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CN105427900B - A reactor melt retention system after a severe accident - Google Patents
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CN105427900B - A reactor melt retention system after a severe accident - Google Patents

A reactor melt retention system after a severe accident Download PDF

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CN105427900B
CN105427900B CN201510918964.9A CN201510918964A CN105427900B CN 105427900 B CN105427900 B CN 105427900B CN 201510918964 A CN201510918964 A CN 201510918964A CN 105427900 B CN105427900 B CN 105427900B
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reactor
fusant
temperature
pile
gaseous
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CN105427900A (en
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郭强
张丽
韩旭
徐钊
王晨
元一单
马卫民
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China Nuclear Power Engineering Co Ltd
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China Nuclear Power Engineering Co Ltd
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    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C9/00Emergency protection arrangements structurally associated with the reactor, e.g. safety valves provided with pressure equalisation devices
    • G21C9/016Core catchers
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C15/00Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
    • G21C15/18Emergency cooling arrangements; Removing shut-down heat
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C15/00Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
    • G21C15/18Emergency cooling arrangements; Removing shut-down heat
    • G21C15/182Emergency cooling arrangements; Removing shut-down heat comprising powered means, e.g. pumps
    • YGENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear fission reactors

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  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Structure Of Emergency Protection For Nuclear Reactors (AREA)

Abstract

The present invention relates to reactor safety system designing techniques, and in particular to reactor fusant out-pile gaseous-waste holdup system after a kind of major accident.Its structure includes fusant arresting device and cooling line, the fusant arresting device being located at below pressure vessel as key equipment, including the porous sacrificial layer and high-temperature crucible construction package for allowing fusant layering diffusion and coolant to pass through, high temperature resistant support column is distributed between each layer as support;Cooling line can continue the cooling water in supplement reactor pit, guarantee flooding and persistently cooling down completely for fusant.When nuclear power station generation reactor core melts the major accident ruined, the present invention can be realized reactor core fusant utmostly and quickly and effectively dispersion cooling, so that reactor pit bottom burn through risk is reduced, the safety under raising reactor disaster.

Description

一种严重事故后反应堆熔融物堆外滞留系统A reactor melt retention system after a severe accident

技术领域technical field

本发明涉及反应堆安全系统设计技术,具体涉及一种严重事故后反应堆熔融物堆外滞留系统。The invention relates to the reactor safety system design technology, in particular to a reactor melt retention system outside the reactor after a severe accident.

