Method for dry storage of spent fuel elements in containers and shipping unit for conveying spent fuel assemblies to intermediate storage site

FIELD: nuclear engineering.

SUBSTANCE: proposed method includes loading spent fuel assemblies in metal-concrete container, conveying the latter to intermediate storage site, and holding it on storage sire. Shipping unit for conveying spent fuel assemblies to intermediate storage site has flat-car for carrying vertically mounted container holding spent fuel assemblies. Container is provided with external removable circular supporting member engageable with mating supporting surface of flat-car frame and means for locking container relative to mentioned frame. Shipping unit is provided with jacks for lifting the frame to load spent fuel assemblies in container. Side surface of container body has rigging members in the form of seats on its top and bottom ends. Bottom end of container is installed inside mentioned circular supporting member. Container locking means include radially disposed submersible adjustable stops.

EFFECT: enhanced reliability and safety of proposed method and device.

4 cl, 8 dwg

 



 

Same patents:

FIELD: transport and storage of spent nuclear fuel.

SUBSTANCE: proposed method includes placement of fuel assemblies in transport package incorporating container and split damping casing designed so as to minimize lift of container when inserting it in split damping casing. Transport package is conveyed to storage place where container is freed of casing, whereupon spent fuel assemblies are kept in storage place. In the process spent fuel assemblies are first placed in container and then the latter is inserted in vertical position into split damping casing made in the form of removable drum with butt-end covering and base that functions as end lid of this drum. Charged container is installed on base, covered on top with removable drum, and the latter is fastened to base. Then split damping casing is secured to container, whereupon transport package is conveyed in transport position to storage place.

EFFECT: enhanced reliability of storage and transportation.

6 cl, 5 dwg

FIELD: nuclear engineering.

SUBSTANCE: proposed method includes bringing craft to nuclear-safe condition by removing fissionable materials therefrom. Radiation-hazardous compartment is inspected for radiation condition, cut out from craft, treated with solidifying compound, and sealed. In the process recovery is made on land. In addition, external components are dismounted from compartment hull. Dismounted radioactive components are cut in two parts and disposed inside compartment hull. Compartment is treated with solidifying compound by its external solidification with variable-thickness layer upon sealing and outside inspection of compartment for radiation condition, and γ-radiation level is measured in the course of inspection. Characteristics of immobilized pollutants of α- and β-radiating radionuclides are determined. Results obtained are mapped and these maps are used to detect radiation-hazardous zones to calculate local thickness of shielding barrier in each of these zones.

EFFECT: enhanced safety, reduced labor consumption and material input.

3 cl, 11 dwg

FIELD: long-term storage of radioactive wastes.

SUBSTANCE: spent nuclear fuel storage has vertical well with bridge in top part of well, containers with spent nuclear fuel boxes disposed in well, and well ventilating system. Containers are made in the form of cylinders with perforated sections in bottom part which are vertically installed on well face. Boxes holding spent nuclear fuel are disposed within container one on top of other. At least one empty container is placed in well and bridge is installed in top part of well below upper ends of containers.

EFFECT: enhanced reliability and long time of radioactive wastes isolation.

2 cl, 2 dwg

FIELD: methods of the radioactive waste disposal.

SUBSTANCE: the invention is pertaining to the field of the radioactive waste disposal. Substance of the invention: the method of the radioactive waste disposal includes boring of a borehole, placement of containers with the A-waste and leaving of a barrier pillar in the zone of the plastic deformations of the surrounding rocks, filling of the free volume of the borehole with an expanding plugging material and sealing of a the borehole head. At that the A-waste disposal is conducted in a clay bed, which is in a plastic state. The containers with the A-waste are placed in the middle part of the clay bed in its section with a length of l = m -2hδ, where "m" is the clay bed thickness, hδ is the thickness of argillaceous rocks. The plugging of the free volume of the borehole is conducted using the extracted from the borehole dried and crushed rock. At that on the section of placement of the containers the plugging is performed by substitution of the drilling mud, and on the section of the barrier pillar after an evacuation of the drilling mud - by portioned feed with water addition in the volume corresponding to the natural humidity. Advantages of the invention consist in an increased degree of reliability at the radioactive waste land disposal.

