Status of radiation shield design for liquid metal fast breeder reactor spent fuel shipping cask application
Neutron and gamma-ray transport calculations in one-dimensional cylindrical geometry have been performed on a trial reference LMFBR spent-fuel shipping cask that could transport one CRBR subassembly. In the study it was assumed that a layer of depleted U and a layer of neutron shielding materials were sandwiched between 5.08-cm-thick (2-in.) layers of stainless steel. The thicknesses of the internal layers were adjusted until a balanced dose rate (50 percent neuton and 50 percent gamma-ray) of 5 mrem/hr was achieved at a point 1.83 m (6 ft) from the cask surface. Neutron-shield materials considered were LiH, Be, B/sub 4/C, DiH/sub 2/./sub 5/, and C (graphite). Of these materials, LiH provided the smallest, lightest, and least expensive cask; however, its use would be contigent on expansion of production facilities for LiH and development of a canning or cladding procedure. The B/sub 4/C shielded cask would offer the best alternative if the designs were limited to those using currently available materials.
- Research Organization:
- Sandia Labs., Albuquerque, NM (USA)
- DOE Contract Number:
- E(29-1)-789
- OSTI ID:
- 7330423
- Report Number(s):
- SAND-76-0595
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
210500 -- Power Reactors
Breeding
42 ENGINEERING
420204* -- Engineering-- Shipping Containers
ACTINIDES
ALKALI METAL COMPOUNDS
BIOLOGICAL SHIELDING
BIOLOGICAL SHIELDS
BORON CARBIDES
BORON COMPOUNDS
BREEDER REACTORS
CARBIDES
CARBON
CARBON COMPOUNDS
CASKS
CONTAINERS
DEPLETED URANIUM
DESIGN
ELEMENTS
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FUEL ELEMENTS
GRAPHITE
HYDRIDES
HYDROGEN COMPOUNDS
LIQUID METAL COOLED REACTORS
LITHIUM COMPOUNDS
LITHIUM HYDRIDES
LMFBR TYPE REACTORS
METALS
NONMETALS
RARE EARTHS
REACTOR COMPONENTS
REACTORS
SHIELDING
SHIELDS
SPENT FUEL CASKS
SPENT FUEL ELEMENTS
URANIUM