背景技术Background technique

我国目前在建和在运行着的大型二代改进型核电厂,多数未设置有效的堆外熔融物滞留系统。日本福岛事故后,核电站安全问题特别是针对严重事故的预防和缓解更为迫切。目前针对严重事故下,堆芯熔融物的冷却与滞留策略主要可分为两种:1)压力容器内熔融物的冷却与保持(IVR),在美国西屋公司的AP-1000机型设计中得到应用;2)压力容器外熔融物冷却与收集(EVR),在俄罗斯设计的VVER-1000机型与法国ANP设计的先进压水堆EPR机型中得到应用。对于堆外冷却策略,俄罗斯的VVER-1000“坩埚”式捕集器综合了AP600非能动供水冷却熔融物包容体金属表面的设计特点和欧洲先进压水堆堆芯捕集器通过牺牲材料改善熔融物特性和降低热流密度的技术特点;法国的ANP“扩展”式堆芯捕集器的设计思路是使熔融物直接流入反应堆堆坑中,在高温作用下熔融物与堆坑牺牲性混凝土发生化学反应,逐渐消融牺牲混凝土,达到初步冷却、收集熔融物的功能,且整个化学反应过程在堆坑保护层保护下进行,确保熔融物不会穿透堆坑进入到结构混凝土,以控制核辐射扩散。国内关于堆芯捕集器的研究也有相关专利见报,如上海核工程研究设计院Ⅰ、Ⅱ、Ⅳ型底部开口蒸汽管道壁式堆芯熔融物滞留装置(CN103377724A,CN103377723A,CN103377720A),具有集成冷却通道的堆芯捕集器(CN103081023A),底部注水叠加外部冷却的大型非能动核电厂堆芯捕集器(CN103177778A)以及有熔融物扩展室的大型非能动压水堆核电厂堆芯捕集器(CN103165198A)等。Most of the large-scale second-generation improved nuclear power plants currently under construction and in operation in my country do not have an effective external melt retention system. After the Fukushima accident in Japan, the safety issues of nuclear power plants, especially the prevention and mitigation of severe accidents, are more urgent. At present, for severe accidents, the cooling and retention strategies of the core melt can be mainly divided into two types: 1) The cooling and retention (IVR) of the melt in the pressure vessel is obtained in the design of the AP-1000 model of the Westinghouse Company in the United States. Application; 2) Cooling and collection of melt outside the pressure vessel (EVR), which is applied in the VVER-1000 model designed in Russia and the advanced pressurized water reactor EPR model designed by ANP in France. For the out-of-core cooling strategy, Russia's VVER-1000 "crucible" trap combines the design features of the AP600 passive water supply to cool the metal surface of the molten material inclusion and the European advanced pressurized water reactor core trap improves melting by sacrificial materials The technical characteristics of material characteristics and heat flux reduction; the design idea of the French ANP "extended" core catcher is to make the melt flow directly into the reactor pit, and the melt reacts chemically with the sacrificial concrete of the pit under the action of high temperature. The reaction gradually melts the sacrificial concrete to achieve the functions of preliminary cooling and collecting the melt, and the entire chemical reaction process is carried out under the protection of the pile pit protection layer to ensure that the melt will not penetrate the pile pit and enter the structural concrete to control the spread of nuclear radiation . Domestic research on core traps has also been published in relevant patents, such as Shanghai Nuclear Engineering Research and Design Institute Type I, II, and IV type bottom opening steam pipe wall core melt retention devices (CN103377724A, CN103377723A, CN103377720A), with integrated cooling Channel core catcher (CN103081023A), large passive nuclear power plant core catcher with bottom water injection and external cooling (CN103177778A) and large passive pressurized water reactor nuclear power plant core catcher with melt expansion chamber (CN103165198A) etc.

但以上专利申请所公开的技术都没有涉及冷却剂可渗透的滞留盘设计,也没有实现熔融物在可控条件下的逐层分摊冷却的设计,因而可以基于上述的思路,研发冷却能力更强,安全滞留效率更高的堆芯熔融物滞留技术。However, none of the technologies disclosed in the above patent applications involves the design of a coolant-permeable stagnation plate, nor does it realize the design of layer-by-layer cooling of the melt under controllable conditions. Therefore, based on the above ideas, a stronger cooling capacity can be developed , Core melt retention technology with higher safety retention efficiency.

发明内容Contents of the invention

本发明的目的在于针对核电站安全设计的需要,提供一种严重事故后反应堆熔融物堆外滞留系统,在核电站发生堆芯融毁的严重事故时,能够实现堆芯熔融物最大程度且快速有效的分散冷却,从而降低堆坑底部熔穿风险,提高反应堆事故下的安全性。The purpose of the present invention is to meet the needs of nuclear power plant safety design, to provide a system for the retention of reactor melt outside the reactor after a severe accident, which can realize the maximum, fast and effective recovery of the core melt when a serious accident of core meltdown occurs in a nuclear power plant. Decentralized cooling, thereby reducing the risk of melt-through at the bottom of the reactor pit and improving safety in the event of a reactor accident.

本发明的技术方案如下:一种严重事故后反应堆熔融物堆外滞留系统,包括设置在反应堆压力容器下方堆坑底部的熔融物滞留装置和来自于安全水源的冷却管线,所述的熔融物滞留装置能够承接反应堆压力容器投影范围内所有落下的熔融物射流,其中,所述的熔融物滞留装置包括多层允许熔融物和冷却剂穿透的耐高温坩埚,在每层耐高温坩埚上设有能够被熔融物熔穿的多孔牺牲层。The technical scheme of the present invention is as follows: a reactor melt retention system after a serious accident, comprising a melt retention device arranged at the bottom of the reactor pit below the reactor pressure vessel and a cooling pipeline from a safe water source, the melt retention The device is capable of receiving all falling melt jets within the projection range of the reactor pressure vessel, wherein the melt retention device includes multiple layers of high-temperature-resistant crucibles that allow the melt and coolant to penetrate, and each layer of high-temperature-resistant crucibles is equipped with A porous sacrificial layer that can be melted through by the melt.