EFFECT: the invention ensures an increased degree of reliability at the radioactive waste land disposal.

5 dwg, 1 ex

FIELD: disposal of radioactive wastes.

SUBSTANCE: proposed method for building radioactive waste disposal structure involves formation of horizontal helical system of round-section transport and room tunnels penetrated by single mechanized tunneling machine including erection of grade-crossing elimination structures. Helical system of tunnels is made in the form of ellipse with variable distance between adjacent tunnels of helical system. Grade-crossing elimination structures are erected at two diametrically opposite points of system where each pair of tunnels is joined to form single tunnel communicating with adjacent coupled tunnel through crossover. Tunnel-to-tunnel distance is predetermined at several points by simulation including heat and radiation load on soil mass.

EFFECT: enhanced radiation safety and reduced construction charges.

1 cl, 2 dwg

FIELD: evacuation of radioactive wastes.

SUBSTANCE: proposed method for container-free subsurface burial of solid radioactive wastes in abandoned deep workings of cryolite zone involves delivery of solid radiation sources pre-cooled in winter to abandoned mine workings. Radiation sources are placed in layer-by-layer manner on prepared falsework paled floor, leveled, compacted, flooded with water, and frozen by natural cold before piling radioactive wastes to full height of subsurface workings. In the process, burial ground is shaped in the form of pillar. Split ice is added in the course of placing layers of solid radioactive wastes including their forced cooling with cold atmospheric air.

EFFECT: enhanced reliability and safety.

1 cl, 1 dwg

The invention relates to the field of storage of radioactive waste recycled
The invention relates to the field of radioactive waste immobilization

The invention relates to the field of spent nuclear fuel

FIELD: transport and storage of spent nuclear fuel.

SUBSTANCE: proposed method includes placement of fuel assemblies in transport package incorporating container and split damping casing designed so as to minimize lift of container when inserting it in split damping casing. Transport package is conveyed to storage place where container is freed of casing, whereupon spent fuel assemblies are kept in storage place. In the process spent fuel assemblies are first placed in container and then the latter is inserted in vertical position into split damping casing made in the form of removable drum with butt-end covering and base that functions as end lid of this drum. Charged container is installed on base, covered on top with removable drum, and the latter is fastened to base. Then split damping casing is secured to container, whereupon transport package is conveyed in transport position to storage place.

EFFECT: enhanced reliability of storage and transportation.

6 cl, 5 dwg

FIELD: nuclear engineering.

SUBSTANCE: proposed device for storage and/or transport of spent nuclear fuel has housing and cover forming inner space for holding spent nuclear fuel. Inner space is divided by means of partitions into compartments, each compartment being meant to receive spent fuel assembly. Each compartment accommodates two tanks holding metal hydride or intermetallic compound. These tanks are provided with channels pressurized with respect to inner space of device which are used to discharge hydrogen produced due to heat released by fuel assembly. Hydrogen outlet channels are designed for charging metal hydride through them and are provided with closing valves.

EFFECT: enhanced reliability of spent nuclear fuel storage and its safety in transit.

1 cl, 3 dwg

FIELD: handling spent nuclear fuel.

SUBSTANCE: proposed module designed for storage of spent nuclear fuel has tight case with inner space to receive spent nuclear fuel. Module is provided with ring made of solid ferromagnetic material possessing magnetocaloric properties. Ring is provided with drive and is free to rotate about its axis. It is disposed so that part of this ring is inside module in immediate proximity of tight tank holding spent nuclear fuel. Other part of ring is placed in constant magnetic field outside of module and can be cooled.

EFFECT: enhanced safety of spent nuclear fuel dry storage.

1 cl, 2 dwg

FIELD: shipment and storage of highly active wastes.

