Patent classifications
G21C3/334
MODULAR WATER PURIFICATION SYSTEM FOR NUCLEAR POWER PLANTS
A modular water purification system for a nuclear power plant includes a plurality of modules that may be selectively connected together directly or through the use of intermediary adapters in a plurality of arrangements. The modules may include a pump module, a FOSAR module, a particulate filtration module, a cross-flow filtration module, a degasification module, and/or a demineralization module, among other possible modules. The modules may have common interfaces so that they can be interconnected (directly or through intermediary adapters) in a variety of configurations for different purposes within the context of the nuclear power plant (e.g., filtering pool water; collecting large objects via vacuuming). Various modules may have form factors and/or mounting structures that are similar enough to the fuel assemblies of the plant that (1) the plant's fuel assembly handling equipment can grab, move, and reposition the modules, and/or (2) the modules may be stored in the fuel pool's storage rack.
MODULAR WATER PURIFICATION SYSTEM FOR NUCLEAR POWER PLANTS
A modular water purification system for a nuclear power plant includes a plurality of modules that may be selectively connected together directly or through the use of intermediary adapters in a plurality of arrangements. The modules may include a pump module, a FOSAR module, a particulate filtration module, a cross-flow filtration module, a degasification module, and/or a demineralization module, among other possible modules. The modules may have common interfaces so that they can be interconnected (directly or through intermediary adapters) in a variety of configurations for different purposes within the context of the nuclear power plant (e.g., filtering pool water; collecting large objects via vacuuming). Various modules may have form factors and/or mounting structures that are similar enough to the fuel assemblies of the plant that (1) the plant's fuel assembly handling equipment can grab, move, and reposition the modules, and/or (2) the modules may be stored in the fuel pool's storage rack.
NUCLEAR FUEL ASSEMBLY MANUFACTURING METHOD, NUCLEAR FUEL ASSEMBLY MANUFACTURING PLANT AND METHOD OF EXPANDING SUCH A PLANT
A method is for manufacturing a nuclear fuel assembly (2) comprising nuclear fuel rods (4) arranged in a bundle and a skeleton (6) supporting the fuel rods (4). The method comprise the steps of inserting fuel rods (4) into the skeleton (6) to obtain a fuel assembly (2) and packaging the fuel assembly (2) in view of transportation. The steps are being performed in a same nuclear fuel assembly manufacturing plant (20), preferably in a same nuclear fuel assembly manufacturing building (60).
NUCLEAR FUEL ASSEMBLY MANUFACTURING METHOD, NUCLEAR FUEL ASSEMBLY MANUFACTURING PLANT AND METHOD OF EXPANDING SUCH A PLANT
A method is for manufacturing a nuclear fuel assembly (2) comprising nuclear fuel rods (4) arranged in a bundle and a skeleton (6) supporting the fuel rods (4). The method comprise the steps of inserting fuel rods (4) into the skeleton (6) to obtain a fuel assembly (2) and packaging the fuel assembly (2) in view of transportation. The steps are being performed in a same nuclear fuel assembly manufacturing plant (20), preferably in a same nuclear fuel assembly manufacturing building (60).
Modular basket assembly for fuel assemblies
A basket assembly for receiving a plurality of fuel assemblies includes a basket having a grid defining spacing between fuel assembly compartments, the grid defining a first compartment for receiving a first fuel assembly and a second compartment for receiving a second fuel assembly, wherein the cross-sectional area of the second compartment is larger than the cross-sectional area of the first compartment. The basket assembly is configured to receive in the first compartment a first fuel assembly, the first fuel assembly being a regular fuel assembly, and the basket assembly configured to receive in the second compartment a second fuel assembly, the second fuel assembly being an irregular fuel assembly, wherein the irregular fuel assembly includes at least one irregular fuel rod.
