WO2022111436A1 - 用于核电厂严重事故下堆芯熔融物滞留的装置 - Google Patents

用于核电厂严重事故下堆芯熔融物滞留的装置 Download PDF

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WO2022111436A1
WO2022111436A1 PCT/CN2021/132259 CN2021132259W WO2022111436A1 WO 2022111436 A1 WO2022111436 A1 WO 2022111436A1 CN 2021132259 W CN2021132259 W CN 2021132259W WO 2022111436 A1 WO2022111436 A1 WO 2022111436A1
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core melt
melt
nuclear power
retention
inner tube
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PCT/CN2021/132259
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English (en)
French (fr)
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邹文重
于沛
王广飞
赵斌
王晓江
丁亮
姜舒婷
鲁陈林
于明锐
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中国核电工程有限公司
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Publication of WO2022111436A1 publication Critical patent/WO2022111436A1/zh

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    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C9/00—Emergency protection arrangements structurally associated with the reactor, e.g. safety valves provided with pressure equalisation devices
    • G21C9/016—Core catchers
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
    • G21C15/18—Emergency cooling arrangements; Removing shut-down heat
    • Y—GENERAL 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
    • Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00—Energy generation of nuclear origin
    • Y02E30/30—Nuclear fission reactors

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  • the invention belongs to the technical field of nuclear power, and in particular relates to a device used for the retention of core melt under severe accidents in nuclear power plants.
  • nuclear power As a clean energy source, nuclear power has developed rapidly in China in the past 20 years, but nuclear power also has radioactivity risks that other forms of energy do not have.
  • nuclear power There have been three major nuclear accidents in the history of nuclear power development. Among them, the Chernobyl accident in 1986 was very serious, a large amount of radioactive material was released into the environment, and part of the molten material fell into the pit (the raft foundation was not melted through).
  • IVR technology most of the radioactive material can be contained in the pressure vessel without leaking into the containment and the environment.
  • the IVR technology may not be applicable, and an ex-core melt retention (EVR) device is required to retain the core melt in the device to ensure that Radioactive material is not released into the environment due to ground penetration.
  • EMR ex-core melt retention
  • the core melt retention device is beneficial to improve the safety of nuclear power plants.
  • the technical problem to be solved by the present invention is to aim at the above-mentioned deficiencies in the prior art, and to provide a device for the retention of core melt in a serious accident of a nuclear power plant, which has good heat dissipation effect and improves the safety of nuclear reactors.
  • the technical solution adopted to solve the technical problem of the present invention is to provide a device for the retention of core melt in a serious accident of a nuclear power plant, comprising: a ring-shaped crucible for capturing the core melt, the ring-shaped crucible comprising: an inner The tube, the outer tube located outside the inner tube, and the bottom plate connected with the bottom of the inner tube and the outer tube respectively, the inner tube, the outer tube and the bottom plate enclose the accommodating area of the annular crucible.
  • the device for the retention of core melt in a serious accident in a nuclear power plant further comprises: a drainage member disposed on the top of the inner tube, and the drainage member is used for guiding the core melt to the container of the annular crucible. Area.
  • the drainage member is an umbrella-shaped structure
  • the bottom of the drainage member of the umbrella-shaped structure is connected to the top of the inner tube
  • the top of the drainage member of the umbrella-shaped structure is away from the top of the inner tube.
  • the tube height of the inner tube is higher than the tube height of the outer tube, and the tube wall of the inner tube whose height is higher than the outer tube is provided with ventilation holes for ventilation, and the ventilation holes are used to discharge the steam generated by heat absorption.
  • the inner diameter of the inner tube gradually decreases from the bottom to the top, at least two layers of support rings are arranged in the hollow tube body of the inner tube, and the outer diameter of the support rings is smaller than the inner diameter of the inner tube corresponding to the support position.
  • the device for the retention of core melt in a serious accident of a nuclear power plant further comprises: a sacrificial material disposed in the accommodation area, the sacrificial material can react with the core melt, so as to reduce the impact of the core melt on the core.
