Ex-Vessel Defueling for TMI-2
Conference
·
· Transactions of the American Nuclear Society
OSTI ID:5578362
As a consequence of the Three Mile Island Unit 2 (TMI-2) accident, the fuel was severely damaged, and fuel fines and fuel rubble were transported throughout the reactor coolant system (RCS) and to other systems connected to the RCS. Estimates of the quantity of fuel in equipment and piping outside the reactor vessel boundary have been developed based on component specific methods, such as sampling, monitoring by camera, and gamma spectroscopy. To ensure a safe, stable plant configuration during the postdefueling monitored storage (PDMS) phase, fuel must be removed from any area if the potential for criticality exists. The fuel quantity estimate is therefore used as a simple guideline to indicate potential need to removal fuel from ex-vessel locations. The juxtaposition of multiple fuel containing components is also considered. Components that have been considered as candidates for possible fuel removal are shown, and their estimated fuel quantities are listed. Three systems have been designed to defuel three specific ex-vessel areas: the pressurizer defueling system, the pressurizer spray line defueling system, and the plenum defueling system.
- Sponsoring Organization:
- USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
- OSTI ID:
- 5578362
- Report Number(s):
- CONF-870601-
- Conference Information:
- Journal Name: Transactions of the American Nuclear Society Journal Volume: 54
- Country of Publication:
- United States
- Language:
- English
Similar Records
TMI-2 (Three Mile Island Unit 2) Ex-Vessel Defueling
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Conference
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Sun Oct 30 00:00:00 EDT 1988
· Transactions of the American Nuclear Society
·
OSTI ID:5839170
Estimated source terms for radionuclides and suspended particulates during TMI-2 defueling operations report on Phase I
Technical Report
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Thu Dec 31 23:00:00 EST 1981
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OSTI ID:5558975
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Related Subjects
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
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ACCIDENTS
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COOLING SYSTEMS
CORIUM
CRITICALITY
DEMOLITION
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ENRICHED URANIUM REACTORS
GAMMA SPECTROSCOPY
HYDROGEN COMPOUNDS
Nuclear Criticality Safety Program (NCSP)
OXYGEN COMPOUNDS
POWER REACTORS
PRESSURIZERS
PWR TYPE REACTORS
Postdefueling Monitored Storage (PDMS) Phase
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR DISMANTLING
REACTORS
SAMPLING
SPECTROSCOPY
THERMAL REACTORS
THREE MILE ISLAND-2 REACTOR
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WATER
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WATER MODERATED REACTORS
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
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Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
CLEANING
COOLING SYSTEMS
CORIUM
CRITICALITY
DEMOLITION
ENERGY SYSTEMS
ENRICHED URANIUM REACTORS
GAMMA SPECTROSCOPY
HYDROGEN COMPOUNDS
Nuclear Criticality Safety Program (NCSP)
OXYGEN COMPOUNDS
POWER REACTORS
PRESSURIZERS
PWR TYPE REACTORS
Postdefueling Monitored Storage (PDMS) Phase
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR DISMANTLING
REACTORS
SAMPLING
SPECTROSCOPY
THERMAL REACTORS
THREE MILE ISLAND-2 REACTOR
Three Mile Island Unit 2 (TMI-2) Accident
WATER
WATER COOLED REACTORS
WATER MODERATED REACTORS