NUCLEAR FUEL ROD END DISTANCE ADJUSTING DEVICE
Provided is the nuclear fuel rod end distance adjusting device, the device allowing an adjustment of a nuclear fuel rod end distance to be stably and efficiently accomplished and including: an insertion rod including nuclear fuel rod tongs and linearly moving forward and backward; a housing having a hollow space; insertion power means installed inside the housing, and moving in a longitudinal direction of the housing by converting a rotational motion into a linear motion; a connector connected between the insertion power means and an insertion rod; and an anti-rotation tool installed between the insertion power means and the connector, being capable of moving in the longitudinal direction of the housing by being interlocked with the linear motion of the insertion power means, but preventing rotational force of the insertion power means from being transmitted to the connector.
APPARATUS FOR FATIGUE TESTING BULGE TOOL HAVING WH-TYPE SKELETON
Provided is an apparatus for fatigue testing a bulge tool having a WH-type skeleton, the apparatus including: a fixing bracket having tool holes penetrated through opposite sides thereof; a tool housing coupled to the tool hole of the fixing bracket and having the bulge tool inserted and installed therein; a moving rail installed at one side of the fixing bracket in a lengthwise direction of the tool housing and providing a reciprocating movement path facing the tool housing; a moving bracket reciprocating along the moving rail; a pusher protrudingly installed from the moving bracket toward the tool housing and moving in and out of the bulge tool; a measurement means installed between the pusher and the moving bracket, measuring a load applied to the bulge tool; and a drive means for generating power reciprocating the moving bracket on the moving rail.
APPARATUS FOR FATIGUE TESTING BULGE TOOL HAVING WH-TYPE SKELETON
Provided is an apparatus for fatigue testing a bulge tool having a WH-type skeleton, the apparatus including: a fixing bracket having tool holes penetrated through opposite sides thereof; a tool housing coupled to the tool hole of the fixing bracket and having the bulge tool inserted and installed therein; a moving rail installed at one side of the fixing bracket in a lengthwise direction of the tool housing and providing a reciprocating movement path facing the tool housing; a moving bracket reciprocating along the moving rail; a pusher protrudingly installed from the moving bracket toward the tool housing and moving in and out of the bulge tool; a measurement means installed between the pusher and the moving bracket, measuring a load applied to the bulge tool; and a drive means for generating power reciprocating the moving bracket on the moving rail.
Nuclear reactor fuel assembly manufacturing method
A method for manufacturing nuclear reactor fuel assembly. The method comprises applying a protective coating on fuel elements, wherein each fuel element is moved through a protective coating application device installed on an assembly stand. The protective coating comprises a water-soluble lubricant consisting of nonylphenol ethoxylate and monobasic unsaturated fatty acids. The method further comprises installing the coated fuel elements into grid cells of an assembly, wherein during the installing, each coated fuel element is moved on the assembly stand in a horizontal direction along its own axis into the grid cells. At least part of the steps of applying a protective coating and installing the coated fuel elements occur simultaneously. After installing the coating, top and bottom nozzles are attached to the assembly. After attaching the top and bottom nozzles, the fuel elements are washed to remove the protective coating from the fuel elements, which are subsequently dried.
Nuclear reactor fuel assembly manufacturing method
A method for manufacturing nuclear reactor fuel assembly. The method comprises applying a protective coating on fuel elements, wherein each fuel element is moved through a protective coating application device installed on an assembly stand. The protective coating comprises a water-soluble lubricant consisting of nonylphenol ethoxylate and monobasic unsaturated fatty acids. The method further comprises installing the coated fuel elements into grid cells of an assembly, wherein during the installing, each coated fuel element is moved on the assembly stand in a horizontal direction along its own axis into the grid cells. At least part of the steps of applying a protective coating and installing the coated fuel elements occur simultaneously. After installing the coating, top and bottom nozzles are attached to the assembly. After attaching the top and bottom nozzles, the fuel elements are washed to remove the protective coating from the fuel elements, which are subsequently dried.