  • the melt is cooled.
  • the sacrificial material in the containment zone is provided with a dimple capable of receiving the initial core melt.
  • the device for the retention of core melt in a serious accident of a nuclear power plant further comprises: a melt guide groove in a funnel structure, and the melt guide groove is used for the pressure vessel in the reactor pit.
  • the outflowing core melt is guided, the bottom of the melt guide groove is provided with a guide hole, the annular crucible is located in the reactor pit below the melt guide groove, and the device further comprises: for blocking the guide groove.
  • a melt retention plug of the orifice, the melt retention plug being adapted to be melted through by the core melt to allow the core melt to flow out of the orifice and into the holding area of the annular crucible.
  • the device for the retention of core melt in a serious accident in a nuclear power plant further comprises: an inner replacement hot water tank located outside the reactor pit, a cooling pipe in the crucible connected to the inner replacement hot water tank, the crucible The inner cooling pipe is used to feed water to the holding area of the crucible.
  • the device for the retention of core melt in a serious accident in a nuclear power plant further comprises: a reactor pit cold water pipeline connected to the inner displacement hot water tank, and a barrier between the outer wall of the annular crucible and the reactor pit of the reactor where the annular crucible is located.
  • a cooling cavity is formed between the tanks, and the cold water pipeline of the pile pit is used to feed water into the cooling cavity.
  • the device for the retention of core melt in a serious accident of a nuclear power plant further comprises: a compartment arranged in the pit of the reactor where the annular crucible is located, and a high temperature-proof material layer is arranged on the inner wall of the compartment, A steel plate is embedded in the high temperature resistant material layer.
  • the device used in the present invention for the retention of core melt under severe accident of a nuclear power plant is used for external containment and integral cooling of the core melt in a pressure vessel.
  • the invention has the following outstanding advantages: (1) The area/volume ratio of the annular crucible is enhanced in the device of the invention, that is, the heat exchange efficiency is improved, the heat dissipation effect is good, and it is more conducive to the cooling of the core melt and the annular crucible. The integrity is guaranteed, and the safety of the nuclear reactor is improved; (2) the overall structure of the device scheme is simple and does not require a large spreading space. The invention enhances the reliability of the device for core melt retention as a whole.
  • FIG. 1 is a schematic structural diagram of a device for the retention of core melt in a serious accident in a nuclear power plant according to Embodiment 2 of the present invention
  • Fig. 2 is the partial mechanism schematic diagram of the annular crucible in Embodiment 2 of the present invention.
  • Example 3 is a schematic diagram of the melt retention plug retaining core melt in the apparatus of Example 2;
  • Figure 4 is a schematic diagram of the melt retention plug being melted through by the core melt in the device of Example 2;
  • FIG. 5 is a schematic diagram of the sacrificial material being melted in the device of Example 2.
  • This embodiment provides a device for the retention of core melt in a serious accident of a nuclear power plant, including: a ring-shaped crucible for trapping the core melt, the ring-shaped crucible comprising: an inner tube, an outer tube located outside the inner tube The tube, the bottom plate connected with the bottom of the inner tube and the outer tube respectively, the inner tube, the outer tube and the bottom plate enclose the accommodating area of the annular crucible.
  • the device used for the retention of core melt in a serious accident of a nuclear power plant is used for external containment of the core melt and overall cooling of the core melt.
  • This embodiment has the following outstanding advantages: (1) The area/volume ratio of the annular crucible is enhanced in the device of this embodiment, that is, the heat exchange efficiency is improved, the heat dissipation effect is good, and it is more conducive to the cooling of the core melt and the ring-shaped crucible. The integrity of the crucible is guaranteed, and the safety of the nuclear reactor is improved; (2) the overall structure of the device scheme is simple and does not require a large spreading space. This embodiment enhances the reliability of the device for core melt retention as a whole.
