13 results about "Nuclear waste storage" patented technology

The invention provides a real-time monitoring method and device for nuclear waste treatment, and relates to the technical field of nuclear power plant production management, and the method comprises the steps: employing a temperature and stress sensing array which is packaged in a radiation shielding sleeve and is integrated in a radiation-resistant sealing module and is based on a fiber Bragg grating; detecting and recording optical signals of tiny deformation, temperature change and mechanical strain of the nuclear waste storage container; converting the optical signal into a denoised electric signal by using a photoelectric converter and a band-pass filter in the sealing module; after the electric signals are integrated through a multiplexer, the electric signals are transmitted and analyzed through an underground optical fiber link and a dual-redundancy high-speed data switch, and graded early warning is carried out according to analyzed tiny deformation, temperature changes and mechanical dependent variables. Therefore, the service life of the temperature and stress sensing array in a high-radiation environment is prolonged, the accuracy of data acquisition is improved, the anti-interference capability of data transmission is improved, real-time graded early warning is realized, and the safety and controllability in the nuclear waste treatment process are improved.

A nuclear waste heat generating system (10) comprises nuclear waste storage site (12) containing one or more storage containers (14) comprising radioactive nuclear waste. The heat pump system (16) comprises a closed working fluid circuit (26) filled with a working fluid, the working fluid circuit including an inflow pipe (22) for supplying the working fluid from a heat sink (18) of the heat pump system (16) to a heat exchanger (20) of the heat pump system (16), and an outflow pipe (24) for returning heated working fluid from the heat exchanger (20) to the heat sink (18). The heat exchanger (20) is thermally coupled to the nuclear waste storage site (12) such that the heat exchanger (20) is heated by decay heat produced by the one or more storage containers (14). Further, a use of one or more storage containers comprising radioactive nuclear waste as a heat source is described.

This utility model discloses a welding fixture for manufacturing the wellhead of a nuclear waste storage well. It includes a base plate with mounting screws at its top. The connecting structure includes a first cylinder, a second cylinder, and a third cylinder, each with a first flange mounted on its outer side. A second fixing screw passes through the top of the second flange. This utility model uses a second flange mounted at the bottom of the first flange, with the first and second flanges engaging to sequentially assemble the cylinder and flange parts onto the fixture. Utilizing the positioning and limiting features on the fixture, and the stop on the flange's inner diameter, the spacing and parallelism of the flanges, the roundness of the cylinder, the coaxiality between cylinders, and the perpendicularity to surface A can be ensured. After assembly, the fixture is removed, and each weld is performed. The welds are then ground to meet non-destructive testing requirements, and the inner surface welds are ground smooth. This achieves the goal of facilitating stable assembly of the welding fixture for manufacturing the nuclear waste storage well head.

The invention relates to the technical field of cesium adsorption resin materials, and discloses an adsorption resin for treating cesium-containing waste liquid and a preparation method thereof, and the preparation method specifically comprises the following steps: 1, generating a polymer: dissolving resorcinol, formaldehyde and sodium bicarbonate in deionized water, heating, reducing pressure, slowly evaporating water, and forming the polymer after a period of time; 2, cooling the solid product overnight, washing with hydrochloric acid, soaking with water, and drying; and 3, crushing the polymer, repeatedly washing, and drying to finally obtain the adsorption resin. In the step 1, the mass of the resorcinol is 320-350 g, the formaldehyde is a 37% aqueous solution, the volume of the formaldehyde is 250-280 mL, the mass of the sodium bicarbonate is 200-205 g, and the volume of the deionized water is 4-5 L. The cesium adsorption resin prepared by the invention has the advantages of high selectivity, good adsorption effect, high mechanical strength and simple preparation method, and can be suitable for treating radioactive waste liquid with complex components and harsh conditions, such as nuclear waste storage tank supernatant.

A nuclear waste canister includes a bottom housing portion; a top housing portion; and a side housing portion attached to the bottom and top housing portions to define an inner volume sized to enclose nuclear waste and configured to store the nuclear waste in a hazardous waste repository of a human-unoccupiable directional drillhole formed in a subterranean formation. The canister includes a post attached to the top housing portion and an outer lip that extends from the top housing portion and is angled toward an axial centerline of the side housing portion.

This utility model relates to the field of wellbore inspection tooling technology, and provides a precision inspection tooling for nuclear waste storage well manufacturing. It includes a base, a guide plate fixedly connected to the outer wall of the base, and a lifting mechanism fixedly connected to the outer wall of the base. The lifting mechanism includes a hydraulic rod fixedly installed on the top of the base, a movable plate fixedly connected to the output end of the hydraulic rod, a guide groove and a sliding groove inside the movable plate, and an L-shaped support rod movably connected inside the movable plate. A testing platform is fixedly connected to the top of the L-shaped support rod. This utility model, by activating the hydraulic rod, moves the movable plate, causing the L-shaped support rod to slide along the sliding groove, thus raising and lowering the testing platform fixedly connected to the top of the L-shaped support rod. This facilitates the adjustment of the wellbore height according to inspection requirements. The cooperation of the guide plate and the guide groove further enhances the stability of the testing platform's lifting and lowering.

This utility model relates to the field of nuclear waste storage well technology, and provides a manufacturing and welding fixture for a nuclear waste storage well shielding plug. The fixture includes a base, a first well opening at the top of the base, a second well opening above the first well opening, and a third well opening above the second well opening. A positioning structure is fixed to the top of the base inside the first well opening. This utility model incorporates an adjustment structure, allowing a first pressure ring and a second pressure ring to move outwards from the stud. Under the action of a first fixing nut and a second fixing nut, the first and second pressure rings can be fixed or disassembled with the stud. The action of a first flat washer and a second flat washer prevents loosening, thus enabling the assembly of storage wells of different lengths. This device facilitates height adjustment, thereby improving the applicability of the nuclear waste storage well shielding plug manufacturing and welding fixture in use.

