LMFBR fuel analysis. Task A: Oxide fuel dynamics. Final report, October 1, 1976--September 30, 1977

Technical Report · Sat Oct 01 00:00:00 EDT 1977

DOI:https://doi.org/10.2172/5010407· OSTI ID:5010407

Dhir, V K; Doshi, J; Frank, M; Hauss, B; Kastenberg, W E; Wong, K

The study presented deals with several areas of uncertainty in the analysis of the unprotected overpower transient for the Clinch River Breeder Reactor. These areas of uncertainty include the time, place, and mode of fuel pin failure; pre-failure fuel motion; fuel freezing, plugging, and plate-out following pin failure; and the potential for re-criticality. Internal molten fuel motion prior to pin failure was found to be sensitive to ramp rate and burnup. The strain-limit fuel failure criterion was found to be inappropriate for analysis based on existing data. The coupling of pre-transient- and transient-induced stresses tended to force the failure location towards the core midplane.

• Research Organization: California Univ., Los Angeles (USA). Dept. of Chemical, Nuclear, and Thermal Engineering
• Sponsoring Organization: USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
• OSTI ID: 5010407
• Report Number(s): NUREG/CR-0011
• Country of Publication: United States
• Language: English

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
CLINCH RIVER BREEDER REACTOR
CORIUM
CRITICAL SIZE
CRITICALITY
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FLUID MECHANICS
FUEL ELEMENT FAILURE
FUEL ELEMENTS
FUEL PINS
HYDRAULICS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
MECHANICS
MELTDOWN
Nuclear Criticality Safety Program (NCSP)
POWER REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR SAFETY
REACTORS
SAFETY
SIZE
SODIUM COOLED REACTORS
STRESSES
TEMPERATURE GRADIENTS
TRANSIENTS