• 专利附录
  • 专利说明
  • 权利要求
  • 类似技术
  • 同族专利
  • 引用文献
  • 法律状态
  • 优先权
    • 专利摘要:
    1. A CONTAINER FOR TRANSPORTATION OF A RADIOACTIVE MATERIAL containing at least one removable shock absorber mounted on one of the ends of the container, characterized in that, in order to improve transportation reliability by improving shock absorption on impact, the shock absorber is made of two convex outside cups of the bells of the cups of the bells on the outside of the shock absorbers upon impact, the shock absorber is made of two convex outside cups of the bells, which are made of two convex outside plates of the cups of the bells on the shock absorbing shock absorption. the walls of the hermetically sealed cavity. 2. The container according to claim 1, characterized in that in the cavity of the shock absorber is placed as an energy absorbing material balsa wood, the fibers of which are parallel to the axis i of the container. 3. The container according to claim 1, (()) due to the fact that the side surface of the shock absorber has a toroidal shape.
    公开号:SU1144632A3
    申请号:SU813276844
    申请日:1981-04-20
    公开日:1985-03-07
    发明作者:Дорослай Пал；Феррони Ферручо
    申请人:Электроватт Инженерунтернемунг Аг (Фирма)；
    IPC主号:
    专利说明:

    This invention relates to shielding containers for transporting radioactive material and is intended for transporting irradiated fuel cells for a turf reactor. A container for transporting radioactive material is known, comprising a massive metal cylinder hermetically sealed at the bottom and top flj. The disadvantage of this container is the absence of shock-proof dampers, which, if dropped, can lead to damage to the casing and the impossibility of further use. The closest to the invention to the technical essence is a container for transporting radio active material, containing at least one removable shock absorber mounted on one of the ends of container 2. The known container is made of a massive forged steel cylinder, hermetically sealed at the bottom and top, so that Slammed the accident without damage. The massive steel case does not transmit gamma radiation. For shielding against neutron radiation, the container is provided with an outer casing filled with water. The side cooling fins serve, on the one hand, to release heat, and on the other, to absorb energy at the time of the container side impact. Shockproof dampers can be provided at the ends of the container, which are used both as a shield for protection against neutrons and as absorbing energy bodies. However, the ability to improve energy at the moment of impact with containers is insufficient. Depending on the angle of incidence and the position of the container at the moment of impact, it is possible to obtain non-uniform deceleration values and in some places very high deceleration peaks, which may entail dangerous damage to the containers. The purpose of the invention is to increase the reliability of transportation by improving depreciation on impact. The goal is achieved by the fact that in a container for transporting radioactive material containing at least one removable anti-shock damper mounted on one of the ends of the container, the anti-shock damper is made of two convexes outward of the cups that are the walls of the hermetically sealed cavity. In the cavity of the shock absorber is placed as an energy absorbing material balsa wood, the fibers of which are parallel to the axis of the container. The side surface of the shock absorber has a toroidal shape. FIG. 1 shows an empty transport container (section A-A in FIG. 2); in fig. 2 - the same for seven irradiated fuel cells (cross section); in fig. 3 the same, for seventeen irradiated fuel cells, cross section; in fig. 4 - fuel cells transported in a container; in fig. 5 is a section BB in FIG. one; in fig. 6 is a sectional view BB in FIG. 1. The transport container consists of a cylindrical body 1 (FIG. 1) of the box 2, for carrying fuel elements, an internal locking lid 3, an outer lid 4 of the container and two shock-absorbing dampers 5 and 6 mounted on the ends of the container. Six container trunnions are provided for lifting the container 7, four of which are mounted on the upper end, and two on the lower end. . The cylindrical body 1 has a bottom 8, in addition, an internal locking cap 3 is installed on it. The cylindrical body 1, the bottom 8 and the internal locking cap 3 are made of carbon steel and provide protection against gamma radiation. The cavity of the container and the outer parts are covered with a stainless steel sheet. The cylindrical part of the container is surrounded by a water jacket 9. The latter extends in the axial direction between the lower and upper bearing pins 7 for shielding the core of the fuel cells. Water serves as a shield for protection against fast neutrons. The outer casing 10 of the water jacket is provided with annular cooling ribs 11 made of steel for perimeter for heat transfer. At the upper end of the outer casing 10 there is an annular chamber.
