A method and apparatus for separation of radioactive particulates from liquids by filtration to remove or recover the particulates, that reduces the surfaces forces associated with electrostatic attraction between the particles and the filter medium by modifying or coating the surface of the filter medium with a material that exhibits a surface charge closer to or the same as that of the particulates in a given aqueous liquid. The method and apparatus can be used to filter radioactive particulates and contaminants from aqueous liquid or liquid process streams with a radiation resistant filter medium. The filters can exhibit a surface charge different from that of the particulates targeted for separation by mechanical filtration. The filtration medium can be modified to increase its resistance to erosion to permit use of more powerful backwashing regeneration methods and prevent attachment of the particulates to the filtration medium by coating the medium with a hydrophobic layer.
An apparatus to test for defects in irradiated nuclear fuel includes a submerged sipping canister, a first recirculation system and a degassing device to remove and discharge pre-existing dissolved fission product gases from the fluid in the system and canister prior to a sipping test, a second recirculation system and a degassing device to extract and detect fission products from the fluid in the canister during the sipping test, a flow control valve to maintain a partial vacuum in the canister when the second recirculation system is operating, and a radiation detector monitoring the output gas from the degassing device. The fluid-contacting surfaces of selected components may be pretreated or modified to reduce adsorption or adherence of radioactive noble gases on wetted surfaces to decrease background radiation levels and contamination of the apparatus. A related method is also disclosed.
G21C 19/32 - Apparatus for removing radioactive objects or materials from the reactor discharge area, e.g. to a storage placeApparatus for handling radioactive objects or materials within a storage place or removing them therefrom
3.
METHOD AND APPARATUS TO TEST FOR DEFECTS IN IRRADIATED NUCLEAR FUEL
An apparatus to test for defects in irradiated nuclear fuel includes a submerged sipping canister, a first recirculation system and a degassing device to remove and discharge pre-existing dissolved fission product gases from the fluid in the system and canister prior to a sipping test, a second recirculation system and a degassing device to extract and detect fission products from the fluid in the canister during the sipping test, a flow control valve to maintain a partial vacuum in the canister when the second recirculation system is operating, and a radiation detector monitoring the output gas from the degassing device. The fluid-contacting surfaces of selected components may be pretreated or modified to reduce adsorption or adherence of radioactive noble gases on wetted surfaces to decrease background radiation levels and contamination of the apparatus. A related method is also disclosed.
C23C 18/08 - Chemical coating by decomposition of either liquid compounds or solutions of the coating forming compounds, without leaving reaction products of surface material in the coatingContact plating by thermal decomposition characterised by the deposition of metallic material
C23C 18/12 - Chemical coating by decomposition of either liquid compounds or solutions of the coating forming compounds, without leaving reaction products of surface material in the coatingContact plating by thermal decomposition characterised by the deposition of inorganic material other than metallic material
C23C 18/16 - Chemical coating by decomposition of either liquid compounds or solutions of the coating forming compounds, without leaving reaction products of surface material in the coatingContact plating by reduction or substitution, i.e. electroless plating
G21C 17/022 - Devices or arrangements for monitoring coolant or moderator for monitoring liquid coolants or moderators
A method for depositing divalent metal compounds on the surface of a nuclear power plant component, the component being a nickel-based or austenitic stainless steel alloy includes: providing within the component an aqueous treatment solution containing at least one soluble metal-containing compound such as a zinc salt and at least one source of oxygen; allowing the treatment solution to remain in the component until the compound is deposited on the wetted surface of the component; and, removing the aqueous solution after exposure. The treatment may be applied more than once, using more than one divalent metal compound, and the surface may further be exposed to a solution containing a noble metal species and a reducing agent. The treatment temperature is preferably below 100°C.
G21C 17/022 - Devices or arrangements for monitoring coolant or moderator for monitoring liquid coolants or moderators
C23C 18/12 - Chemical coating by decomposition of either liquid compounds or solutions of the coating forming compounds, without leaving reaction products of surface material in the coatingContact plating by thermal decomposition characterised by the deposition of inorganic material other than metallic material
C23C 18/16 - Chemical coating by decomposition of either liquid compounds or solutions of the coating forming compounds, without leaving reaction products of surface material in the coatingContact plating by reduction or substitution, i.e. electroless plating
C23C 18/08 - Chemical coating by decomposition of either liquid compounds or solutions of the coating forming compounds, without leaving reaction products of surface material in the coatingContact plating by thermal decomposition characterised by the deposition of metallic material
A method for depositing divalent metal compounds on the surface of a nuclear power plant component, the component being a nickel-based or austenitic stainless steel alloy includes: providing within the component an aqueous treatment solution containing at least one soluble metal-containing compound such as a zinc salt and at least one source of oxygen; allowing the treatment solution to remain in the component until the compound is deposited on the wetted surface of the component; and, removing the aqueous solution after exposure. The treatment may be applied more than once, using more than one divalent metal compound, and the surface may further be exposed to a solution containing a noble metal species and a reducing agent. The treatment temperature is preferably below 100° C.
