TMI-2 Defueling Canister Reactivity Analysis
Conference
·
· Transactions of the American Nuclear Society
OSTI ID:6883268
- Babcock and Wilcox, Lynchburg, VA (United States)
The accident at Three Mile Island Unit 2 (TMI-2) resulted in most of the reactor core's being reduced to debris ranging in size from very small fines to partial fuel assemblies. Babcock and Wilcox has designed three types of defueling canisters to receive this range of debris. Supporting these designs, detailed Monte Carlo reactivity calculations have been performed to ensure the criticality safety of each canister during the various loading, transfer, and storage conditions at the TMI-2 site.
- Research Organization:
- Babcock and Wilcox, Lynchburg, VA (United States)
- Sponsoring Organization:
- USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
- OSTI ID:
- 6883268
- Report Number(s):
- CONF-860610-
- Conference Information:
- Journal Name: Transactions of the American Nuclear Society Journal Volume: 52
- Country of Publication:
- United States
- Language:
- English
Similar Records
Criticality Safety for TMI-2 Canister Storage at INEL
Unique applications of underwater tooling: the TMI-2 defueling experience
Ex-Vessel Defueling for TMI-2
Conference
·
Sun Jun 15 00:00:00 EDT 1986
· Transactions of the American Nuclear Society
·
OSTI ID:6883258
Unique applications of underwater tooling: the TMI-2 defueling experience
Conference
·
Tue Dec 31 23:00:00 EST 1985
· Trans. Am. Nucl. Soc.; (United States)
·
OSTI ID:6657598
Ex-Vessel Defueling for TMI-2
Conference
·
Sun Jun 07 00:00:00 EDT 1987
· Transactions of the American Nuclear Society
·
OSTI ID:5578362
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
97 MATHEMATICS AND COMPUTING
COMPUTER CODES
CONTAINERS
CORIUM
DEMOLITION
ENRICHED URANIUM REACTORS
FUEL ASSEMBLIES
K CODES
MONTE CARLO METHOD
MULTIPLICATION FACTORS
Nuclear Criticality Safety Program (NCSP)
POWER REACTORS
PWR TYPE REACTORS
REACTIVITY
REACTOR DISMANTLING
REACTORS
REMOVAL
STORAGE
THERMAL REACTORS
THREE MILE ISLAND-2 REACTOR
Three Mile Island Unit 2 (TMI-2)
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
97 MATHEMATICS AND COMPUTING
COMPUTER CODES
CONTAINERS
CORIUM
DEMOLITION
ENRICHED URANIUM REACTORS
FUEL ASSEMBLIES
K CODES
MONTE CARLO METHOD
MULTIPLICATION FACTORS
Nuclear Criticality Safety Program (NCSP)
POWER REACTORS
PWR TYPE REACTORS
REACTIVITY
REACTOR DISMANTLING
REACTORS
REMOVAL
STORAGE
THERMAL REACTORS
THREE MILE ISLAND-2 REACTOR
Three Mile Island Unit 2 (TMI-2)
WATER COOLED REACTORS
WATER MODERATED REACTORS