A receiving unit for spent fuel assembly
(57) Abstract:Usage: the device is intended for transportation teplosistema assemblies. The essence of the invention: a receiving unit for spent fuel assemblies containing foam with elements of its mounting in the pool, made a split in the plane perpendicular to its surface and seal in the joint. The lower part of the device is provided with a vertical guideway formed by the continuation of its walls, and the sealing sleeve mounted on the removable part of the case. The length of the removable part of the case is 1.2oC2,0 the length of the fuel Assembly. 1 C.p. f-crystals, 8 ill. The invention relates to the field of spent nuclear fuel (SNF), in particular, to the technology of transportation of fuel assemblies from the unloading-loading machines (RCM), in the pool for storage. The invention can be used in existing nuclear power plants, and the design of new units.The closest analogue of the proposed technical solution is a receptor for the spent fuel Assembly details of which are contained in the work. The receiver is designed in teplovidelyaushaya Assembly is made through the open upper end of the device, which is located above the water pool storage of spent nuclear fuel. Loading of the fuel assemblies in the device is performed by REM, in the construction which provides protection against ionizing radiation of spent fuel Assembly. Subsequent extraction of the fuel Assembly receiving device is performed by the handling equipment of the reactor hall, which does not contain protection against ionizing radiation of spent fuel Assembly.The disadvantages of the device closest analogue is:
the necessity of lifting the fuel Assembly protective volume of pool water when it is unloaded from the receiving device in which the premises of the reactor hall creates a high level of radiation. The occurrence in these terms of possible failure handling equipment is associated with high labor costs and doses to eliminate it. In addition, changes in the environment: water air water leads to changes in the temperature of the fuel Assembly and reduces the corrosion resistance of the material of the shells.The task of the proposed technical solution, so the bit device (pencil case, of the case).The essence of the proposed technical solution is that the receiving device for spent fuel assemblies containing foam with elements of its mounting in the pool, made a split in the plane perpendicular to its surface and seal in the joint. For easy operation the lower part of the device is provided with a vertical guideway formed by the continuation of its walls, and the sealing sleeve mounted on the removable part of the case. The length of the removable part of the case is 1.2oC2,0 length fuel Assembly conditions the availability of the necessary protective layer of pool water when removing from the output device and the transportation pool teplovidelyaushaya assemblies of different sizes and different values of the decay power.The technical solution is illustrated graphic material. In Fig.1 shows a receiving device in the incision. In Fig.2 a longitudinal section a-a receptor. In Fig.3 view B of Fig.1. Fig.4, 5, 6, 7, 8 the sequence of execution of transport operations with the fuel Assembly using the receiver.The receiving device (pencil box) 1 (Fig.1) consists of a bottom part 2 and the EC 5, the support 6. At the bottom of the lower part 2 of the case 1 has an elastic element 7. The upper part 3 of the case 1 contains the gasket 8 and the flange 9. The case 1 is installed in a water pool 10. In the upper part of the basin 10 case 1 is fixed folding grip 11, hinged to the bracket 12. The bracket 12 is provided with a limiter 13 lateral displacement of the suspension 14 fuel Assembly 15 (Fig.4).The receiving device (pencil box) 1 works as follows (Fig.4, 5, 6, 7). The case 1 is mounted on the bottom 16 of the basin 10 and fixed by capturing 11 (Fig.4). Unloading-loading machine (REM) (Fig. not shown) discharged from a reactor fuel Assembly 15, join with the upper part 3 of the case 1 through a connecting pipe 17 with cuffs 18 and do unloading of the fuel assemblies 15 in the case 1. In this case, a fuel Assembly 15 is backed by a sealing tube 19 of the suspension 14 fuel Assembly 15 on the upper end of the removable upper part 3 of the case 1. After unloading the fuel assemblies 15 are produced undocking REM with case 1 and the machine REM divert from the receiving device 1. To release the removable upper part 3 of the case 1 (Fig.5), through valve 20 and the grip 21 of the fuel is x2">After dismantling of the tube 19 of the fuel Assembly 15 mounted on the elastic element 7 (Fig. 6). Liberated shoot the upper part 3 of the case 1 (Fig. 6) through the valve 20 and the grip 23, is removed from a vertical guideline 4 of the lower part 2 of the case 1, and the folding grip 11 folded. Further, through the seizure 21 (Fig.7) fuel Assembly 15 with the suspension 14 is suspended on the hook of the crane 20 and removed from the slot of the bracket 12, the limiter 13 lateral displacement of the suspension 14 fuel Assembly 15, and then, the fuel Assembly 15 with the suspension 14 is lifted by the crane 20. After the release of the lower end of the fuel Assembly 15 (Fig.7) from the cavity of the lower part 2 of the case 1, further lifting her stop and move under the protective layer of water in the pool 10 (Fig. not shown) to place the following technological operations: the Department of the suspension 14 from the fuel Assembly 15, etc.Technology using the proposed receiving device 1 may have other options. For example, in Fig.8 illustrates the operation of the proposed receiving device 1 with the installation unloaded from the machine REM fuel Assembly 15 through the sealing tube 19 of the suspension 14 to the upper end of the vertical guide 4 n the Yemen device 1, undocking REM with the receiving device 1, etc. described previously and corresponds to the numbers of the positions indicated in Fig.4, 5, 6, 7.Implementation of the proposed solution allows to increase the security technology of spent nuclear fuel and the safety of nuclear power plants. 1. A receiving unit for spent fuel assemblies containing foam, open top, with the fastening elements into the pool, wherein the housing case is made detachable in the plane perpendicular to its generatrix, and sealed at the interface of the two parts, and the length of the upper removable part of the case is 1.2 2.0 length of the fuel Assembly.2. The device under item 1, characterized in that the lower part of a case provided with a vertical guideway formed by the continuation of its walls.
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
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: 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: 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: 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: 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: 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 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
FIELD: storage and transportation of used nuclear fuel.
SUBSTANCE: metal-concrete container for transportation and/or storage of used assemblies of fuel elements of nuclear reactors has case with bottom, internal protection air-tight cap, edge damping members. Casing with central cell is inserted inside cavity of case. Peripheral cells are disposed around central cell for mounting housings with used assemblies of fuel elements. Peripheral cells are made in form of tubular members that are mounted to have spaces in relation to internal protection air-tight case and bottom of case. Casing has longitudinal rod members disposed around circle in relation to central cell of casing. Container has first and second sheet members which are mounted along height of case and are connected for disconnection by means of longitudinal rods. Edge damping members are made in form spring-shaped members and they are mounted onto internal protection air-tight cap each in opposite to corresponding cell of casing for interaction with housing under normal conditions of exploitation of metal-concrete container.
EFFECT: higher safety of handling of loaded container.
6 cl, 7 dwg
FIELD: storage and transportation of spent nuclear fuel.
SUBSTANCE: proposed metal-concrete container for transportation and/or storage of nuclear-reactor spent fuel assemblies has housing with bottom, internal pressurizing safety cover, hood inserted into housing and provided with cells to receive boxes with spent fuel assemblies. Container also has damping members engageable with cover on inner surface end, with housing bottom, and with housing internal wall. Hood is installed within housing in a space relation to housing internal wall. Side damping members are installed between the latter and hood. Each damping member is made in the form of longitudinal rod passed through holes in respective first and second sheet members installed throughout container height on internal wall of housing and on hood and disposed in parallel with housing bottom.
EFFECT: enhanced reliability of spent nuclear fuel storage.
6 cl, 5 dwg