进一步,如上所述的严重事故后反应堆熔融物堆外滞留系统,其中,相邻的两层耐高温坩埚之间设有起连接和支撑作用的耐高温支撑柱。Furthermore, in the reactor melt retention system after a serious accident as described above, a high-temperature-resistant support column is provided between two adjacent layers of high-temperature-resistant crucibles for connection and support.

更进一步,如上所述的严重事故后反应堆熔融物堆外滞留系统,其中,相邻的两层耐高温坩埚之间留有高度为40-60cm的自由空间。Furthermore, in the reactor melt retention system after a severe accident as described above, there is a free space with a height of 40-60 cm between two adjacent layers of high-temperature-resistant crucibles.

进一步,如上所述的严重事故后反应堆熔融物堆外滞留系统,其中,除最底层以外的每层所述耐高温坩埚上设有阵列式分布且隔层交错的流通孔,所述的多孔牺牲层以20-30cm的厚度平铺在每层耐高温坩埚的上表面。Furthermore, in the reactor melt retention system after a serious accident as described above, the high temperature resistant crucibles on each layer except the bottom layer are provided with flow holes distributed in an array and criss-crossed, and the porous sacrificial The layers are tiled on the upper surface of each layer of high temperature resistant crucible with a thickness of 20-30 cm.

更进一步,如上所述的严重事故后反应堆熔融物堆外滞留系统,其中,所述的耐高温坩埚为盘状结构,中部为平整的收集区,外缘翘起10-30度形成护堰,所述的流通孔设置在耐高温坩埚的中部收集区,相邻两层耐高温坩埚上的流通孔错位布置。Furthermore, in the reactor melt retention system after a serious accident as described above, the high-temperature-resistant crucible has a disc-shaped structure, the middle part is a flat collection area, and the outer edge is tilted by 10-30 degrees to form a weir, The flow holes are arranged in the central collection area of the high-temperature-resistant crucible, and the flow holes on two adjacent layers of high-temperature-resistant crucibles are staggered.

进一步,如上所述的严重事故后反应堆熔融物堆外滞留系统,其中,所述的多孔牺牲层为通过烧结工艺加工而成的海绵体结构,孔隙率0.1-0.3;在多孔牺牲层的中部设有阵列式分布的滞留孔和滞留坑。Further, in the reactor melt retention system after a serious accident as described above, the porous sacrificial layer is a sponge structure processed by a sintering process with a porosity of 0.1-0.3; There are retention holes and retention pits distributed in an array.

进一步,如上所述的严重事故后反应堆熔融物堆外滞留系统,其中,所述的多孔牺牲层的熔化温度为1500-2000℃,所述的耐高温坩埚和耐高温支撑柱的熔化温度在2800℃以上。Furthermore, in the reactor melt retention system after a serious accident as described above, the melting temperature of the porous sacrificial layer is 1500-2000°C, and the melting temperature of the high-temperature-resistant crucible and the high-temperature-resistant support column is 2800°C. ℃ or more.

进一步,如上所述的严重事故后反应堆熔融物堆外滞留系统,其中,所述的冷却管线共设置两列并配备泵阀,分别为堆外注水管线和堆内注水管线;所述的堆外注水管线的出口位于堆坑底部,用于向堆坑内供水;所述的堆内注水管线的出口与压力容器相连,用于向反应堆压力容器内供水。Further, in the reactor melt retention system outside the reactor after a serious accident as described above, the cooling pipelines are arranged in two rows and equipped with pump valves, which are respectively external water injection pipelines and internal reactor water injection pipelines; The outlet of the water pipeline is located at the bottom of the reactor pit, and is used to supply water to the reactor pit; the outlet of the water injection pipeline in the reactor is connected with the pressure vessel, and is used to supply water to the reactor pressure vessel.

更进一步,如上所述的严重事故后反应堆熔融物堆外滞留系统,其中,所述冷却管线提供的冷却剂流经熔融物滞留装置,冷却剂快速渗透进入多孔牺牲层的空隙之中实现冷却功能。Furthermore, in the reactor melt retention system after a severe accident as described above, the coolant provided by the cooling pipeline flows through the melt retention device, and the coolant quickly penetrates into the voids of the porous sacrificial layer to realize the cooling function .