    3
    12 extensions, separated from water. In this expansion chamber 12, filled with gas, there are two concentric mounted bellows
    13 of stainless steel. As water expands, gas in expansion chamber 12 is compressed between the bellows 13 and the latter expand. The normal working pressure of water is approximately 2 bar. In order to protect the outer casing from being exposed to too high a water pressure, it is provided with several small washers with a predetermined fracture point. Valves installed on opposite sides of the lower end of the outer casing 10 are provided for water inlet and outlet. The other valve enters the expansion chamber 12 and serves to fill this chamber with gas and to empty it.
    The outer casing 10 is closed at the lower and upper ends with thick lateral ribs 14 that are filled along the perimeter and are used to absorb shocks.
    To control the temperature of the container, temperature sensors are provided that enter the container to different depths. The temperature sensors are located in the hottest area of the cylindrical container body 1 directly in front of the cooling fins. Temperature sensors are placed in the pipe, in a manner that the scattered gamma rays do not have a free exit. The total length of the cylindrical body 1 of the container is 5.29 m. The depth of the container measured from the surface of the flange 15 to the bottom of the container is 5.12 m. In case of fitting the internal locking mechanism 3 and no spacers, the maximum depth is 4.655 m.
    The cooling steel fins 11 are coated with a protective epoxy resin layer which can be decontaminated from radioactive substances. All other loose parts of the container, with the exception of massive stainless steel ribs 14 at the ends of the outer casing, are made of stainless steel or are covered with at least a layer of stainless steel sheet with a thickness of 3 mm. The inner concave surfaces of the container are also covered with stainless 446324
    steel. .To ensure the safety of the transport container has two krysh1ki.- To close the container serve as an internal lock
    5 bolts 3 with an annular flange 15 and fixing bolts 16, an outer bolt 4 of the container with fixing bolts 17, three metal O-rings (not shown) and
    10 flange 18 with holes for fastening bolts 19 of shock-absorbing dampers 5 and 6. Various restricting spacer washers can be fixed to the internal locking knob 3 so that the dimensions of the container cavity can be adapted to the length of the various i transported fuel rods. The inner bolt 3 and the fastener bolts, which are fastened to it with bolts, form an integral transport unit. So: 1sak is internally locked 3; made of steel, it provides
    25 sufficient shielding against gamma radiation. Both shock absorbers 5 and 6, filled with balsa wood 20, provide shielding of neutron radiation.
    j Twenty-four evenly spaced bolts 16 secure the internal locking cap 3 by means of an annular flange 15 on the housing 1
    - container. The top lid 4 of the container is fixed with twelve additional, equally spaced bolts 17. To fix the shock absorbers 5 and 6,
    0 annular flange 18 and eight other evenly distributed bolts 19. Bolts 16-19, annular flanges 15 and 18 and the top lid 4 of the container are made of stainless steel. Inside 5 ren, the locking key 3, in turn, is covered with a stainless steel sheet.
    Boxes 2 and 21 can be inserted into the jg shipping container. Box 2 ((FIG. 2) serves to hold seven fuel cells in it, and Box 21 (Fig. 3) holds seventeen fuel cells in it. 55 Boxes 2 and 21 have high internal strength and provide shielding against neutrons for safe transportation of fuel cells. In this case, the polyenes are anti-shock. In a normal transport of fuel cells, it is carried out in a dry state. The boxes provided for this box 2 and 21 are thick, cast aluminum washers 22 Stainless bolts 23 (FIG. 1) are provided between the inner wall of the container and the aluminum washers 22, taking into account thermal expansion, clearance. Inside the boxes 2 and 21 there are elongated channels 24 for fuel cells made of stainless boron steel with additive 1% by weight of neutral boron to absorb neutrons. Boxes 2 and 21 are also lower limit spacer plates 25 (Fig. 4) for fuel cells. Cylindrical holes 26 are provided between fuel channels 24 for fuel cells in which there is a mixture of graphite and boron carbide, the latter being placed in stainless steel pipes. This mixture is also part of the neutron shield. Fuel cells 27-29 can be transported with or without a containment shell 30. If the transport is carried out without additional protective sheath, then additional channels made of stainless steel must be welded to the lower limiting spacer plates 25 and pressed into the channels 24 (Fig. 1). One or more channels 24 made of stainless steel. can be mounted in box 2 with the option of removing them. After these channels have been removed, special protective containers for damaged fuel cells are pushed into the free cavity 24 times. The rest, never e a ie, channels 24 are welded to. top stainless steel plate 31 (4ig. 4) boxes 2 (Fig. 1). In this way, thermal expansion down is provided. In the case of transporting fuel cells in the wet state, thin-walled boron steel pipes are pushed into the channels 24, to prevent bending of them, expansion rings 32 are provided that are spaced apart from each other at a certain distance. Holes are formed in these expansion rings 32 so that water can circulate freely. In