Status of radiation shield design for liquid metal fast breeder reactor spent fuel shipping cask application

Technical Report · Wed Sep 01 00:00:00 EDT 1976

OSTI ID:7330423

Dupree, S A; Rack, H J

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; TRN: 77-006534
• Country of Publication: United States
• Language: English

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