进一步,如上所述的严重事故后反应堆熔融物堆外滞留系统,其中,当堆坑内发生熔融物与冷却剂相互作用,温度与压力超过一定阈值时,配置的堆坑通风系统超压爆破装置将自动爆破泄压,防止堆坑混凝土隔墙出现损坏。Furthermore, in the reactor melt retention system after a serious accident as described above, when the melt interacts with the coolant in the reactor pit and the temperature and pressure exceed a certain threshold, the configured overpressure blasting device of the pit ventilation system will Automatic blasting and pressure relief to prevent damage to the concrete partition wall of the pile pit.

本发明的有益效果如下:(1)本发明设计的盘状耐高温坩埚,可将承接的高温熔融物摊薄,从而增大换热面积,并逐层分摊冷却,减小热流集中的风险;(2)本发明采用多层坩埚通孔错位布置的设计,可有效进行熔融物分流及立体分布;(3)本发明通过两列冷却管线同时对堆内和堆外的熔融物进行冷却,对反应堆熔融物堆外滞留装置,同时实现自下而上的淹没和自上而下的喷淋两种冷却方式,增加了系统的可靠性。The beneficial effects of the present invention are as follows: (1) The disc-shaped high-temperature-resistant crucible designed by the present invention can thin the high-temperature molten material received, thereby increasing the heat exchange area, and sharing the cooling layer by layer, reducing the risk of heat flow concentration; 2) The present invention adopts the design of multi-layer crucible through-hole staggered arrangement, which can effectively divide and distribute the molten material; (3) The present invention simultaneously cools the molten material inside and outside the reactor through two columns of cooling pipelines, and cools the reactor. The retention device outside the melt pile realizes two cooling methods: bottom-up submersion and top-down spraying at the same time, which increases the reliability of the system.

附图说明Description of drawings

图1为反应堆熔融物堆外滞留系统布置图;Figure 1 is a layout diagram of the reactor melt retention system outside the reactor;

图2为熔融物滞留装置结构示意图;Fig. 2 is a structural schematic diagram of a melt retention device;

图3为熔融物滞留装置剖面图(牺牲层、耐高温坩埚通孔位置示意图)。Fig. 3 is a sectional view of the melt retention device (schematic diagram of the position of the sacrificial layer and the through hole of the high temperature resistant crucible).

具体实施方式Detailed ways

下面结合附图和实施例对本发明进行详细的描述。The present invention will be described in detail below in conjunction with the accompanying drawings and embodiments.

本发明提供了一种严重事故后反应堆熔融物堆外滞留系统,其布置结构如图1所示,包括设置在反应堆压力容器5下方堆坑7底部的熔融物滞留装置和两列来自于安全水源的冷却管线1、2。熔融物滞留装置包括多层可允许熔融物和冷却剂穿透的耐高温坩埚9(最底层11除外),在耐高温坩埚9上设置多孔牺牲层8和耐高温支撑柱10等组件,布置于反应堆压力容器5正下方,可以承接反应堆压力容器投影范围内所有落下的熔融物射流。两列冷却管线配备泵阀,均自电站自备的安全水源取水,事故条件下,堆外注水管线2和堆内注水管线1分别向堆坑7和反应堆压力容器5内供水,堆外注水管线2将水自堆坑7底部注入,用于逐渐淹没熔融物滞留装置;堆内注水管线1将水直接注入反应堆压力容器5,用于冷却堆芯以及向熔融物滞留装置顶部提供类似喷淋的冷却形式。当堆坑内发生熔融物与冷却水相互作用,温度与压力超过一定阈值时,配置的堆坑通风系统超压爆破装置3将自动爆破泄压,防止堆坑混凝土隔墙4出现损坏。The present invention provides a reactor melt retention system outside the reactor after a serious accident. The cooling lines 1, 2. The melt retention device includes a multi-layer high-temperature-resistant crucible 9 (except the bottom layer 11) that allows the melt and coolant to penetrate. On the high-temperature-resistant crucible 9, components such as a porous sacrificial layer 8 and a high-temperature-resistant support column 10 are arranged. Directly below the reactor pressure vessel 5 can receive all the molten jets falling within the projected range of the reactor pressure vessel. The two columns of cooling pipelines are equipped with pump valves, both of which take water from the safe water source provided by the power station. Under accident conditions, the external water injection pipeline 2 and the internal reactor water injection pipeline 1 supply water to the reactor pit 7 and the reactor pressure vessel 5 respectively, and the external reactor water injection pipeline 2. Water is injected from the bottom of the reactor pit 7 to gradually submerge the melt retention device; the water injection pipeline 1 in the reactor directly injects water into the reactor pressure vessel 5 for cooling the core and providing a spray-like spray to the top of the melt retention device cooling form. When the melt interacts with the cooling water in the pit and the temperature and pressure exceed a certain threshold, the configured overpressure blasting device 3 of the pit ventilation system will automatically blast and release the pressure to prevent damage to the concrete partition wall 4 of the pit.

