Pacific Nuclear Systems, Inc.

Nutech Corporation

Ian D McInnes

Robert D Quinn

Charles J Temus

Robert A Lehnert

Steven E Sisley

Kyle B Jones

Larry E Fischer

John V Massey

Robert A Johnson

The present invention provides a cask (10) for transport and short-term storage of spent nuclear fuel. The cask 10 includes a structural shell (14) defining a cavity (40) for receiving spent nuclear fuel. The shell is formed from an upper shell portion (16) formed of a first metal and a lower shell portion (18) formed from a second metal. The first metal utilized to form the upper shell portion has a higher load bearing strength than the second metal utilized to form the lower shell portion. A bearing surface is defined on the upper shell portion by trunnions (30) mounted within sleeves (32) secured to the upper shell portion. The trunnions (30) each define a bearing projection (160) that is engageable to enable hoisting of the cask, with the tensile and shear loads of hoisting the cask being transferred from the trunnions to the trunnion mounting sleeves, and thus to the upper shell portion of the structural shell. The cask further includes a bottom closure plate (20) secured to the bottom end of the shell, and a top closure plate releasably securable to the top end of the shell. A neutron radiation absorbing shield jacket (28) is formed about the exterior of the structural shell.

Transportation and storage cask for spent nuclear fuels

A skid for transporting a nuclear fuel transportation cask. The skid comprises a supporting member having parallel spaced-apart plates. The plates are aligned perpendicular to a longitudinal axis of the cask, include a semi-circular trough for mating with the cask, and are connected by longitudinal fins parallel to the longitudinal axis of the cask. The skid also comprises a retaining member including parallel spaced-apart plates. The plates of the retaining member are aligned perpendicular to a longitudinal axis of the cask, include a trough for mating with the cask, and are connected by longitudinal fins parallel to the longitudinal axis of the cask. The fins of the supporting member are spaced apart such that when the cask rests in the trough of the supporting member, the fins of the supporting member are aligned with elongate members of the cask neutron radiation shielding material to transfer the load between the cask and the skid.

Skid for transporting a nuclear fuel transportation cask

The present invention provides a cask (10) for transport and short-term storage of spent nuclear fuel. The cask 10 includes a structural shell (14) defining a cavity (40) for receiving spent nuclear fuel. The shell is formed from an upper shell portion (16) formed of a first metal-and a lower shell portion (18) formed from a second metal. The first metal utilized to form the upper shell portion has a higher load bearing strength than the second metal utilized to form the lower shell portion. A bearing surface is defined on the upper shell portion by trunnions (30) mounted within sleeves (32) secured to the upper shell portion. The trunnions (30) each define a bearing projection (160) that is engageable to enable hoisting of the cask, with the tensile and shear loads of hoisting the cask being transferred from the trunnions to the trunnion mounting sleeves, and thus to the upper shell portion of the structural shell. The cask further includes a bottom closure plate (20) secured to the bottom end of the shell, and a top closure plate releasably securable to the top end of the shell. A neutron radiation absorbing shield jacket (28) is formed about the exterior of the structural shell.

Impact limiters having noncircular outer peripheries are described for use to protect nuclear fuel transportation casks. The impact limiters include two different materials as impact absorbing materials. The impact limiter includes multiple sides and a tapered cap.

Impact limiter for spent nuclear fuel transportation cask

A horizontal, modular, dry, irradiated fuel storage system (10) includes a thin-walled canister (12) for containing irradiated fuel assemblies (20), which canister (12) can be positioned in a transfer cask (14) and transported in a horizontal manner from a fuel storage pool (18), to an intermediate-term storage facility. The storage system (10) includes a plurality of dry storage modules (26) which accept the canister (12) from the transfer cask (14) and provide for appropriate shielding about the canister (12). Each module (26) also provides for air cooling of the canister (12) to remove the decay heat of the irradiated fuel assemblies (20). The modules (26) can be interlocked so that each module (26) gains additional shielding from the next adjacent module (26). Hydraulic rams (30) are provided for inserting and removing the canisters (12) from the modules (26).

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San Jose, CA, United States of America

Ian D McInnes