Methodology for evaluation of insulation-debris effects. Containment emergency sump performance-unresolved safety issue A-43
The postulated failure of high energy piping within a light water reactor containment has raised safety questions related to the generation of insulation debris, the migration of such debris to the containment emergency sump screens and the potential for severe screen blockages. High, or total, screen blockages could result in impairment of the long term RHR recirculation systems. Debris considerations are an integral part of the unresolved Safety Issue A-43, Containment Emergency Sump Performance. This report develops calculational methods and debris transport models which can be used for estimating the quantities of debris that might be generated by a LOCA, the transport of such debris, methods for estimating screen blockages and attendant pressure losses. Five operating plants were analyzed using this debris evaluation methodology. These calculations show the dependency on plant containment layout, sump location and design, and types and quantities of insulation employed. 9 figures, 6 tables.
- Research Organization:
- Burns and Roe, Inc., Woodbury, NY (USA)
- DOE Contract Number:
- AC04-76DP00789
- OSTI ID:
- 6733320
- Report Number(s):
- NUREG/CR-2791; SAND-82-7067; ON: DE83001108
- Country of Publication:
- United States
- Language:
- English
Similar Records
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
ARKANSAS-1 REACTOR
CONTAINMENT
COOLING SYSTEMS
ENERGY SYSTEMS
ENRICHED URANIUM REACTORS
FLOW BLOCKAGE
LOSS OF COOLANT
MAINE YANKEE REACTOR
MASS TRANSFER
PIPES
POWER REACTORS
PRAIRIE ISLAND-1 REACTOR
PRESSURE DROP
PUMPS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTORS
RHR SYSTEMS
SALEM-1 REACTOR
SEQUOYAH-2 REACTOR
THERMAL INSULATION
THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
ARKANSAS-1 REACTOR
CONTAINMENT
COOLING SYSTEMS
ENERGY SYSTEMS
ENRICHED URANIUM REACTORS
FLOW BLOCKAGE
LOSS OF COOLANT
MAINE YANKEE REACTOR
MASS TRANSFER
PIPES
POWER REACTORS
PRAIRIE ISLAND-1 REACTOR
PRESSURE DROP
PUMPS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTORS
RHR SYSTEMS
SALEM-1 REACTOR
SEQUOYAH-2 REACTOR
THERMAL INSULATION
THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS