• 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:
    ,one. DEVICE FOR CAPTURE-. NIA OF MELTING HEAT BREACHING ELEMENTS OF A NUCLEAR REACTOR, containing a drain chute located under the active zone, leading to a catching bath located horizontally below the basement of the reactor and ending above the upper edge of the catching bath, which was created by using this solution. at the exit of the tray, the bath and the drain tray are made movable relative to each other. 13 ±. I. ..N. V /: -: -; v -; - i-V-: 4: vVvЗУА ЧУГ I П
    公开号:SU1118300A3
    申请号:SU802937818
    申请日:1980-06-25
    公开日:1984-10-07
    发明作者:Ляйсте Др.Ханс-Вальтер；Ульрих Ляйсте Ханс
    申请人:Др. Ханс-Вальтер Л йсте и Ханс Ульрих Л йсте (ФРГ)；
    IPC主号:
    专利说明:

    2, the device according to claim 1, wherein the bath is color mobile and is set eccentrically with respect to the active zone.
    3. A device according to claim 1, characterized in that the base of the trap bath is lined with a layer.
    having an enveloping and absorbing material and filler.
    4. A device according to claim 3, characterized in that the layer of coating and absorbing material and filler comprises a homogeneous mixture of 1/6 pieces of glass, 2/6 cement, 1/6 steel cubes and 2/6 grades of spar.
    The invention relates to a device for capturing melted heat-slitting elements of a nuclear reactor.
    In nuclear reactors or other nuclear power plants, the emitting material should not be released into the environment. In particular, in the case of an uncontrolled accelerating reactor, runoff of melting heat-generating elements to the soil should be prevented, since this can cause life-threatening environmental damage for a long time. In addition, technical measures should be taken to exclude the formation of secondary critical mass when melting fuel flows, since this effect is not excluded for fast neutron reactors, due to the amount of fuel in their active zone that is sufficient for the formation of secondary critical mass.
    A device for trapping molten parts of the core of a fast nuclear reactor is known, comprising an outlet tray and a bath of high-temperature material, installed below the core 13.
    The design drawback is insufficient turf safety, since when melted debris flows down the path of their movement, for example, due to blockage, as well as directly if it enters the bath, secondary critical mass may be formed, resulting in a secondary flash of a self-sustaining chain reaction. .
    The closest to the technical essence of the invention is a device for capturing melted heat-lancing elements of a nuclear reactor, which contains a drain tray located under the active zone leading to a catching bath horizontally located below the reactor and ending above the upper edge of the trap bath 23.
    A disadvantage of the known device is insufficient turf safety, since when the molten fuel flows into a fixed bath on the tray, a secondary mass can be formed from the tray.
    The aim of the invention is to increase the nuclear safety by eliminating the formation of secondary critical mass when the molten fuel flows down on the code from the tray.
    This goal is achieved by the fact that in a known device for capturing melted heat-loosening elements of a nuclear reactor, there is a drainage tray located under the active zone leading to a catching bath horizontally below the basement of the reactor and ending above the upper edge of the catching bath, the catching bath and the drainage tray are movable one relative to the other.
    In this case, the catching bath you-. full of mobile and installed eccentrically relative to the active zone.
    In addition, the base of the trap bath is lined with a layer having a coating and absorbing material and filler. 3 Moreover, the layer of enveloping and absorbing material and filler contains a homogeneous mixture of the following composition, h: 1/6 of glass fragments, 2/6 of cement, 1/6 of steel cubes and 2/6 of hard granite. The content of 1/6 of the glass fragments in the cladding layer was chosen because, in this case, the molten particles of heat removing elements envelop the molten glass and form regions that do not contain a secondary critical mass. A higher glass content would cause fusion of more extensive areas in which there is a possibility of the formation of a secondary critical glass, and a lower glass content would not allow it to reach the nodding range. The content of 2/6 parts of cement was chosen because, in this case, cement reliably protects the molten glass and binds the existing 1 moisture. With a smaller amount of cement, some of the WATER would remain unbound, and with a higher content of cement, part of it would be irretrievably lost. The content of 1/6 parts of steel cubes was chosen because it is this part that provides the satisfactory absorbing properties of the whole mixture, thereby reducing the likelihood of formation of the secondary critical mass. A smaller amount of steel would not allow the desired effect of neutron absorption to be achieved, and a larger amount would prevent a uniform distribution of the molten mass in the bath. A content of 2/6 parts of yellow spar prevents further melting of the existing particles, since the spar does not melt at a given temperature. At a lower shpat content, fusing of wider areas could begin, which could increase the likelihood of the formation of secondary kr. Mass and prevent uniform distribution of the molten mass in the bath. With a higher content of heavy spar, no increase in its effective effect is observed, as it is used to form non-fusible intermediate areas. In order to create additional protection, an additional protective bath is provided, the base of which extends below the drain chute and which, with its upper edge in the form of a wall that rises above the earth's surface, covers all reactor structures containing emitting material. FIG. 1 shows the proposed device, the cut; in fig. 2 - the same, without an additional bath, top view; in fig. 3 is a view A of FIG. 1. The device contains a nuclear reactor. 1 with the reactor core 3 located inside the dome (shell) 2 with heat-gap elements 4. Foundation 5 of the reactor dome is adjoined by a discharge tray 6, running vertically down first, which passes through the curved transition region 7 into the horizontal area of mouth 8. In the curved transition the area of the drain chute 6 rests on the foundation 9. The drain chute in cross-section has the shape of a bath (FIG. 3) with a width equal to approximately twice the width of the active zone 3, under which it passes, overlapping the surface, transitional Power 7 (Fig. 2). The discharge tray consists of a base layer 10 of stainless steel with a thickness of approximately 10 cm, on which a layer 11 is also applied with a thickness of approximately 10 cm of solid industrial porcelain, which has been vitrified several times. The horizontal area of the mouth 8 of the drain pan rests with its lower side on the slide bearing 12 on the upper edge 13 of the carousel catching bath 14. This carousel bath 14 is mounted on the base of the base 15 rotating on the ball bearing 16 on the bearing ring 17 and is driven slowly by the drive 18 rotation. In one embodiment, the upper edge 13 has a height of 3 m, and the base 15 has a diameter equal to four times the length of the heat-gap elements 4. The trap carousel 14 also has a base layer 19 of strong stainless steel approximately 10 cm thick, covered with a surface layer 20 of solid industrial porcelain. This layer 20 51 is vitrified twice as often as layer 11 of the drain tray 6. The interior of bath 14 is filled to approximately two-thirds of its height with a homogeneous mixture of 1/6 glass fragments, 2/6 cement, 1/6 steel cubes with dimensions of 10x10 cm as a retarding element and 2/6 tons of white spar as an additional agent. The mixture is unbound and protected from moisture. Its surface is indicated in FIG. 1 at 21, in addition to the mixture, it is also preferable to add cipher sticks of approximately 10x10 cm in size, as well as pieces of graph with the same surface dimensions. The purpose of using this mixture is to reliably slow down in the event of the heat-trapping elements flowing through the discharge chute 6 flowing through, preventing further draining and, moreover, trapping radioactive radiation. The bath 14 through the inlet 22 is accessible from the surface of the earth 23 through a space also shielded by the dome 24 from the surrounding environment. The suction pipe 25, which serves to suck radioactive gases, is also brought out to this dome from below. These gases can then be diverted from the upper outlet of the suction pipe 26 to a safe storage location, for example, lined with heavy spar or the like. sealed gas tanks. All devices, including safety devices, for additional protection are surrounded by an additional protective bath 27 with a van base below the catching bath 14. 28 and with a closed side wall 29, rising in the shape of the enclosing wall 30, for example, up to a height of 2 m above the surface of the earth 23 and thereby surrounding the construction of the nuclear power plant containing all of the radiating material. The additional protective bath consists of heavy spar-based benton and has a wall thickness of 1–2 m. In view of the expediency, its base is covered with the same homogeneous mixture of slow-motion 1x elements and a filler, as well as 14. Into the mixture, slate pats, as well as pieces of graphite with a surface area of approximately 10x10 cm. In order to also avoid any leakage of radioactive material above the ground, entrances and exits, and also entrances through the enclosing wall 30 must be in the form of stairs. or inclined entrances. While the drain chute 10 and the carousel catching bath 14 can be provided at reasonable costs in already existing nuclear reactors, the cost of providing an additional protective bath 27 is no longer economically viable. Therefore, an additional protective bath is only considered for new buildings. The device works as follows. After the accident and melting of the active zone, the heat-gap elements of the melted core are captured by the drain chute 6 and evenly distributed by the region of mouth 8 are dropped onto the surface 21 of the carousel bath 14, which is rotated, for example, automatically, which eliminates the formation of secondary mass. There, the heat slugging elements can remain without interfering with the repair work in reactor 1, until the time when they can be transported. The suction device (not forged), intended for the suction pipe 25, in the event of an accident, is also included as soon as it is determined that radioactive gases are present, be it in the interior of the dome 2 or above the surface of the carousel of bath 14 with covered with an amount of heat-generating elements. Such gases are then sucked into a protected space, namely, a gas-shielded gas reservoir, where they are held before transportation. The suction pipe 25 is opened and closed by hydraulic or mechanical, but not electric, mechanisms in order to avoid the danger of an explosion. This mechanism is equipped with a fuse to prevent leakage of any amount of gas. 711 The drain chute is so designed that the flowing heat slug elements obtain the necessary speed on the drain chute in order to reach the mouth 8 at a speed sufficient to fall on the carousel 14. Figure 2 The drain chute is also designed in this way which makes it possible to catch a globular fracture of the nuclear plasma and allows it to fall in the form of droplets or balls into a carousel bath. Phage.3
    权利要求:
    Claims (4)
    [1]
    ,1. DEVICE FOR CAPTURE OF FUSELY MELTING FUEL ELEMENTS OF A NUCLEAR REACTOR, containing a drain tray located below the active zone leading to a collecting bath horizontally below the base of the reactor and ending above the upper edge of the collecting bath, distinguished by eliminating the need for secondary education critical masses when the molten fuel is drained at the outlet of the tray, the bath and the drain tray are movable relative to one another.
