Post-failure phenomena in LMFBR TOP accidents. Quarterly progress report, January 1, 1976--March 31, 1976
Technical Report
·
OSTI ID:7361895
Refinements were made in the calculations of minimum molten fuel masses required for voiding. These refinements included consideration of condensation heat losses and improved modeling of flow channel geometry. The refined calculations indicate minimum molten fuel masses in excess of 3.2 gm/pin are needed for extensive voiding. Plenum gas release calculations applicable to LOF-driven-TOP and normal LOF accidents as well as to TOP accidents were formulated. Other activities included resolution of discrepancies in PLUTO calculations and attendance at several meetings at NRC's request.
- Research Organization:
- Virginia Univ., Charlottesville (USA). Dept. of Nuclear Engineering
- OSTI ID:
- 7361895
- Report Number(s):
- NP-20942
- Country of Publication:
- United States
- Language:
- English
Similar Records
Post-failure phenomena in LMFBR top accidents. Final report, October 1, 1976--September 30, 1977
Post-failure phenomena in LMFBR TOP accidents. Quarterly progress report, October 1, 1975--December 31, 1975
Post-failure phenomena in LMFBR TOP accidents. Annual report, July 1, 1975--June 30, 1976
Technical Report
·
Mon Oct 31 23:00:00 EST 1977
·
OSTI ID:5010398
Post-failure phenomena in LMFBR TOP accidents. Quarterly progress report, October 1, 1975--December 31, 1975
Technical Report
·
Tue Dec 31 23:00:00 EST 1974
·
OSTI ID:7362756
Post-failure phenomena in LMFBR TOP accidents. Annual report, July 1, 1975--June 30, 1976
Technical Report
·
Fri Dec 31 23:00:00 EST 1976
·
OSTI ID:7108334
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210500 -- Power Reactors
Breeding
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BREEDER REACTORS
ENERGY TRANSFER
EPITHERMAL REACTORS
EXCURSIONS
FAST REACTORS
FBR TYPE REACTORS
FLUID FLOW
FUEL ELEMENT FAILURE
FUEL ELEMENTS
FUEL PINS
FUEL-COOLANT INTERACTIONS
HEAT TRANSFER
LIQUID FLOW
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
LOSS OF FLOW
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR SAFETY
REACTORS
RESEARCH PROGRAMS
SAFETY
VOIDS
210500 -- Power Reactors
Breeding
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BREEDER REACTORS
ENERGY TRANSFER
EPITHERMAL REACTORS
EXCURSIONS
FAST REACTORS
FBR TYPE REACTORS
FLUID FLOW
FUEL ELEMENT FAILURE
FUEL ELEMENTS
FUEL PINS
FUEL-COOLANT INTERACTIONS
HEAT TRANSFER
LIQUID FLOW
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
LOSS OF FLOW
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR SAFETY
REACTORS
RESEARCH PROGRAMS
SAFETY
VOIDS