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.

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 compression member for insertion into a pig for transporting a container of biohazardous materials includes a flange maintained in spaced relation with an annulus by pillars; and spaced apart pivotable grip components supported by the annulus and extending downwards from the annulus between respective ones of the pillars towards, but not into contact with, the flange, the pivotable grip components resiliently compressible inwardly against the container when the container is received within the compression member. In use, the compression member receives at least a closure portion of the container and, in turn, is itself received within a complementary annulus of the pig. When being received within the complementary annulus of the pig, the pivotable grip components are urged inwards towards the container thereby to grip the container and provide a spacer for between this portion of the container and the pig.

A method of packaging a radioactive waste including the steps of: (a) providing a containment enclosure having (i) an outer polymeric fabric layer and (ii) an inner polymeric fabric layer, wherein the outer and inner polymeric fabric layers are thermally stable to −40° F.; (b) placing a radioactive waste within the inner polymeric fabric layer; and (c) closing an outer closeable flap on the outer polymeric fabric layer.

A storage apparatus is provided for dry storage of radioactive nuclear waste. The storage apparatus comprises a sealed canister containing the radioactive nuclear waste and an outer ventilated metal storage overpack (VMSO). The VMSO has a plurality of vents to enable ambient air flow through the VMSO and around the canister to thereby dissipate heat from the canister. The VMSO has a side wall having an inner metal layer and one or more sets of alternating layers. Each set includes a neutron absorbing layer adjacent to another metal layer so that neutron absorbing and metal layers alternate throughout the side wall. The neutron absorbing layer or layers are designed to absorb neutron particles radiated from the radioactive nuclear waste and the metal layers are designed to absorb gamma particles radiated from the radioactive nuclear waste as well as radiated from the neutron absorbing layer or layers that result from reactions associated with absorption of neutron particles.

A storage apparatus is provided for dry storage of radioactive nuclear waste. The storage apparatus comprises a sealed canister containing the radioactive nuclear waste and an outer ventilated metal storage overpack (VMSO). The VMSO has a plurality of vents to enable ambient air flow through the VMSO and around the canister to thereby dissipate heat from the canister. The VMSO has a side wall having an inner metal layer and one or more sets of alternating layers. Each set includes a neutron absorbing layer adjacent to another metal layer so that neutron absorbing and metal layers alternate throughout the side wall. The neutron absorbing layer or layers are designed to absorb neutron particles radiated from the radioactive nuclear waste and the metal layers are designed to absorb gamma particles radiated from the radioactive nuclear waste as well as radiated from the neutron absorbing layer or layers that result from reactions associated with absorption of neutron particles.

[Object] To provide a radiation shielding material that includes a resin composition obtained by filling a matrix formed of resin with a radiation-absorbing substance and is capable of obtaining a structure in which transparency is significantly improved as compared with the conventional radiation shielding material while having a radiation shielding effect similar to that of the conventional radiation shielding material.

[Solving Means] A radiation shielding material includes: a resin composition containing a proportion of 20 to 80 vol % of fluoride powder containing barium as a constituent element. The fluoride powder is favorably barium fluoride or lithium barium fluoride, the resin favorably has a refractive index (n) of 1.4 to 1.6, and particularly, a difference between a refractive index of the resin and a refractive index of the fluoride powder is favorably within ±0.05.

The invention generally relates to a radiation shielding apparatus that includes a shielding box unit into which a radiation generating device is inserted, a locking unit disposed on an outside of the shielding box unit, an operation display unit disposed on the outside of the shielding box unit to display a locked state of the locking unit, and a control unit for controlling an operation of each of the radiation generating device and the operation display unit.

The present disclosure provides a linked antenna pair for a shipping container having a thermally insulated and electromagnetically shielded cavity for holding a payload. The linked antenna pair comprises a first antenna disposed inside the cavity, a second antenna disposed outside the cavity, and a feed line that electrically connects the first antenna to the second antenna.

The present disclosure provides a linked antenna pair for a shipping container having a thermally insulated and electromagnetically shielded cavity for holding a payload. The linked antenna pair comprises a first antenna disposed inside the cavity, a second antenna disposed outside the cavity, and a feed line that electrically connects the first antenna to the second antenna.