The application discloses a boron-containing stainless steel with high shielding performance and a preparation method thereof, relates to the field of fusion reactor irradiation shielding materials, and can also be applied to other fields requiring shielding of neutrons and gamma rays, such as fission reactors, nuclear power devices, nuclear waste storage racks and the like. The boron steel contains the following components in percentage by weight: Cr 7.5-25%, Ni 8.5-18.5%, Mn 0.5-4.3%, B 1.8-4.5%, C 0.02%-0.06%, and the balance is Fe and inevitable impurities. The components of the alloy are proportioned according to the application, atomized, mixed, sintered and machined, and finally, a block boron steel with high boron content, high density, uniform boride distribution and good shielding performance is obtained. The high-performance boron steel shielding material improves the shielding efficiency of thermal neutrons, and provides support for the development of DEMO reactors, compact fusion reactors and other shielding fields.

The invention discloses a welding tool for assembly based on a nuclear waste storage well, and relates to the technical field of welding, the welding tool comprises a supporting mechanism, the supporting mechanism is used for positioning and fixing a shaft section to be welded, and an assembly mechanism is arranged on the outer surface of the supporting mechanism; the assembling mechanism participates in the welding thermal process and is used for regulating and controlling dynamic integration and thermal-mechanical coupling response of the restraining state in the welding process. In the assembling stage, the two parent parts apply axial pressure to the middle oblique cutting structure extrusion sheet, geometric units of the oblique cutting structure extrusion sheet are promoted to be mutually nested and distributed compactly, a high-rigidity flexible supporting layer with the energy absorption characteristic is formed to absorb and homogenize local stress, meanwhile, the concave ring and the convex ring which are meshed with each other provide circumferential initial positioning and mechanical locking, and the mechanical locking effect is improved. And the wire sealing rings in the wire grooves are used for circumferential fixation, so that the welding residual tensile stress is reduced, and the initial assembly precision and the structural stability of the joint are improved.

The invention relates to the technical field of radioactive nuclear waste storage, and discloses an intelligent nuclear waste liquid storage container. The container comprises a barrel, and the barrel comprises a polyethylene inner container layer and a composite outer layer. The composite outer layer comprises a polyurethane buffer layer, a fiber reinforced layer and an elastic surface layer which are connected in sequence; the polyurethane buffer layer is connected with the polyethylene liner layer; and a fiber bragg grating sensor is embedded or paved inside or on the outer surface of the fiber reinforced layer. According to the intelligent nuclear waste liquid storage container, the composite outer layer is additionally arranged on the basis of a traditional polyethylene cylinder, and the mechanical strength, the irradiation resistance and the shielding performance of the container are improved; and a fiber bragg grating sensor is embedded in the fiber reinforced layer or on the outer surface of the fiber reinforced layer, so that intelligent real-time monitoring on the working state strain of the waste container is realized.

This invention discloses a robot and method for grinding the walls of nuclear waste storage wells, belonging to the field of nuclear waste treatment technology. The device includes a three-axis truss mechanism and a grinding mechanism, connected by an adjustment mechanism. An electrical cabinet and a dust removal mechanism are installed on the three-axis truss mechanism. The method includes: 1. Preparatory work before grinding; 2. Determining the four walls of the nuclear waste storage well to be ground and installing the grinding robot; 3. Grinding the four walls of the nuclear waste storage well; 4. Determining the bottom surface of the nuclear waste storage well to be ground and installing the grinding robot; 5. Grinding the bottom surface of the nuclear waste storage well; 6. Removing the grinding robot. This invention replaces manual grinding operations in the well with an automated mechanism. Operators can remotely control the machine from outside the wellhead, completely avoiding the safety risks of falls, dust inhalation, and collisions associated with manual work in the confined space of deep wells, thus ensuring the occupational health and personal safety of construction workers.

This utility model relates to the field of well casing manufacturing technology, and provides a welding fixture for manufacturing nuclear waste storage well casings. The fixture includes a well casing body, on which an internal support structure is uniformly arranged. The internal support structure includes wedge-shaped blocks, an internal support plate, and connecting grooves. The wedge-shaped blocks are uniformly arranged on the inner wall of the well casing body, and connecting grooves are formed on the side of each wedge-shaped block away from the well casing body. By providing the internal support structure, the uniformly distributed wedge-shaped blocks closely contact the inner wall of the well casing body, ensuring that the well casing body maintains a standard circular shape during welding and avoiding roundness deviations. The interlocking connection between the internal support plate and the connecting grooves forms a rigid support, reducing vibration or deformation during welding and improving structural stability. The symmetrical distribution of the wedge-shaped blocks on both sides of the internal support plate facilitates quick installation and disassembly. This device enables the device to support the welding shape of the well casing body, improving the working efficiency of the welding fixture for manufacturing nuclear waste storage well casings during use.

A dry storage systems for radioactive nuclear waste materials may include a double-walled canister system. The canister system may include a canister having a tubular inner shell defining an internal cavity for storing nuclear waste material, a first lid sealably welded to a first end of the inner shell, a primary base plate defining a peripheral edge portion and having an annular closure flange, and an annular full thickness butt weld formed at an abutment joint between the annular closure flange and a second end of the inner shell. The inner shell, first lid, and first end closure may collectively define a sealed primary pressure retention barrier. A tubular outer shell may adjoin the inner shell. The outer shell may be welded to the canister to form a hermetically sealed secondary pressure retention barrier.