Criticality Analyses for TMI-2 Defueling
Conference
·
OSTI ID:6077302
- Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
A bounding strategy has been adopted for assuring subcriticality during all TMI-2 defueling operations. The strategy is based upon establishing a safe soluble boron level for the entire reactor core in an optimum reactivity configuration. This paper presents the determination of a fuel rubble model which yields a maximum infinite lattice multiplication factor and the subsequent application of cell-averaged constants in finite system analyses. Included in the analyses are the effects of fuel burnup determined from a simplified power history of the reactor. A discussion of the analytical methods employed and the determination of an analytical bias with benchmark critical experiments completes the presentation.
- Research Organization:
- Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
- Sponsoring Organization:
- USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
- DOE Contract Number:
- AC05-84OR21400
- OSTI ID:
- 6077302
- Report Number(s):
- CONF-850917-7; ON: DE86008974
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
220900* -- Nuclear Reactor Technology-- Reactor Safety
Analytical Bias Determination
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BORON
BURNUP
CRITICALITY
ELEMENTS
ENRICHED URANIUM REACTORS
Fuel Rubble Model
Nuclear Criticality Safety Program (NCSP)
Optimum Reactivity Configuration
POWER REACTORS
PWR TYPE REACTORS
REACTIVITY
REACTOR FUELING
REACTORS
SAFETY
SEMIMETALS
Safe Soluble Boron Level
THERMAL REACTORS
THREE MILE ISLAND-2 REACTOR
Three Mile Island
Unit 2 (TMI-2) Defueling Operations
WATER COOLED REACTORS
WATER MODERATED REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
220900* -- Nuclear Reactor Technology-- Reactor Safety
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Analytical Methods
BORON
BURNUP
CRITICALITY
ELEMENTS
ENRICHED URANIUM REACTORS
Fuel Rubble Model
Nuclear Criticality Safety Program (NCSP)
Optimum Reactivity Configuration
POWER REACTORS
PWR TYPE REACTORS
REACTIVITY
REACTOR FUELING
REACTORS
SAFETY
SEMIMETALS
Safe Soluble Boron Level
THERMAL REACTORS
THREE MILE ISLAND-2 REACTOR
Three Mile Island
Unit 2 (TMI-2) Defueling Operations
WATER COOLED REACTORS
WATER MODERATED REACTORS