Patent classifications
G21F5/06
XRF analyzer
A portable XRF analyzer includes a hand shield to substantially block x-rays from impinging on a hand of a user. The portable XRF analyzer includes a heat sink over an x-ray source and a heat sink over an x-ray detector. The heat sinks are separated from each other by a thermally insulative material.
XRF analyzer
A portable XRF analyzer includes a hand shield to substantially block x-rays from impinging on a hand of a user. The portable XRF analyzer includes a heat sink over an x-ray source and a heat sink over an x-ray detector. The heat sinks are separated from each other by a thermally insulative material.
Handling and confinement hood, application to handling holders of samples of nuclear materials such as nuclear fuels
The present invention concerns a hood for handling and confinement of at least two objects of slender shape, including an external enclosure and internal enclosures inside the external enclosure and at least one motor fixed above an internal enclosure and inside a barrel, the motor(s) being adapted to rotate the screw of the screw-nut mechanism of each internal enclosure and therefore the nut over a stroke A, and first and second mechanical control means, arranged in part above the cover of the external enclosure, respectively for manually guiding the internal enclosures in translation over a stroke A0 and manually pivoting the barrel in order to bring a holding member of one of the internal enclosures opposite the opening in the bottom of the external enclosure. Application to the handling and confinement of nuclear material sample holders.
Systems and methods for canister inspection, preparation, and maintenance
A travel system (20) for a canister storage, transfer, or transport system generally includes a support structure (22), at least one traveling device (24) for preparing, inspecting, and/or repairing the canister, and a base ring (26) for supporting the traveling device and providing for rotational movement of the traveling device relative to the support structure.
System for low profile translation of high level radioactive waste
An apparatus, system and method for handling and translating high level radioactive waste. The apparatus comprises a body for supporting the cask close to the ground so that the cask and the apparatus can pass underneath over head doors. The apparatus further comprises rollers for translating the cask. The apparatus additionally supports the storage cask during spent nuclear fuel transfer procedures.
USING ADDITIVE MANUFACTURING TO PRODUCE SHIELDING OR MODULATING MATERIAL FOR NUCLEAR DETECTORS
An apparatus for a nuclear detector of a downhole tool and method of manufacturing the apparatus is disclosed. The apparatus includes a single multi-metallic component manufactured using additive manufacturing, wherein the component includes at least a first material having a first density and a second material having a second density. The method includes using additive manufacturing to form the component so that the component includes at least a first material having a first density and a second material having a second density and the first material and the second material form the single multi-metallic component.
Drying spent nuclear fuel based on evaluation of drying characteristics obtained using gas spectroscopy
Apparatus and method for drying spent nuclear fuel loaded in a cavity of a canister. A non-reactive gas discharged from the canister is selectively circulated through one of a contaminated circulation system and a non-contaminated circulation system according to a measured radiation dose rate.
Drying spent nuclear fuel based on evaluation of drying characteristics obtained using gas spectroscopy
Apparatus and method for drying spent nuclear fuel loaded in a cavity of a canister. A non-reactive gas discharged from the canister is selectively circulated through one of a contaminated circulation system and a non-contaminated circulation system according to a measured radiation dose rate.
METHOD FOR PREVENTING CORROSION OF SPENT NUCLEAR FUEL CANISTER BY USING ELECTROLYTIC CORROSION PROTECTION
A method for preventing corrosion of a spent nuclear fuel canister by using electrolytic corrosion protection, according to the present invention, has an effect of enabling a semi-permanent operation and, particularly, has effects of preventing oxidation and corrosion problems of a canister made of a metal material, in consideration of various environmental variables that may cause corrosion, and ensuring the structural stability of the canister so as to enable a semi-permanent operation.
Integrated ion-exchange disposal and treatment system
A canister for interim storage and subsequent consolidation of waste materials via hot pressing and comprising at least one ion exchange material. The canister is configured to house the ion exchange material after it is exchanged with a contaminating ion without releasing the contaminating ion and to consolidate waste materials via hot-isostatic pressing. A method comprising contacting a fluid waste with an ion exchange material.