THETA1B; fuel rod thermal response loss of coolant accidents. [IBM360/75; FORTRAN IV]
Technical Report
·
OSTI ID:6344506
THETA1B computes the thermal response characteristics of a nuclear fuel rod subjected to a loss-of-coolant accident environment.IBM360/75; FORTRAN IV; OS/360; 400K bytes of core memory are required.
- Research Organization:
- EG and G Idaho, Inc., Idaho Falls (USA)
- OSTI ID:
- 6344506
- Report Number(s):
- ANL/NESC-512; ON: DE83048512
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100* -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
ACCIDENTS
COMPUTER CODES
ENERGY TRANSFER
FLUID FLOW
FUEL ELEMENTS
FUEL RODS
HEAT TRANSFER
LOSS OF COOLANT
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTORS
T CODES
TRANSIENTS
WATER COOLED REACTORS
210100* -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
ACCIDENTS
COMPUTER CODES
ENERGY TRANSFER
FLUID FLOW
FUEL ELEMENTS
FUEL RODS
HEAT TRANSFER
LOSS OF COOLANT
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTORS
T CODES
TRANSIENTS
WATER COOLED REACTORS