Application of Probabilistic Risk Assessment Techniques During Design Phase for Dry Storage Casks
Conference
·
OSTI ID:6535693
- Idaho National Engineering Laboratory (INEL), Idaho Falls, ID (United States). EG&G Idaho, Inc.
Canisters containing the Three Mile Island (TMI) spent fuel and debris are being stored in a storage pool at the Idaho National Engineering Laboratory (INEL). In order to store these canisters in dry storage casks, a system is being designed to remove entrained water from the canisters. The conceptual design for this drying process was evaluated in respect to the occurrence of a nuclear criticality. The system design was evaluated to address the mechanical failure of the components. Also, human interfaces with the equipment were assessed. The integration of these two facets resulted in a model that was quantified to calculate the occurrence frequency of a nuclear criticality. Changes to design, administrative guidelines, and procedures were recommended so that an acceptable level of risk based on nuclear criticality occurrence frequency could be achieved.
- Research Organization:
- Idaho National Engineering Laboratory (INEL), Idaho Falls, ID (United States). EG&G Idaho, Inc.
- Sponsoring Organization:
- USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
- DOE Contract Number:
- AC07-76ID01570
- OSTI ID:
- 6535693
- Report Number(s):
- EGG-M-90142; CONF-9002139--2; ON: DE91001821
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
050900* -- Nuclear Fuels-- Transport
Handling
& Storage
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
96 KNOWLEDGE MANAGEMENT AND PRESERVATION
CASKS
CONTAINERS
CRITICALITY
DRYING
Drying Process
ENRICHED URANIUM REACTORS
FUEL POOLS
Fault Tree Analysis (FTA)
Integrated Risk Assessment Approach
Long-Term Storage
MANAGEMENT
Nuclear Criticality Safety Program (NCSP)
Operational safety Requirements (OSRs)
POWER REACTORS
PWR TYPE REACTORS
RADIOACTIVE WASTE STORAGE
REACTORS
REMOVAL
RISK ASSESSMENT
SAFETY
SPENT FUEL CASKS
STORAGE
Storage Pool
THERMAL REACTORS
THREE MILE ISLAND-2 REACTOR
Three Mile Island (TMI) Spent Fuel
WASTE MANAGEMENT
WASTE STORAGE
WATER COOLED REACTORS
WATER MODERATED REACTORS
WATER REMOVAL
Handling
& Storage
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
96 KNOWLEDGE MANAGEMENT AND PRESERVATION
CASKS
CONTAINERS
CRITICALITY
DRYING
Drying Process
ENRICHED URANIUM REACTORS
FUEL POOLS
Fault Tree Analysis (FTA)
Integrated Risk Assessment Approach
Long-Term Storage
MANAGEMENT
Nuclear Criticality Safety Program (NCSP)
Operational safety Requirements (OSRs)
POWER REACTORS
PWR TYPE REACTORS
RADIOACTIVE WASTE STORAGE
REACTORS
REMOVAL
RISK ASSESSMENT
SAFETY
SPENT FUEL CASKS
STORAGE
Storage Pool
THERMAL REACTORS
THREE MILE ISLAND-2 REACTOR
Three Mile Island (TMI) Spent Fuel
WASTE MANAGEMENT
WASTE STORAGE
WATER COOLED REACTORS
WATER MODERATED REACTORS
WATER REMOVAL