G21C 21/00 - Apparatus or processes specially adapted to the manufacture of reactors or parts thereof
C23C 18/16 - Chemical coating by decomposition of either liquid compounds or solutions of the coating forming compounds, without leaving reaction products of surface material in the coatingContact plating by reduction or substitution, i.e. electroless plating
C23C 18/18 - Pretreatment of the material to be coated
7.
Method and apparatus for improved removal and retention of radioactive particulates from fluids
A method and apparatus for improved separation and containment of radioactive particulates from liquids by filtration. The improvements are achieved by utilizing more than one stage of filtration to remove radioactive particulates from a fluid. The first stage of filtration is designed for high liquid flowrate, low differential pressure across the filter medium, and reversibility of flow through the medium to facilitate backwashing. The second or more stages of filtration receive the backwash flow and captured particulates from the first stage at a lower flowrate, but at high pressure using a high-pressure pump configured between the stages.
G21C 19/307 - Arrangements for introducing fluent material into the reactor coreArrangements for removing fluent material from the reactor core with continuous purification of circulating fluent material, e.g. by extraction of fission products specially adapted for liquids
G21F 9/12 - Processing by absorptionProcessing by adsorptionProcessing by ion-exchange
8.
Method and apparatus for enhanced separation and removal of contaminants and irradiated particulates from fluids
A method and apparatus for separation of radioactive particulates from liquids by filtration to remove or recover the particulates, that reduces the surfaces forces associated with electrostatic attraction between the particles and the filter medium by modifying or coating the surface of the filter medium with a material that exhibits a surface charge closer to or the same as that of the particulates in a given aqueous liquid. The method and apparatus can be used to filter radioactive particulates and contaminants from aqueous liquid or liquid process streams with a radiation resistant filter medium. The filters can exhibit a surface charge different from that of the particulates targeted for separation by mechanical filtration. The filtration medium can be modified to increase its resistance to erosion to permit use of more powerful backwashing regeneration methods and prevent attachment of the particulates to the filtration medium by coating the medium with a hydrophobic layer.
A method and apparatus for improved separation and containment of radioactive particulates from liquids by filtration. The improvements are achieved by utilizing more than one stage of filtration to remove radioactive particulates from a fluid. The first stage of filtration is designed for high liquid flowrate, low differential pressure across the filter medium, and reversibility of flow through the medium to facilitate backwashing. The second or more stages of filtration receive the backwash flow and captured particulates from the first stage at a lower flowrate, but at high pressure using a high-pressure pump configured between the stages.
A method and apparatus for improved separation and containment of radioactive particulates from liquids by filtration. The improvements are achieved by utilizing more than one stage of filtration to remove radioactive particulates from a fluid. The first stage of filtration is designed for high liquid flowrate, low differential pressure across the filter medium, and reversibility of flow through the medium to facilitate backwashing. The second or more stages of filtration receive the backwash flow and captured particulates from the first stage at a lower flowrate, but at high pressure using a high-pressure pump configured between the stages.
A method and apparatus for separation of particulates from liquids by filtration for the purpose of removal or recovery of the particulates. Reducing the surfaces forces associated with electrostatic attraction between the particles and the filter medium is accomplished by modifying or coating the surface of the filter medium with one or more materials that exhibit a surface charge closer to or the same as that of the particulates in a given aqueous liquid. This permits filtration by mechanical interception but reduces the subsequent adhesion that prevents or hinders regeneration. The method and apparatus can be used in the filtration of radioactive particulates and contaminants from aqueous liquid inventories or liquid process streams with radiation resistant filter medium such as ceramics, sintered metal powders, or sintered metal fibers. These types of filters can exhibit a surface charge very different from that of the particulates targeted for separation by mechanical filtration.
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