SUBSTANCE: proposed container for transport and dry storage of spent nuclear fuel has hermetically sealed storage tank and can holding spent nuclear fuel. In addition, it has external steel-reinforced concrete casing with outer and inner metal shells and bottom, cooling ducts, and fixing dampers. Hermetically sealed tank is provided with transport ring that holds shell in position relative to longitudinal axis of casing and with three detachable lids. It is also provided with dampers disposed over entire perimeter of inner cylindrical shell that function to lock cylindrical shell on lid and outer steel-reinforced concrete casing and to transfer heat therefrom. Cooling system is designed so that cooling air flows through cylindrical gap between outer surface of tank and inner surface of external steel-reinforced concrete casing over cooling ducts.

EFFECT: enhanced operating reliability of container.

5 cl, 4 dwg

FIELD: storage of hazardous materials.

SUBSTANCE: proposed device for keeping in storage hazardous materials such as spent radioactive nuclear fuel has cylindrical concrete housing accommodating three-dimensional pre-stressed hardware and axially elongated hazardous-material storage area. Pre-stressed hardware includes hardware fittings spirally passed about storage area and disposed in concrete housing close to outer surface.

EFFECT: enhanced reliability of hazardous material storage.

7 cl, 8 dwg

FIELD: handling radioactive wastes.

SUBSTANCE: proposed method for nuclear fuel storage in container includes introduction of nuclear fuel in fuel collector, as well as preparation of formwork to receive concrete body and installation of fuel collector into formwork. Formwork is immersed in tank and concrete is placed in immersed formwork to form concrete housing. Formwork with concrete housing formed therein is extracted from tank. System for manufacturing nuclear fuel storage container and for holding fuel in fuel collector installed in concrete housing that forms part of storage container has water tank. In addition it has tools for assembling formwork for storage container concrete housing and facilities for conveying formwork and fuel collector to water tank. It also has facilities for introducing nuclear fuel in fuel collector, facilities for concrete placement in formwork, and those for removing formwork from water tank. Nuclear fuel storage method includes piling of containers so that their central channels are aligned and held open for intercommunication. Fluid cooling agent is supplied to bottom end of central channel in lowermost storage container and discharged from top end of central channel in uppermost storage container.

EFFECT: enhanced reliability of radioactive waste isolation.

25 cl, 7 dwg

FIELD: safety facilities for handling radioactive materials.

SUBSTANCE: proposed internal container designed for long-time storage and transport of high-radioactivity materials such as plutonium dioxide has container body closed with sealed cover and specified-volume charging box placed in this body and provided with its respective cover. Container body has cylindrical passage for charging box that mounts additional internal cover provided with gas filtering device and hermetically installed relative to its surface for axial displacement. External cover of container body is provided with shut-off valve accommodating gas filtering device installed therein between inner space of container and valve seat. Such mechanical design of container enables reducing irreparable loss of plutonium during its long-time storage and transport.

EFFECT: enhanced safety and reliability , enlarged functional capabilities of container.

7 cl, 2 dwg

The invention relates to the field of nuclear engineering

The invention relates to the field of storage and transportation of spent nuclear fuel

The invention relates to the field of processing, transportation and disposal of spent nuclear fuel (SNF), in particular to a method of loading spent fuel in the transport of the radiation-shielding container ships nuclear technology maintenance (ATO) or on floating bases storage of spent fuel for further transportation

FIELD: safety facilities for handling radioactive materials.

SUBSTANCE: proposed internal container designed for long-time storage and transport of high-radioactivity materials such as plutonium dioxide has container body closed with sealed cover and specified-volume charging box placed in this body and provided with its respective cover. Container body has cylindrical passage for charging box that mounts additional internal cover provided with gas filtering device and hermetically installed relative to its surface for axial displacement. External cover of container body is provided with shut-off valve accommodating gas filtering device installed therein between inner space of container and valve seat. Such mechanical design of container enables reducing irreparable loss of plutonium during its long-time storage and transport.

EFFECT: enhanced safety and reliability , enlarged functional capabilities of container.

7 cl, 2 dwg

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