Investigation of the thermal behavior of 2-1/2 ton cylinder protective overpack
Conference
·
OSTI ID:7052061
UF/sub 6/ cylinders containing reactor grade enriched uranium are transported in protective overpacks. Recently, the design of the 2-1/2 ton UF/sub 6/ cylinder overpack was modified to insure the safety of the cylinder inside the overpack. Modifications include a continuous stainless liner from the outer surface to the inner surface of the overpack and step joints between the upper and lower halves of the overpack. The effects of a continuous stainless steel liner and moisture in the insulation layer of a UF/sub 6/ cylinder protective overpack were investigated with a numerical code. Results were compared with limited available field data. The purpose of comparing the numerical results with field data is to insure the validity of the numerical analysis and the physical properties used in the analysis. The study indicates that the continuous stainless steel liner did not influence the heat transfer rate much from the outer surface of the overpack to the 30B cylinder inside. The effect of step joints was not modeled due to the difficulty of quantifying the leakage rate through the gap. With a continuous stainless steel liner from the outside of the overpack to the inside, the overpack satisfies the thermal design criteria of protecting the cylinder inside for a minimum of 30 minutes when the overpack is exposed to a fire. The effect of moisture inside the insulation layer in the overpack is to reduce the energy to the cylinder with its high thermal capacity. The high pressure steam generated from the moisture will be relieved externally through the vent holes on the outer surface of the overpack. Although these holes are sealed after the overpack is dried, the plug sealing the holes will melt when the overpack is exposed to a fire. 3 refs., 8 figs.
- Research Organization:
- Oak Ridge Gaseous Diffusion Plant, TN (USA)
- DOE Contract Number:
- AC05-84OT21400
- OSTI ID:
- 7052061
- Report Number(s):
- K/QT-166; CONF-880558-9-Vugraphs; ON: DE88010427
- Country of Publication:
- United States
- Language:
- English
Similar Records
Thermal analysis of a 30B cylinder protective overpack
Thermal analysis of UF/sub 6/ cylinder inside a protective overpack
Thermal analysis of UF/sub 6/ cylinder inside a protective overpack
Technical Report
·
Wed Jul 31 00:00:00 EDT 1985
·
OSTI ID:5226236
Thermal analysis of UF/sub 6/ cylinder inside a protective overpack
Conference
·
Tue Dec 31 23:00:00 EST 1985
·
OSTI ID:5824800
Thermal analysis of UF/sub 6/ cylinder inside a protective overpack
Technical Report
·
Fri Oct 31 23:00:00 EST 1986
·
OSTI ID:6994115
Related Subjects
050900* -- Nuclear Fuels-- Transport
Handling
& Storage
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
ACTINIDE COMPOUNDS
CALCULATION METHODS
COMPUTER CODES
CONTAINERS
CONTROL
ENERGY TRANSFER
FIRES
FLUORIDES
FLUORINE COMPOUNDS
HALIDES
HALOGEN COMPOUNDS
HEAT FLUX
HEAT TRANSFER
ISOTOPE ENRICHED MATERIALS
MATERIALS
MODIFICATIONS
PERFORMANCE TESTING
T CODES
TEMPERATURE CONTROL
TESTING
THERMAL ANALYSIS
THERMAL INSULATION
TRANSPORT
URANIUM COMPOUNDS
URANIUM FLUORIDES
URANIUM HEXAFLUORIDE
Handling
& Storage
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
ACTINIDE COMPOUNDS
CALCULATION METHODS
COMPUTER CODES
CONTAINERS
CONTROL
ENERGY TRANSFER
FIRES
FLUORIDES
FLUORINE COMPOUNDS
HALIDES
HALOGEN COMPOUNDS
HEAT FLUX
HEAT TRANSFER
ISOTOPE ENRICHED MATERIALS
MATERIALS
MODIFICATIONS
PERFORMANCE TESTING
T CODES
TEMPERATURE CONTROL
TESTING
THERMAL ANALYSIS
THERMAL INSULATION
TRANSPORT
URANIUM COMPOUNDS
URANIUM FLUORIDES
URANIUM HEXAFLUORIDE