本发明所提供的熔融物滞留装置为多层结构,如图2、图3所示,每层结构单元之间由耐高温支撑柱10连接并支撑,相邻两层结构单元之间留有40-60cm的自由空间。多孔牺牲层8的熔化温度1500-2000度,且以20-30cm的厚度平铺在耐高温坩埚9、11上表面;所述的耐高温坩埚8和耐高温支撑柱10的熔化温度在2800度以上,可采用高温陶瓷材料。除最底层以外的每层所述耐高温坩埚9上设有阵列式分布且隔层交错的流通孔12,相邻两层耐高温坩埚上的流通孔12错位布置,位于最底部的耐高温坩埚为无孔坩埚。耐高温坩埚及其上的多孔牺牲层主体形状为盘状结构,外缘翘起10-30度形成护堰,中部为平整的收集区,所述的流通孔12就设置在耐高温坩埚的中部收集区。所述的多孔牺牲层的中部留有阵列式分布的滞留孔13和滞留坑14。多孔牺牲层是通过烧结工艺加工而成,为多孔的海绵体结构,孔隙率0.1-0.3,可以允许冷却剂快速渗透进入多孔牺牲层的海绵体结构空隙之中实现冷却功能。The melt retention device provided by the present invention is a multi-layer structure, as shown in Figure 2 and Figure 3, each layer of structural units is connected and supported by high temperature resistant support columns 10, leaving 40 between adjacent two layers of structural units -60cm free space. The melting temperature of the porous sacrificial layer 8 is 1500-2000 degrees, and it is tiled on the upper surfaces of the high-temperature-resistant crucibles 9 and 11 with a thickness of 20-30 cm; the melting temperature of the high-temperature-resistant crucible 8 and the high-temperature-resistant support column 10 is 2800 degrees Above, high temperature ceramic materials can be used. Each layer of the high-temperature-resistant crucible 9 except the bottom layer is provided with flow holes 12 distributed in an array and interlaced with each other. The flow holes 12 on two adjacent layers of high-temperature-resistant crucibles are arranged in a staggered position. The high-temperature-resistant crucible at the bottom A non-porous crucible. The main body shape of the high temperature resistant crucible and the porous sacrificial layer on it is a disc structure, the outer edge is raised by 10-30 degrees to form a weir, and the middle part is a flat collection area, and the flow hole 12 is set in the middle part of the high temperature resistant crucible collection area. The central part of the porous sacrificial layer has retention holes 13 and retention pits 14 distributed in an array. The porous sacrificial layer is processed by a sintering process and has a porous sponge structure with a porosity of 0.1-0.3, which allows the coolant to quickly penetrate into the pores of the porous sacrificial layer's sponge structure to achieve cooling.

本发明所提供的严重事故后反应堆熔融物堆外滞留系统,发生核电站严重事故时,根据操纵员的指令,冷却系统运行,通过分别向堆内和堆外注水的方式,可以对熔融物形成来自上部和下部的双重冷却,促进其凝固滞留和最终长期冷却。The reactor molten matter retention system outside the reactor after a severe accident provided by the present invention, when a serious nuclear power plant accident occurs, the cooling system operates according to the operator's instructions, and the molten material can be formed by injecting water into the reactor and outside the reactor respectively. The double cooling of the upper and lower parts promotes its solidification retention and eventual long-term cooling.