the horizontal transport position, the expansion rings 32 sense the weight of the fuel cells. In order that the box 2 or 21 can be pushed into the transport container in a straight line without any possibility. To rotate or move it during transport, a longitudinal groove is made on the outer surface of the box into which the corresponding protrusion is made, which is made on the inner wall of the container. The bearing pins 7 serve, on the one hand, for lifting the container for transportation, and on the other, for fastening it on the transport container. For example, a saddle device welded to the transport carriage can be used as a transport substrate. The bearing pins 7 are screwed into the body 1 of the container with the possibility of their removal. They are, with the exception of their inner portions, deformable. The two lower bearing pins 7 are mounted eccentrically with respect to the axis 33 (Fig. 1) of the container in order to ensure the overturning of the transport container in the gauge; green side when lowering it to the saddle unit. Support studs 1 and bolts are made of stainless steel. The shock absorbers 5 and 6 consist mainly of a thick-walled outer cup 34, a thin-walled inner cup 35, gaskets of balsa wood 20, an annular flange 36 and; several pipes 37. Both cups 34 and 35 are welded on the outside to an annular flange 36, which serves centering the shock absorber when it is mounted. It is fixed to the cylindrical body 1 of the container with bolts 19. Thick-walled pipes 37 passing through the damper 5 are welded to the outer cup 34 and to the annular flange 36. Bolts 19 can be pushed through the pipes 37. In case the transport container falls axially downwards, the kinetic energy at the moment The following parts absorb the impact: the circular in horizontal projection is convex to the outside, the outer cup 34, which is axially relatively soft and pliable; Balsa-wood packing 20, the walls of which are directed parallel to the axis 33 of the container (balsa wood can absorb a significant part of the kinetic energy); rigid tubes 37 absorbing approximately 50% of the energy during deformation. .. In the event of impact of the side wall of the transport container, the kinetic energy is absorbed by the torus-shaped part 38 of the outer cup 34, as well as by massive end ribs 14. They deform approximately simultaneously and absorb approximately the same amount of energy. In this case, the absorption of the kinetic energy of the impact by balsam wood is absent due to the orientation of its fibers. In case of impact of the edge of the transport container, a combination of both of the above-mentioned cases of energy absorption takes place, and balsa wood absorbs more or less energy depending on the angle of impact. The proposed implementation of the transport container allows uniform deceleration and energy absorption in all directions without negative deceleration peaks, which can be observed using known Hbtx containers in which only the ribs are deformable. The advantage is also the uniform distribution of the work of deformation on the outer surface of the proposed transport container. The bearing pins 7 are deformable and can also absorb kinetic energy if they are struck to the side by the end side when the container is dropped. The outer cups 34 and all tubes 37 are made of stainless steel. The cavity between the outer and inner cups is hermetically closed so that the packing of balsa wood cannot polish moisture. For transportation, the container is mounted horizontally on the saddle with the carriage. For rail transport, a carriage is installed on a flatbed car or on a special freight car with a platform. In the first case, an entire installation consisting of a carriage, a container, and a door has the dimensions of a standard container, so that this installation can be transported further and to. the ship. In the case of transportation on a freight car with a platform, the center of gravity is lower, so that higher speeds during transportation can be achieved. The container cavity is accessible through the internal closure lid 3 pressed by the annular flange 15, through two valves 39 (Fig. 5-6) and through small closed sampling holes made in the internal locking knob 3. The cavity is sealed by both valves 39 metal rings of circular cross section located between the annular flange 18 and the internal locking lid 3 and between the flange 18 and the corresponding sealing surface of the container body 1. The opening for sampling and control of the atmosphere in the cavity is made in the support pin 40 of the internal shut-off valve Krysha 3. Plastic O-rings are placed between the outer lid 4 of the container and the body 1 of the container, while at the same time the valves of the valves are sealed to the valves with metal O-rings. In the outer lid 4 of the container and in the cranks: the valves are provided with openings for sampling and control. They . also serve to control the tightness of the cavity. The advantage of the two cavities is that the valve between them can be continuously monitored for leakage of radioactive material. All removable parts of the container cavity, with the exception of cast aluminum washers in the box, are made of stainless steel or covered with a layer of stainless steel sheet 3 mm thick. Stainless
    9
    Steel is resistant to the following liquids for cleaning and disinfection: demineralized water, nitric acid, sodium hydroxide solution and nitrofluor solution with 5% fluorine.