  • this embodiment provides a device for the retention of core melt 2 in a serious accident of a nuclear power plant, including: a ring-shaped crucible 4 for trapping the core melt 2 , the ring-shaped crucible 4 includes: an inner tube 8, an outer tube 15 located outside the inner tube 8, a bottom plate 16 connected to the bottom of the inner tube 8 and the outer tube 15 respectively, and the inner tube 8, the outer tube 15, and the bottom plate 16 enclose the annular crucible 4. District 23.
  • the core melt 2 is continuously cooled by the annular crucible 4 to ensure that the core melt 2 stays in the holding area 23 of the annular crucible 4.
  • the hollow structure of the inner tube 8 increases the heat exchange area and enhances heat exchange.
  • the annular crucible 4 increases the heat exchange area, enhances the overall heat exchange of the annular crucible 4, reduces the probability of heat exchange failure at the bottom of the annular crucible 4, and further reduces the possibility of radioactive leakage after a nuclear power plant accident.
  • the bottom plate 16 in this embodiment is formed by extending and connecting the inner tube 8 and the outer tube 15 to the bottom of the area between the inner tube 8 and the outer tube 15 respectively.
  • the device for the retention of core melt 2 in a serious accident of a nuclear power plant further includes: a drainage member 10 arranged on the top of the inner tube 8, and the drainage member 10 is used for draining the core melt 2 to the The receiving area 23 of the annular crucible 4 .
  • the drainage member 10 is an umbrella-shaped structure, the bottom of the drainage member 10 of the umbrella-shaped structure is connected to the top of the inner tube 8 , and the top of the drainage member 10 of the umbrella-shaped structure is away from the top of the inner tube 8 .
  • the tube height of the inner tube 8 is higher than the tube height of the outer tube 15, and the tube wall of the inner tube 8 whose height is higher than the outer tube 15 is provided with a ventilation hole 17 for ventilation, and the ventilation hole 17 is used to generate heat absorption. steam is discharged.
  • the ventilation holes 17 are inclined ventilation holes 17 .
  • the stack pit 5 is provided with an exhaust hole 14 for discharging steam.
  • the inner diameter of the inner tube 8 gradually decreases from the bottom to the top, at least two layers of support rings 6 are arranged in the hollow tube body of the inner tube 8, and the outer diameter of the support rings 6 is smaller than the inner diameter of the inner tube 8 corresponding to the support position.
  • the existence of the support ring 6 improves the strength of the inner tube 8 and ensures the overall integrity of the annular crucible 4 .
  • the support ring 6 improves the overall structural stability of the annular crucible 4 .
  • the device for the retention of the core melt 2 in a serious accident of a nuclear power plant further includes: a sacrificial material 7 arranged in the accommodating area 23 .
  • the sacrificial material 7 is used for reacting with the core melt 2 , cooling the core melt 2 , and changing the fluidity of the core melt 2 .
  • the sacrificial material 7 is any one or more of Fe 2 O 3 , SiO 2 and Al 2 O 3 .
  • the sacrificial material 7 in the accommodating area 23 is provided with a pit 18 .
  • the pit 18 is arranged in the center of the sacrificial material 7 , and the pit 18 is used to receive the initial melt 2 to prevent the melt 2 from overflowing.
  • the umbrella-shaped flow guide 10 plays the role of protecting the inner tube 8 and also plays the role of diverting the core melt 2 to the pit 18 .
  • the device for the retention of core melt 2 in a serious accident of a nuclear power plant further comprises: a melt guide groove 3 in a funnel structure, and the melt guide groove 3 is used to prevent the reactor pit
  • the device further comprises: a melt retention plug 9 for blocking the guide hole 19, the melt retention plug 9 is suitable for being melted through by the core melt 2 to allow the core melt 2 to flow out of the guide
  • the hole 19 flows into the receiving area 23 of the annular crucible 4 .
  • the molten material diversion groove 3 of the funnel structure is formed by splicing a plurality of diverting plates, which can ensure that the core molten material 2 broken at different positions of the pressure vessel 1 can finally be effectively caught and guided to the melting point.
