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

Technical Report ·
OSTI ID:7330423

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