    The lower part of the cavity of the container can be cleaned through the lower valves.
    All outer surfaces of the coyner, including the liquid pump, are also covered with stainless steel sheet, with the exception of the section with cooling fins. When the transport container is unloaded in the wet state, when it is immersed in the discharge basin, the area with cooling fins is covered with a special shield. The latter consists of a cylindrical casing made of stainless steel, equipped with inflatable rubber gaskets. Before the transport container is immersed in the discharge basin, it is brought to a vertical position and secured by means of the lower bearing pins 7 on the base. A stainless steel case is then attached, which is sealed with inflatable rubber gaskets. At the lower end of the casing, opposite the container valve, a removable cap is provided for the purpose of connecting the pipelines to the container valve and after attaching the casing. During this operation, the valve between the top and bottom gaskets can already be emptied at that time.
    4463210
    as a section with cooling fins still surrounded by water.
    If the shipping container is immersed, the water pressure between J with both inflated rubber gaskets at both ends is higher than the outside, so that the water of the discharge pond cannot enter the cavity of the ribs. An epoxy paint is applied on the ribs, allowing easy cleaning and disinfection in case of radioactive contamination.
    After attaching the jacket, it is necessary to remove the heat input by cooling the area with cooling fins. For this purpose, it is necessary to provide for the connection dp of cooling water on the casing.
    The removal of heat from the container is carried out by convection and heat radiation, primarily through cooling fins, since both shock absorbers are heat insulating. A small amount of heat is discharged through the supporting and non-ribbed surface of the housing.
    At the moment of impact of the container after a free fall, NPIs in the fire take into account the loss of water in the casing 10. The empty casing 10 slokokit then as an insulating layer, and heat is given only located in the inside of the cooling fins.
    Various emergency cases can be simulated and investigated with the help of computing devices.
    Phage. 2 "7 /
    Fig.Z
    JO
    X
    25 FIG. four
    Phage. 5 bb
    权利要求:
    Claims (3)
    [1]
    1. CONTAINER FOR TRANSPORTATION OF RADIOACTIVE MATERIAL, containing at least one removable shockproof damper mounted on one of the ends of the container, characterized in that, in order to increase the reliability of transportation due to improved shock absorption during impact, the shockproof damper is made of two outwardly convex cups being the walls of a hermetically sealed cavity.
    [2]
    2. The container according to claim 1, characterized in that in the cavity of the shockproof damper is placed as energy-absorbing material balsa wood, the fibers of which are parallel to the axis of the container.
    [3]
    3. The container according to claim 1, characterized in that the side surface of the shockproof damper has a toroidal shape.
