ALARA studies on spent fuel and waste casks

Technical Report · Tue Apr 01 04:00:00 EST 1980

DOI:https://doi.org/10.2172/5439456· OSTI ID:5439456

Sutherland, S H

In this report, some implications of applying the ALARA concept to cask designs for transporting spent fuel, high-level commercial and defense waste, and remote-handled transuranic waste are investigated. The XSDRNPM, one-dimensional radiation transport code, was used to obtain potential shield designs that would yield total dose rates at 1.8 m from the cask surface of 10, 5, and 2 mrem/h. Gamma shields of depleted uranium, lead, and steel were studied. The capacity of the casks was assumed to be 1, 4, or 7 elements or canisters, and the wastes were 1, 3, 5, and 10 years old. Depending on the dose rate, the cask empty weights and lifetime transportation costs were estimated.

• Research Organization: Sandia Labs., Albuquerque, NM (USA)
• DOE Contract Number: EY-76-C-04-0789
• OSTI ID: 5439456
• Report Number(s): SAND-79-1841; TTC-0050
• Country of Publication: United States
• Language: English

Related Subjects

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Handling
& Storage
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
42 ENGINEERING
420204* -- Engineering-- Shipping Containers
CASKS
CONTAINERS
COST
DESIGN
DOSE RATES
HIGH-LEVEL RADIOACTIVE WASTES
MANAGEMENT
RADIATION PROTECTION
RADIOACTIVE MATERIALS
RADIOACTIVE WASTES
SHIELDS
SPENT FUEL CASKS
TRANSPORT
WASTE MANAGEMENT
WASTE TRANSPORTATION
WASTES