如图1所示,堆芯熔融物熔穿下封头6后,落入反应堆熔融物堆外滞留装置的顶层滞留单元,高温熔融物在重力作用下,会在盘状的承接装置内摊薄,从而增大换热面积,使得冷却效果和凝固滞留功能更易高效达成。As shown in Figure 1, after the core molten material melts through the lower head 6, it falls into the top layer retention unit of the reactor molten material retention device outside the reactor, and the high-temperature molten material will be diluted in the disc-shaped receiving device under the action of gravity, Thereby increasing the heat exchange area, making the cooling effect and solidification retention function easier to achieve efficiently.

如图2所示,大量的高温熔融物最初落入滞留装置时,首先接触的是多孔牺牲层8,一方面,海绵状的多孔牺牲层8内所渗透的冷却水可以有效的对熔融物降温,促使其凝固结壳,另一方面,在堆积有过量的高温熔融物的局部区域,牺牲层材料(如氧化铁或氧化铝或两者的混合物)会通过自身熔化吸收大量热量,并确保温度低于耐高温坩埚的设计温度以内,确保其结构强度和装置几何形式的完整性。As shown in Figure 2, when a large amount of high-temperature molten material first falls into the retention device, it first contacts the porous sacrificial layer 8. On the one hand, the cooling water permeated in the spongy porous sacrificial layer 8 can effectively cool the molten material. , to promote its solidification crust, on the other hand, in the local area where excessive high-temperature melt is accumulated, the sacrificial layer material (such as iron oxide or aluminum oxide or a mixture of the two) will absorb a large amount of heat by melting itself, and ensure the temperature It is lower than the design temperature of the high temperature crucible to ensure its structural strength and the integrity of the geometric form of the device.

如图3所示,当顶部的牺牲层8被熔穿时,其对应位置的过量熔融物将通过熔穿的孔道流入下一层单元结构的牺牲层之上,第二次被摊平和冷却。由于下层的多孔牺牲层设计有阵列布置的滞留孔13和滞留坑14,熔融物被受控的分配到本层耐高温坩埚9的上方,如果在这一层,仍有局部区域的熔融物不能得到充分冷却和滞留,则对应份额的熔融物会继续熔穿牺牲层8,并沿耐高温坩埚9预设的流通孔12向下一层扩展结构迁移。通过合理设计牺牲层的包覆厚度和耐高温坩埚上通孔的开设位置与直径,借助上下错位的通孔布置方式,每一层堆积过于集中的熔融物都将可控的分摊至下一层,这种多层滞留的设计,既延长了滞留时间,又为热源的三维空间均匀再分布提供了可行途径,通过这种方式,最终可将熔融物安全高效的凝固滞留并提供长期冷却。As shown in FIG. 3 , when the sacrificial layer 8 on the top is melted through, the excess melt at its corresponding position will flow into the sacrificial layer of the next layer of unit structure through the melted channel, and be flattened and cooled for the second time. Since the porous sacrificial layer of the lower layer is designed with retention holes 13 and retention pits 14 arranged in an array, the melt is distributed to the top of the high-temperature-resistant crucible 9 in this layer in a controlled manner. If it is fully cooled and retained, the corresponding portion of the melt will continue to melt through the sacrificial layer 8 and migrate to the next extended structure along the preset flow holes 12 of the high temperature resistant crucible 9 . By rationally designing the cladding thickness of the sacrificial layer and the opening position and diameter of the through-holes on the high-temperature-resistant crucible, with the help of the up-and-down dislocation through-hole arrangement, the molten material accumulated in each layer will be controllably distributed to the next layer , this design of multi-layer retention not only prolongs the residence time, but also provides a feasible way for the uniform redistribution of the heat source in three-dimensional space. In this way, the melt can be solidified and retained safely and efficiently, and long-term cooling can be provided.

此外,在多层滞留装置中,最底层的结构单元配备的耐高温坩埚11为无孔设计,以确保在极端情况下,即使熔融物会突破重重屏障达到最后一层滞留结构单元,仍能被全部包容在所设计的熔融物滞留装置之中,而不会与安全壳的混凝土底板发生相互作用,产生更多安全风险。In addition, in the multi-layer retention device, the high-temperature-resistant crucible 11 equipped with the lowest structural unit is non-porous to ensure that in extreme cases, even if the melt breaks through the barriers and reaches the last layer of the retention structural unit, it can still be absorbed. All contained within the designed melt retention device without interacting with the concrete floor of the containment and creating additional safety risks.