    1 1,144,632 1
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    同族专利:
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    引用文献:
    公开号 | 申请日 | 公开日 | 申请人 | 专利标题
    RU2518159C1|2012-12-04|2014-06-10|Федеральное государственное унитарное предприятие "Горно-химический комбинат"|Transport packaging set for transportation and storage of nuclear fuel|
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    RU2706336C1|2018-06-01|2019-11-18|Российская Федерация, от имени которой выступает Государственная корпорация по атомной энергии "Росатом" |Method of manufacturing, storage and application of mobile portable module for repair of damages in transported containers with toxic materials|FR1568340A|1968-03-29|1969-05-23|
    FR1586456A|1968-08-30|1970-02-20|
    US3619616A|1969-01-24|1971-11-09|Gen Electric|Forced air cooled radioactive materials container|
    FR2031845A5|1969-02-10|1970-11-20|Commissariat Energie Atomique|
    FR2113805B1|1970-11-17|1976-03-19|Transnucleaire|
    US3731101A|1971-04-14|1973-05-01|Nl Industries Inc|Shipping container for radioactive material|
    ES401582A1|1971-06-11|1977-07-01|Gen Electric|A transportation container for radioactive material. |
    DE2221610A1|1972-05-03|1973-11-15|Kernforschungsanlage Juelich|Radiation shielded transit pack - for radioactive material or components|
    US3886368A|1973-02-27|1975-05-27|Nuclear Fuel Services|Spent fuel shipping cask|
    FR2254860B3|1973-12-17|1977-09-16|Etude En Centre|
    FR2258692B1|1974-01-23|1977-03-04|Transnucleaire|
    US3962587A|1974-06-25|1976-06-08|Nuclear Fuel Services, Inc.|Shipping cask for spent nuclear fuel assemblies|
    GB1496846A|1975-12-01|1978-01-05|Atomic Energy Authority Uk|Transport containers for radioactive material|
    DE2830305B1|1978-07-10|1980-01-24|Kraftwerk Union Ag|Fuel transport container|
    US4336460A|1979-07-25|1982-06-22|Nuclear Assurance Corp.|Spent fuel cask|DE3037328C2|1980-10-02|1982-12-23|Transnuklear Gmbh, 6450 Hanau|Shock absorbers for containers for the transport and / or storage of radioactive material|
    IT1152714B|1982-10-11|1987-01-07|Aginucleare Spa|IMPACT ABSORBER FOR NUCLEAR FUEL CONTAINERS AND / OR DANGEROUS CHEMICAL SUBSTANCES|
    DE3301735C2|1983-01-20|1986-04-10|Kernforschungsanlage Jülich GmbH, 5170 Jülich|Transitional storage facility for highly radioactive waste|
    FR2556877A1|1983-12-19|1985-06-21|Fonderie Alcoa Mg Sa|INSERT NEUTROPHAGE FOR CONTAINER FOR TRANSPORTING BARS OR RADIOACTIVE MATERIALS, AND CONTAINER COMPRISING SUCH INSERTS|
    DE3425978C2|1984-07-14|1987-07-02|Kernforschungszentrum Karlsruhe Gmbh, 7500 Karlsruhe, De|
    DE3430243C2|1984-08-17|1986-11-27|Deutsche Gesellschaft für Wiederaufarbeitung von Kernbrennstoffen mbH, 3000 Hannover|Storage container for holding individual fuel rods from irradiated nuclear reactor fuel elements|
    US4636645A|1984-10-31|1987-01-13|Westinghouse Electric Corp.|Closure system for a spent fuel storage cask|
    FR2588993B1|1985-10-17|1988-01-08|Transnucleaire Sa|PACKAGING FOR THE TRANSPORT OF HAZARDOUS MATERIALS|
    US4908515A|1985-12-27|1990-03-13|Nus Corporation|Method of efficiently storing spent nuclear fuel rods in a cylindrical container|
    US5061858A|1987-10-19|1991-10-29|Westinghouse Electric Corp.|Cask assembly for transporting radioactive material of different intensities|
    US4825088A|1987-10-30|1989-04-25|Westinghouse Electric Corp.|Lightweight titanium cask assembly for transporting radioactive material|
    US4972087A|1988-08-05|1990-11-20|Transnuclear, Inc.|Shipping container for low level radioactive or toxic materials|
    US5394449A|1993-10-08|1995-02-28|Pacific Nuclear Systems, Inc.|Impact limiter for spent nuclear fuel transportation cask|
    WO1995010839A1|1993-10-08|1995-04-20|Vectra Technologies, Inc.|Impact limiter for spent nuclear fuel transportation cask|
    US20010011711A1|1996-05-03|2001-08-09|Graham Nicholson|Container for nuclear fuel transportation|
    GB9609304D0|1996-05-03|1996-07-10|British Nuclear Fuels Plc|Improvements in and relating to fuel transportation|
    US5894134A|1996-09-13|1999-04-13|General Atomics|Shipping container for radioactive material|
    US6332906B1|1998-03-24|2001-12-25|California Consolidated Technology, Inc.|Aluminum-silicon alloy formed from a metal powder|
    US5965829A|1998-04-14|1999-10-12|Reynolds Metals Company|Radiation absorbing refractory composition|
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    法律状态:
    优先权:
    申请号 | 申请日 | 专利标题
    CH759379|1979-08-20|
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