    00 OE
    [2]
    2, The device according to p. ^ Characterized in that the bathtub is movable and mounted eccentrically with respect to the core.
    [3]
    3. The device pop. ^ characterized in that the base of the collecting bath is lined with a layer having enveloping and absorbing material and a filler.
    [4]
    4. The device pop. 3, characterized in that the layer of enveloping and absorbing material and filler contains a homogeneous mixture of 1/6 glass fragments, 2/6 cement, 1/6 steel cubes and 2/6 heavy spar.
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    同族专利:
    公开号 | 公开日
    FR2460026B1|1983-02-25|
    GB2052133A|1981-01-21|
    JPS5639492A|1981-04-15|
    CH627869A5|1982-01-29|
    DE2925680C2|1981-08-27|
    GB2052133B|1983-04-27|
    DE2925680B1|1980-10-23|
    FR2460026A1|1981-01-16|
    引用文献:
    公开号 | 申请日 | 公开日 | 申请人 | 专利标题
    DE4339904A1|1993-06-08|1994-12-15|Siemens Ag|Device for retaining a hot molten mass, in particular a core meltdown within the propagation chamber of a nuclear reactor installation|
    CN105551540A|2015-12-16|2016-05-04|中国核电工程有限公司|Core melt grouping trapping container|US4045284A|1975-03-10|1977-08-30|Rosewell Michael P|Nuclear reactor fuel containment safety structure|
    US4036688A|1975-04-09|1977-07-19|The United States Of America As Represented By The United States Energy Research And Development Administration|Apparatus for controlling molten core debris|
    DE2557884A1|1975-12-22|1977-06-30|Interatom|PROTECTIVE LAYER FOR FLOOR COOLER|
    DE2741795A1|1977-09-16|1979-03-29|Interatom|CORE REACTOR COLLECTION PAN WITH THERMAL INSULATION|DE4211030C2|1992-04-02|1994-03-10|Siemens Ag|Nuclear reactor plant with a water-cooled reactor and method for operating the same|
    DE4319094A1|1993-06-08|1994-12-15|Siemens Ag|Device and method for collecting and cooling meltdown|
    EP0730776B1|1993-11-23|1998-05-20|Siemens Aktiengesellschaft|Device for retaining a core melt-through inside the spreading chamber of a nuclear reactor installation|
    DE4322107A1|1993-07-02|1995-01-12|Siemens Ag|Device for collecting and cooling the meltdown|
    DE19512286C1|1995-04-05|1996-10-17|Siemens Ag|Arrangement for water displacement|
    DE19527462C1|1995-07-27|1996-12-05|Siemens Ag|Containers for receiving and spreading meltdown and nuclear power plant with such a container|
    DE19531626A1|1995-08-28|1997-03-06|Siemens Ag|Chamber to collect and retain molten reactor core material|
    JP2001510559A|1996-12-05|2001-07-31|シーメンスアクチエンゲゼルシヤフト|Container for containing and diffusing core melt and nuclear equipment equipped with the container|
    FR2985360A1|2012-01-02|2013-07-05|Jean Pronost|Nuclear security and safety device for use during total melting of cores of e.g. nuclear reactors after nuclear accident, has lining whose bottom is covered with resisting material to prevent from achieving nuclear material critical mass|
    法律状态:
    优先权:
    申请号 | 申请日 | 专利标题
    DE2925680A|DE2925680C2|1979-06-26|1979-06-26|Catcher for melting fuel elements of a nuclear reactor|
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