The present disclosure relates to a transfer cask for transferring spent nuclear fuel. The transfer cask transfers a canister storing the spent nuclear fuel and includes a transfer container having a space for accommodating the canister; a neutron shielding body arranged on an outer periphery of the transfer container to shield neutrons; and an opening/closing portion that is coupled to a lower portion of the transfer container and opens and closes the lower portion of the transfer container, wherein the opening and closing portion, a support portion supporting the transfer container and having a first through hole in communication with the transfer container; a lid assembly having a first lid portion and a second lid portion that open and close the first through hole; and a base plate on which the support portion is seated and a second through hole through which the canister is drawn out is formed.

In general, radiation shielding systems that shield radiation from multiple directions are described. In one embodiment, a method of shielding radiation is provided, including supporting a shielding device on an object proximate a radiation source, positioning a first shielding portion in a vertical position relative to the object, positioning a second shielding portion to extend away from the first portion, the second shielding portion attached to the first portion, and shielding radiation from the radiation source by the first shielding portion and the second shielding portion such that the first and second shielding portions provide a radiation shielding zone for a healthcare practitioner.

In general, radiation shielding systems that shield radiation from multiple directions are described. In one embodiment, a method of shielding radiation is provided, including supporting a shielding device on an object proximate a radiation source, positioning a first shielding portion in a vertical position relative to the object, positioning a second shielding portion to extend away from the first portion, the second shielding portion attached to the first portion, and shielding radiation from the radiation source by the first shielding portion and the second shielding portion such that the first and second shielding portions provide a radiation shielding zone for a healthcare practitioner.

A containment enclosure for shielding an outer cask containing an inner canister loaded with nuclear waste such as spent fuel rods. The enclosure includes a lower base portion at least partially embedded in a concrete pad and an upper radiation shielding portion defined by a shield jacket coupled to and supported by the lower base portion at a circumferential joint. Cavities of the base and shielding portions collectively define a contiguous containment space for the cask. A portion of the cask resides in each of the base and shielding portions which completely enclose and shield the cask to minimize radiation dosage of personnel in the environment surrounding the cask. The cask is cooled by a natural convectively-driven ambient cooling air ventilation system including air inlets at the circumferential joint of the enclosure. The concrete pad may be part of a spent nuclear fuel storage installation comprising plural cask containment enclosures.

In general, radiation shielding systems that shield radiation from multiple directions are described. In one embodiment, a method of shielding radiation is provided, including supporting a shielding device on an object proximate a radiation source, positioning a first shielding portion in a vertical position relative to the object, positioning a second shielding portion to extend away from the first portion, the second shielding portion attached to the first portion, and shielding radiation from the radiation source by the first shielding portion and the second shielding portion such that the first and second shielding portions provide a radiation shielding zone for a healthcare practitioner.

Method for long-term dry storage of spent nuclear fuel includes injecting the inert gas into a cavity formed in a cask between inner and outer lids under pressure greater than the pressure of the inert gas in the inner cavity of the cask in which the spent nuclear fuel is located. The cask contains a body with a spent nuclear fuel container placed in it, tight inner and outer lids forming a cavity into which the inert gas is pumped under pressure greater than the pressure in the inner cavity of the cask. The outer lid comprises a labyrinth hole closed with a flange and sealed with a gasket. The flange comprises an angle valve, to which at least two pressure sensors are connected. The angle valve and sensors are covered with a protective cover during long-term storage. The gasket is installed in an annular groove of the lower flange.

Method for long-term dry storage of spent nuclear fuel includes injecting the inert gas into a cavity formed in a cask between inner and outer lids under pressure greater than the pressure of the inert gas in the inner cavity of the cask in which the spent nuclear fuel is located. The cask contains a body with a spent nuclear fuel container placed in it, tight inner and outer lids forming a cavity into which the inert gas is pumped under pressure greater than the pressure in the inner cavity of the cask. The outer lid comprises a labyrinth hole closed with a flange and sealed with a gasket. The flange comprises an angle valve, to which at least two pressure sensors are connected. The angle valve and sensors are covered with a protective cover during long-term storage. The gasket is installed in an annular groove of the lower flange.

A containment enclosure for shielding an outer cask containing an inner canister loaded with nuclear waste such as spent fuel rods. The enclosure includes a lower base portion at least partially embedded in a concrete pad and an upper radiation shielding portion defined by a shield jacket coupled to and supported by the lower base portion at a circumferential joint. Cavities of the base and shielding portions collectively define a contiguous containment space for the cask. A portion of the cask resides in each of the base and shielding portions which completely enclose and shield the cask to minimize radiation dosage of personnel in the environment surrounding the cask. The cask is cooled by a natural convectively-driven ambient cooling air ventilation system including air inlets at the circumferential joint of the enclosure. The concrete pad may be part of a spent nuclear fuel storage installation comprising plural cask containment enclosures.

The present disclosure relates to a radiographic shield incorporating a radiographic shutter mechanism, and a protective jacket for a radiographic device. The radiographic shutter mechanism includes machined tungsten components which in some embodiments, includes a jigsaw puzzle type interconnection, the radiographic shield includes an S-shaped passageway in combination with the radiographic shutter mechanism. The protective jacket allows for various mounting configurations, such as integrated SCAR mounting configurations, including a ratchet snap configuration.

A portable XRF analyzer includes a hand shield to substantially block x-rays from impinging on a hand of a user. The portable XRF analyzer includes a heat sink over an x-ray source and a heat sink over an x-ray detector. The heat sinks are separated from each other by a thermally insulative material.