Provided are systems for filling containers with radioactive and/or other types of potentially hazardous materials. In some aspects, the systems include a shielding material that substantially defines a chamber and, preferably, substantially blocks radioactivity, a conduit extending from outside to into the chamber, and a unit that is disposed in the chamber proximal to the conduit and is adapted to receive a capsule through the conduit. The systems of the present disclosure can further comprise a syringe, a syringe controller that is disposed in the dispensing chamber and adapted to meter an aliquot from a radioactive stock solution and inject the aliquot into the capsule or a vial.

[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.

[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 present invention provides systems, methods and devices for storing and/or disposing of hazardous waste material. In some embodiments, the waste material includes nuclear waste such as calcined material. In certain embodiments, the device includes a container having a container body, a filling port configured to couple with a filling nozzle and a filling plug, and an evacuation port having a filter. The evacuation port is configured to couple with an evacuation nozzle and an evacuation plug. In certain embodiments, the method includes (a) adding hazardous waste material via a filling nozzle coupled to a filling port of a container, the container including an evacuation port, (b) evacuating the container during adding of the hazardous waste material via an evacuation nozzle coupled to an evacuation port of the container, (c) sealing the filling port, (d) heating the container, and (e) sealing the evacuation port.

The present invention provides systems, methods and devices for storing and/or disposing of hazardous waste material. In some embodiments, the waste material includes nuclear waste such as calcined material. In certain embodiments, the device includes a container having a container body, a filling port configured to couple with a filling nozzle and a filling plug, and an evacuation port having a filter. The evacuation port is configured to couple with an evacuation nozzle and an evacuation plug. In certain embodiments, the method includes (a) adding hazardous waste material via a filling nozzle coupled to a filling port of a container, the container including an evacuation port, (b) evacuating the container during adding of the hazardous waste material via an evacuation nozzle coupled to an evacuation port of the container, (c) sealing the filling port, (d) heating the container, and (e) sealing the evacuation port.

There is disclosed a canister for interim storage and subsequent consolidation of waste materials via hot pressing. In an embodiment, the canister comprises at least one ion exchange material, and is configured to: house the ion exchange material after it is exchanged with a contaminating ion without releasing the contaminating ion; and consolidate via hot-isostatic pressing. There is also disclosed a contacting a fluid waste with an ion exchange material, wherein the ion exchange material is located in a canister; evacuating the canister; and hot isostatically pressing (HIP) the canister until it collapses under HIP conditions.

A vessel for removing radionuclides from a liquid. The vessel comprises a shielded housing comprising an outer shell and an inner shell disposed within the outer shell. The housing defines an ion exchange chamber between the inner and outer shells. The vessel also comprises an inlet fluidly coupled with the ion exchange chamber, the inlet being configured for fluid communication with a source of the liquid, and an outlet fluidly coupled with the ion exchange chamber, the outlet being configured for fluid communication with a destination of the liquid. The vessel further comprises a first fluid passage extending between an exterior of the vessel and the inner shell and a second fluid passage extending between the exterior of the vessel and the inner shell.

A method of stabilizing virgin ion exchange resin material is provided. The method includes rinsing virgin ion exchange resin material with deoxygenated water, introducing the rinsed virgin ion exchange resin material into a gas impermeable vessel and hermetically sealing the vessel. A vessel containing deoxygenated water and virgin ion exchange resin material is also provided. A method of facilitating water treatment in a site in need thereof by providing the gas impermeable vessel containing virgin ion exchange resin material and residual moisture from deoxygenated water is also provided.

A method of stabilizing virgin ion exchange resin material is provided. The method includes rinsing virgin ion exchange resin material with deoxygenated water, introducing the rinsed virgin ion exchange resin material into a gas impermeable vessel and hermetically sealing the vessel. A vessel containing deoxygenated water and virgin ion exchange resin material is also provided. A method of facilitating water treatment in a site in need thereof by providing the gas impermeable vessel containing virgin ion exchange resin material and residual moisture from deoxygenated water is also provided.

A vessel for treatment of radioactive liquid. The vessel comprises a shielded housing defining an ion exchange chamber therein. The ion exchange chamber is configured to receive ion exchange media in its interior between an interior top surface and an interior bottom surface. The vessel further comprises an inlet diffuser disposed in the ion exchange chamber proximate the bottom surface and an outlet collection header disposed in the ion exchange chamber proximate the top surface. Also, the vessel comprises a process inlet in fluid communication with the inlet diffuser and a process outlet in fluid communication with the outlet collection header.