Preliminary high level waste conceptual cask designs and an assessment of a clad waste cask
Neutron and gamma-ray transport calculations in one- and two-dimensional cylindrical geometry have been performed for a number of high-level waste and cladding waste conceptual cask shield designs. Stainless-steel-lined depleted uranium and lead were the primary gamma-shield materials considered in this study. The thicknesses of these shield-material regions were varied until the total dose rate, at 91.44 cm (3 ft) from the cask surface, was less than 1000 mrem/hr for accident environments. Neutron-shield materials including borated beechwood, water, serpentine, and calcium borate were then added to the cask surface until the total dose rate, at 1.83 m (6 ft) from the cask surface, was less than 10 mrem/hr for normal operating conditions. It was determined that the best combination of these shield materials, based on overall cask dimensions was depleted uranium and borated beechwood.
- Research Organization:
- Sandia Labs., Albuquerque, NM (USA)
- DOE Contract Number:
- EY-76-C-04-0789
- OSTI ID:
- 6824183
- Report Number(s):
- SAND-77-2030
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
ACTINIDES
CASKS
CONTAINERS
DEPLETED URANIUM
DESIGN
ELEMENTS
HIGH-LEVEL RADIOACTIVE WASTES
MANAGEMENT
METALS
NEUTRAL-PARTICLE TRANSPORT
NEUTRON TRANSPORT
ONE-DIMENSIONAL CALCULATIONS
PHOTON TRANSPORT
RADIATION TRANSPORT
RADIOACTIVE MATERIALS
RADIOACTIVE WASTE DISPOSAL
RADIOACTIVE WASTES
SHIELDING
TWO-DIMENSIONAL CALCULATIONS
URANIUM
WASTE DISPOSAL
WASTE MANAGEMENT
WASTES
WOOD