOR CORES
REACTOR KINETICS
REACTOR PROTECTION SYSTEMS
REACTOR SAFETY
REACTORS
SAFETY
SENSITIVITY
TWO-PHASE FLOW
US AEC
US DOE
US ERDA
US ORGANIZATIONS
WATER COOLED REACTORS
WATER MODERATED REACTORS