Disclosed are a composite material and a method for preparing the same. The composite material is consisted of TiO.sub.2 and BaZn.sub.1.2Co.sub.0.8Fe.sub.16O.sub.27. The composite material of the invention has the advantages of high absorption frequency band, good compatibility and wide frequency band, and it is applicable for the shell protection material of a mobile phone or a TV set, thereby absorbing the electromagnetic wave band that is the most harmful to human bodies, without influencing the normal communication function of an electronic device, for example, a mobile phone.

Disclosed are a composite material and a method for preparing the same. The composite material is consisted of TiO.sub.2 and BaZn.sub.1.2Co.sub.0.8Fe.sub.16O.sub.27. The composite material of the invention has the advantages of high absorption frequency band, good compatibility and wide frequency band, and it is applicable for the shell protection material of a mobile phone or a TV set, thereby absorbing the electromagnetic wave band that is the most harmful to human bodies, without influencing the normal communication function of an electronic device, for example, a mobile phone.

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.

A radiographic projector for housing and projecting a radioisotope for use in radiography is described. The front end of the projector has a chamfered surface for receiving an ancillary shielding component. The material used for the front end surface of the projector is tungsten powder in a less dense material matrix. A locking mechanism for a projector is described, including a locking bar for locking a source holder in the projector. The locking mechanism includes an interlock section for retaining the locking bar in an unlocked position while a source holder is not in its storage position, and a latch section for latching the locking bar in the unlocked position prior to engagement of the interlock section. A holster for mounting a radiographic projector and a refraction cage for a remote windout mechanism are also described.

A screen made of radiation shielding material for protecting an operator from ionizing radiation, includes: (i) a lower part equipped with a front wall made of radiation shielding material, having an upper border; (ii) an upper part equipped with a front wall made of a radiation shielding material, at least one part of which is transparent, which front wall includes a lower border; and (iii) at least one passage for the arms of the operator. The front walls of the upper part and of the lower part are separable from each other, the upper part being borne by supporting elements allowing the screen to be reversibly maneuvered either into an active radiation shielding position in which the upper and lower borders are juxtaposed, or into a retracted position in which the upper and lower borders are separated from each other, in order to free a space above the lower part.

The invention relates to a long-term storage device (1) intended to receive a containment case (3) containing radioactive materials, where this device includes a main body (2) having an inner surface delimiting a housing (7). According to the invention, in an unloaded configuration, in which the containment case containing radioactive materials is absent from the storage device, the latter includes a storage case (9) delimiting a cavity (4) to receive the containment case, where the storage device also includes ventilation means allowing air to circulate between the exterior of the storage device and a space delimited between the inner surface of the main body and the storage case (9).

The present invention relates to the long-term preservation of biological material. More specifically, it concerns a preservation container comprising: a biological container for containing biological material, a first shield configured for absorbing gamma-rays, a second shield configured for absorbing ambient neutrons, said second shield surrounding the biological container, the preservation container being of low-radioactivity background materials, and a method for preserving a biological material, comprising: a) providing a biological material in a confinement container, b) providing the preservation container of the invention, c) placing the confinement container containing the biological material into said preservation container, d) storing said preservation container containing the biological material in a room located under a material attenuating cosmic rays and induced particles, said material having a thickness equivalent to 1 m to 7000 m of water, for attenuating cosmic rays.

A radioactive nuclear waste storage system includes a cask comprising a hermetically sealed internal cavity configured for holding the waste such as spent nuclear fuel submerged in an inventory of water. One or more pressure surge capacitors disposed inside the cask include a vacuum cavity evacuated to sub-atmospheric conditions prior to storage of fuel in the cask. At least one rupture disk seals a vacuum chamber inside each capacitor. Each rupture disk is designed and constructed to burst at a predetermined burst pressure level occurring inside the cask external to the capacitor. This allows excess cask pressure occurring during a high pressure excursion resulting from abnormal operating conditions to bleed into capacitor, thereby returning the pressure inside the cask to acceptable levels. In one embodiment, the capacitors are located in peripheral regions of the cask cavity adjacent to the circumferential wall of the cask body.

Provided herein are radioactive lift transport carts including a wheeled base having a platform, a shielding assembly on the platform and including a shield casing having an interior cavity, a first well positioned within the interior cavity and sized to receive a first radioactive payload, a second well positioned within the interior cavity and sized to receive a second radioactive payload, the shield casing extending around the first and second well casings to form one or more shielding cavities between the shield casing and the first and second well casings, radiation shielding material filling the one or more shielding cavities to surround the first and second well casings, a mast extending upward from the wheeled base, a boom extending outward from the mast to form a cantilever, and a lift repositionable along the boom to lift the radioactive payloads out of at least one of the first and second wells.

Provided herein are radioactive lift transport carts including a wheeled base having a platform, a shielding assembly on the platform and including a shield casing having an interior cavity, a first well positioned within the interior cavity and sized to receive a first radioactive payload, a second well positioned within the interior cavity and sized to receive a second radioactive payload, the shield casing extending around the first and second well casings to form one or more shielding cavities between the shield casing and the first and second well casings, radiation shielding material filling the one or more shielding cavities to surround the first and second well casings, a mast extending upward from the wheeled base, a boom extending outward from the mast to form a cantilever, and a lift repositionable along the boom to lift the radioactive payloads out of at least one of the first and second wells.