Multi-component cask for storage and transport of spent nuclear fuel

A multi-component transfer cask system for storage and transport of spent nuclear fuel comprising:

• a vertical longitudinal axis;
• a vertically elongated outer container having a neutron radiation shielding composition, the outer container comprising a top end including an annular top flange, a bottom end, and a cylindrical sidewall extending between the ends and defining a first cavity;
• a vertically elongated inner container having a gamma radiation blocking composition, the inner container comprising a top end including an annular mounting flange, a bottom end, and a sidewall extending between the ends and defining a second cavity configured to hold a spent nuclear fuel canister;
• the mounting flange of the inner container detachably coupled to the top flange of the outer the outer container such that the inner container is suspended and supported via the coupled flanges in a cantilevered manner;
• wherein the inner container is axially and slideably separable from the outer container.

A method for transferring and transporting spent nuclear fuel comprising:

• providing a nuclear fuel transport cask comprising an outer neutron shield cylinder having an internal first cavity and an inner gamma block cylinder having an internal second cavity, the gamma block cylinder detachably coupled to and nested inside the first cavity of the neutron shield cylinder;
• separating the gamma block cylinder from the neutron shield cylinder;
• placing the gamma block cylinder on a support surface;
• loading a plurality of spent nuclear fuel assembles into the second cavity of the gamma block cylinder;
• lifting the gamma block cylinder over the neutron shield cylinder;
• and
• inserting the gamma block cylinder and fuel canister assembly into the neutron shield cylinder.