显然,本领域的技术人员可以对本发明进行各种改动和变型而不脱离本发明的精神和范围。这样,倘若对本发明的这些修改和变型属于本发明权利要求及其同等技术的范围之内,则本发明也意图包含这些改动和变型在内。Obviously, those skilled in the art can make various changes and modifications to the present invention without departing from the spirit and scope of the present invention. Thus, if these modifications and variations of the present invention fall within the scope of the claims of the present invention and equivalent technologies, the present invention also intends to include these modifications and variations.

Claims (9)

1. reactor fusant out-pile gaseous-waste holdup system after a kind of major accident, including setting is below reactor pressure vessel (5) The fusant arresting device of reactor pit (7) bottom and cooling line from stand-by water source, the fusant arresting device energy Enough accept all fusant jet streams fallen in reactor pressure vessel (5) drop shadow spread, it is characterised in that: the fusant Arresting device includes the high-temperature crucible (9,11) that multilayer allows fusant and coolant to penetrate, two layers adjacent of high-temperature crucible Between be equipped with connection and supporting role high temperature resistant support column (10), on every layer of high-temperature crucible be equipped with can be melted object The porous sacrificial layer (8) of burn through, the porous sacrificial layer (8) are the cavernous structure being process by sintering process.
2. reactor fusant out-pile gaseous-waste holdup system after major accident as described in claim 1, it is characterised in that: adjacent two There are the free spaces that height is 40-60cm between layer high-temperature crucible.
3. reactor fusant out-pile gaseous-waste holdup system after major accident as described in claim 1, it is characterised in that: remove the bottom The every layer in addition high-temperature crucible (9) is equipped with array distribution and the staggered recirculation hole of interlayer (12), and described is porous Sacrificial layer is laid in the upper surface of every layer of high-temperature crucible with the thickness of 20-30cm.
4. reactor fusant out-pile gaseous-waste holdup system after major accident as claimed in claim 3, it is characterised in that: described is resistance to High-temperature crucibles (9,11) are disk-like structure, and middle part is smooth collecting region, and outer rim tilts 10-30 degree and forms shield weir, the stream The middle part collecting region in high-temperature crucible (9) is arranged in through-hole (12), recirculation hole (12) dislocation on adjacent two layers high-temperature crucible Arrangement.
5. reactor fusant out-pile gaseous-waste holdup system after major accident as described in claim 1, it is characterised in that: described is more The porosity of hole sacrificial layer (8) is 0.1-0.3;The delay hole (13) of array distribution is equipped at the middle part of porous sacrificial layer (8) (14) are cheated with being detained.
6. reactor fusant out-pile gaseous-waste holdup system after major accident as described in claim 1, it is characterised in that: described is more The fusion temperature of hole sacrificial layer (8) is 1500-2000 DEG C, the high-temperature crucible (9,11) and high temperature resistant support column (10) Fusion temperature is at 2800 DEG C or more.
7. reactor fusant out-pile gaseous-waste holdup system, feature exist after major accident as claimed in any one of claims 1 to 6 In: two column are arranged altogether and are equipped with pump valve for the cooling line, respectively waterflood-transmission line (1) in out-pile waterflood-transmission line (2) and heap; The outlet of the out-pile waterflood-transmission line (2) is located at reactor pit (7) bottom, for supplying water into reactor pit (7);Water filling in the heap The outlet of pipeline (1) is connected with pressure vessel (5), for supplying water into reactor pressure vessel (5).
8. reactor fusant out-pile gaseous-waste holdup system after major accident as claimed in claim 7, it is characterised in that: the cooling Through fusant arresting device, coolant rapid osmotic enters among the gap of porous sacrificial layer to be realized the coolant flow that pipeline provides Refrigerating function.
9. reactor fusant out-pile gaseous-waste holdup system after major accident as described in claim 1, it is characterised in that: work as reactor pit (7) fusant occurs in and coolant interacts, when temperature and pressure are more than certain threshold value, the reactor pit ventilating system of configuration is super It presses demolition set (3) by automatic-explosion pressure release, prevents reactor pit concrete partition (4) from damaging.
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