A chargeable atomic battery (CAB) and a standardized pre-irradiation encapsulation manufacturing method. A CAB unit is manufactured through a non-radioactive process and then placed in a radiation field (typically a fission reactor) to convert a portion of a non-radioactive precursor material into an activated material (e.g., radioisotope) for charging. After charging, the CAB unit is ready for use and can be combined with additional CAB units into a CAB stack to achieve the desired activity and then integrated into a CAB pack or a product that uses the radioactivity for the desired application such as heating, electricity, and passive x-ray sources. The pre-irradiation encapsulation manufacturing method uses a die press and sintering process to produce the CAB unit with the precursor material fully encapsulated by the encapsulation material. During and after the charging process, the encapsulation material serves as a barrier, preventing release of the activated material release.

A chargeable atomic battery (CAB) and a standardized pre-irradiation encapsulation manufacturing method. A CAB unit is manufactured through a non-radioactive process and then placed in a radiation field (typically a fission reactor) to convert a portion of a non-radioactive precursor material into an activated material (e.g., radioisotope) for charging. After charging, the CAB unit is ready for use and can be combined with additional CAB units into a CAB stack to achieve the desired activity and then integrated into a CAB pack or a product that uses the radioactivity for the desired application such as heating, electricity, and passive x-ray sources. The pre-irradiation encapsulation manufacturing method uses a die press and sintering process to produce the CAB unit with the precursor material fully encapsulated by the encapsulation material. During and after the charging process, the encapsulation material serves as a barrier, preventing release of the activated material release.

The present disclosure relates to a device (1) for sampling and/or injection of a radioactive solution (S) in a vial (2), wherein the vial (2) comprises an opening closed by a puncturable closure member (3). The device (1) comprises a container (7) adapted to receive said vial (2) and a vial adaptor (4), said vial adaptor (4) having a longitudinal axis (L1), provided at a first end (41) with a hollow spike (42) adapted to pierce said puncturable closure member (3) when the vial adaptor (4) is mounted on the vial (2), and at a second end (43) with connection means (5) adapted for its removable connection to a syringe (6), the container (7) comprising: a container body (71) adapted to receive said vial (2), the container body (71) having an opening (711), and a vial adaptor support structure (72) configured for being mounted onto the opening (711) of the container body (71), and comprising retention means configured for enabling releasable retention of said vial adaptor (4) within said vial adaptor support structure (72), and wherein the vial adaptor support structure (72) and the container body (71) are made at least partially of a radioprotective material for providing protection against ionizing radiation.

The invention relates generally to nuclear engineering and more particularly to controlled reactor start-up. The invention improves reliability of an operational neutron source by creating additional safety barriers between the coolant and the source active part materials. The operational neutron source is designed as a steel enclosure housing an ampule containing antimony and beryllium with separate antimony and beryllium cavities positioned coaxially. The antimony is contained in the central enclosure made of a niobium-based alloy unreactive with antimony. A beryllium powder bed is located between the antimony enclosure and the ampule enclosure. The ampule enclosure is made of martensite-ferrite steel poorly reacting with beryllium. An upper gas collector is located above the ampule, which serves as a compensation volume collecting gaseous fission products. At the bottom, the ampule is supported by a reflector and a bottom gas collector. The gas collectors, reflector and washers are made of martensite-ferrite grade steel.

Radiation monitoring devices and associated methods are described. According to one aspect, a radiation monitoring device includes a housing configured to pass radiation emitted from a radiological source located in proximity to the radiation monitoring device, a radiation detector configured to receive the radiation emitted from the radiological source and to generate information regarding the radiation, and communications circuitry configured to communicate the information regarding the radiation in a plurality of communications at a plurality of different moments in time externally of the radiation monitoring device

A device for transferring a toxic substance from a dispensing vessel to at least one receiving vessel comprising: (i) a receiving portion arranged to receive a dispensing vessel containing a toxic substance; and (ii) a transfer apparatus having a first infusion line adapted for fluid communication with the dispensing vessel to transfer a carrier fluid into said vessel and a second infusion line having one end adapted for fluid communication to withdraw and transfer the carrier fluid and the toxic substance from the dispensing vessel and the other end of the second infusion line arranged to connect with the at least one receiving vessel.

A device for transferring a toxic substance from a dispensing vessel to at least one receiving vessel comprising: (i) a receiving portion arranged to receive a dispensing vessel containing a toxic substance; and (ii) a transfer apparatus having a first infusion line adapted for fluid communication with the dispensing vessel to transfer a carrier fluid into said vessel and a second infusion line having one end adapted for fluid communication to withdraw and transfer the carrier fluid and the toxic substance from the dispensing vessel and the other end of the second infusion line arranged to connect with the at least one receiving vessel.

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 nuclear fuel storage system includes an outer canister and fuel basket positioned therein. The basket is formed by orthogonally arranged and interlocked slotted plates which collectively define exterior side surfaces of the basket and a grid array of open cells each configured to hold a fuel assembly. At least some slotted plates comprise cantilevered plate extensions protruding laterally beyond the side surfaces of the basket to define various shaped peripheral gaps between the basket and canister. The plate extensions are configured to engage the shell of the canister. Vertically elongated reinforcement members are inserted in the peripheral gaps and fixedly coupled to the basket. Reinforcement members may comprise elongated reinforcement plates and/or tubular shimming members which may be fixedly coupled to the slotted plate extensions. The reinforcement members structurally strengthen the fuel basket. The plate extensions further act as fins to enhance heat dissipation from the basket.

A nuclear fuel storage system includes an outer canister and fuel basket positioned therein. The basket is formed by orthogonally arranged and interlocked slotted plates which collectively define exterior side surfaces of the basket and a grid array of open cells each configured to hold a fuel assembly. At least some slotted plates comprise cantilevered plate extensions protruding laterally beyond the side surfaces of the basket to define various shaped peripheral gaps between the basket and canister. The plate extensions are configured to engage the shell of the canister. Vertically elongated reinforcement members are inserted in the peripheral gaps and fixedly coupled to the basket. Reinforcement members may comprise elongated reinforcement plates and/or tubular shimming members which may be fixedly coupled to the slotted plate extensions. The reinforcement members structurally strengthen the fuel basket. The plate extensions further act as fins to enhance heat dissipation from the basket.