Disclosed is a radiation shielding tube, wherein a guide tube is made of tungsten or the like, which is excellent in shielding performance, and is configured to be movable depending on various positions where a collimator is installed, so that the guide tube can effectively shield a radiation exposed during movement of a radiation source or RT work in the tube. The radiation shielding tube has a guide tube which is disposed between a radiation source container and a collimator and connects them to each other, and the guide tube is formed in an articular form to be bendable.

Disclosed is a radiation shielding tube, wherein a guide tube is made of tungsten or the like, which is excellent in shielding performance, and is configured to be movable depending on various positions where a collimator is installed, so that the guide tube can effectively shield a radiation exposed during movement of a radiation source or RT work in the tube. The radiation shielding tube has a guide tube which is disposed between a radiation source container and a collimator and connects them to each other, and the guide tube is formed in an articular form to be bendable.

A bunker system for shielding radiation emitted from a radiation treatment device includes a multi-core wall structure that completely surrounds the radiation treatment device. The wall structure includes a cast-in-place concrete inner core of limited thickness in order to minimize curing time requirements. The inner core is immediately surrounded by an outer core constructed from a plurality of preformed modular blocks. Each modular block is constructed of a radiation shielding material, such as concrete. As part of the assembly process, the preformed modular blocks are designed to be stacked top-to-bottom and side-by-side in an interlocking fashion to form a continuous wall structure, with blocks additionally arranged in a front-to-back relationship to achieve the required outer core thickness. The dual-core construction of the wall structure enables the bunker system to be quickly and efficiently assembled with enhanced quality control and potential reusability.

The invention relates to a technique for handling liquid radioactive waste from a nuclear fuel-energy cycle, and may be used in a process for processing liquid radioactive waste for maximally reducing the volume thereof and removing radionuclides by concentrating same in a solid phase. The aim is achieved by means of a method for processing liquid radioactive waste and for the recovery thereof, including waste oxidation, separating sludge, colloids and suspended particles from a liquid phase, and removing, from the liquid phase, radionuclides to be subsequently recovered using selective sorbents and filters; the method is characterized in that, prior to the stage for separating sludge, colloids and suspended particles from the liquid phase of the radioactive waste, selective sorbents in the form of powders are added and mixed into the liquid waste.

A nuclear reactor core comprising fissile material is surrounded by a core former. The core former comprises one or more single-piece annular rings wherein each single-piece annular ring comprises neutron-reflecting material. In some embodiments the core former comprises a stack of two or more such single-piece annular rings. In some embodiments the stack of single-piece annular rings is self-supporting. In some embodiments the stack of single-piece annular rings does not include welds or fasteners securing adjacent single-piece annular rings together. A core basket may contain the nuclear reactor core and the core former, and in some embodiments an annular gap is defined between the core former and the core basket. In some embodiments the core former does not include welds and does not include fasteners.

A nuclear reactor core comprising fissile material is surrounded by a core former. The core former comprises one or more single-piece annular rings wherein each single-piece annular ring comprises neutron-reflecting material. In some embodiments the core former comprises a stack of two or more such single-piece annular rings. In some embodiments the stack of single-piece annular rings is self-supporting. In some embodiments the stack of single-piece annular rings does not include welds or fasteners securing adjacent single-piece annular rings together. A core basket may contain the nuclear reactor core and the core former, and in some embodiments an annular gap is defined between the core former and the core basket. In some embodiments the core former does not include welds and does not include fasteners.

The present disclosure, in an embodiment, is a facility that includes a device configured to generate a beam having an energy range of 5 MeV to 500 MeV, a first radiation shielding wall surrounding the device, a second radiation shielding wall surrounding the first radiation shielding wall, radiation shielding fill material positioned between the first radiation shielding wall and the second radiation shielding wall forming a first barrier. In embodiments, the radiation shielding fill material includes at least fifty percent by weight of an element having an atomic number from 12 to 83, and a thickness of the first barrier is 0.5 meter to 6 meters.

Conventional shielding materials are based on single material either toxic lead or barium based compounds and any matrix made therefrom contains only single phased barium based compounds, thereby posing limited radiation shielding capacity. Since brine sludge, an industrial toxic waste product, generated in chloralkali industry contains multiple compounds; there is a need to provide a process which enables the preparation of multi-phase based radiation shielding materials. In view of the above, the present invention provides advanced non-toxic radiation shielding materials utilizing tailored brine sludge and a process that enables conversion of toxic elements like chromium, zinc, copper and vanadium present in brine sludge into non-toxic shielding phases, thereby enabling to convert a toxic waste material into highly value added advanced radiation shielding materials possessing homogeneous radiation shielding matrix.

The present invention relates to radiation shielding. In order to provide an improved mobile shielding solution, an interconnectable modular radiation-shielding unit (10) is provided for building a radiation-shielding wall. The interconnectable modular radiation-shielding unit comprises a housing and at least one port. The housing at least partially forms a chamber therein that is configmed to hold an X-ray shielding fluid composition. The at least one port leads through the housing into the chamber and being configmed to receive the X-ray shielding fluid composition. The housing comprises a detachably connectable portion that is configmed to be mechanically connected to a detachably connectable portion of a further interconnectable modular radiation-shielding unit to build the radiation shielding wall.

The present invention relates to radiation shielding. In order to provide an improved mobile shielding solution, an interconnectable modular radiation-shielding unit (10) is provided for building a radiation-shielding wall. The interconnectable modular radiation-shielding unit comprises a housing and at least one port. The housing at least partially forms a chamber therein that is configmed to hold an X-ray shielding fluid composition. The at least one port leads through the housing into the chamber and being configmed to receive the X-ray shielding fluid composition. The housing comprises a detachably connectable portion that is configmed to be mechanically connected to a detachably connectable portion of a further interconnectable modular radiation-shielding unit to build the radiation shielding wall.