  • Retention plug 9 The melt retention plug 9 is used to retain the core melt 2 initially broken in the pressure vessel 1 to reduce the uncertainty of the core melt 2 flowing out of the pressure vessel 1 in different accidents. After a certain period of time, the melt retention plug 9 is melted through, and the core melt 2 falls into the annular crucible 4 .
  • the device for the retention of the core melt 2 in the serious accident of the nuclear power plant further comprises: an inner displacement hot water tank 11 located outside the reactor pit 5, and an inner displacement hot water tank 11 connected to the inner displacement hot water tank 11.
  • the cooling pipe 20, the cooling pipe 20 in the crucible is used to feed water into the accommodating area 23 of the crucible.
  • a first valve 12 is provided on the cooling pipe 20 in the crucible.
  • the device for the retention of the core melt 2 in the event of a serious accident in a nuclear power plant further includes: a reactor pit cold water pipeline 21 connected to the inner displacement hot water tank 11, and a connection between the outer wall of the annular crucible 4 and the reactor where it is located.
  • a cooling cavity is formed between the compartments 22 in the pile pit 5, and the cold water pipeline 21 of the pile pit is used to feed water into the cooling cavity.
  • a second valve 13 is provided on the cold water pipeline 21 of the heap pit.
  • the device for the retention of the core melt 2 in the event of a serious accident in a nuclear power plant further includes: a compartment 22 arranged in the reactor pit 5 of the reactor where the annular crucible 4 is located, and the inner wall of the compartment 22 is provided with There is a high temperature resistant material layer, and a steel plate is embedded in the high temperature resistant material layer.
  • the melt retention plug 9 is melted through by the core melt 2 , and the umbrella-shaped drainage member 10 will ensure that the melt 2 will not enter the hollow body of the inner tube 8 ,
  • the molten material 2 is guided and slid into the holding area 23 of the annular crucible 4 through the umbrella-shaped flow guide 10, and the molten material 2 starts to react with the sacrificial material 7 in the holding area 23 of the annular crucible 4 and melt the sacrificial material 7,
  • a mixture of the core melt 2 and the sacrificial material 7 is formed, and the temperature of the formed mixture is initially lowered.
  • the mixture begins to melt the sacrificial material 7 in the crucible, at which point the temperature of the mixture decreases further, as shown in FIG. 5 .
  • the sacrificial material 7 is melted, the temperature of the annular crucible 4 is raised, and the outside starts to boil, and steam is generated, and the steam rises to carry away the heat.
  • the existence of the inner tube 8 increases the heat exchange area, can better take away heat, and ensure the integrity of the annular crucible 4 .
  • the steam generated on the wall surface of the inner pipe 8 is discharged through the inclined ventilation holes 17 in the upper part of the inner pipe 8 .
  • annular crucible 4 accommodates the mixture mixed with the upper sacrificial material 7, the mixture reacts with the distributed sacrificial material 7 in the crucible and melts, and the temperature of the mixture is lowered again.
  • the accommodating area 23 of the annular crucible 4 as described above is surrounded by the inner tube 8 , the outer tube 15 , and the bottom plate 16 , and is used as the bottom of the device where the entire core melt 2 stays.
  • a layer of anti-high temperature material is arranged on the inner wall of the compartment 22 where the annular crucible 4 is located, and a layer of steel plate is embedded in the inner layer of the anti-high temperature material to increase its strength.
  • the device for the retention of the core melt 2 generally enhances the nuclear power plant's ability to alleviate serious accidents, reduces the risk of radioactive material being melted through the foundation, and is beneficial to the improvement of the nuclear power plant's safety level.
  • the device used for the retention of the core melt 2 in the serious accident of the nuclear power plant is used for externally containing and integrally cooling the core melt 2 in the pressure vessel 1 .
  • This embodiment has the following outstanding advantages: (1) The area/volume ratio of the annular crucible is enhanced in the device of this embodiment, that is, the heat exchange efficiency is improved, the heat dissipation effect is good, and the cooling of the core melt 2 and the cooling effect are more favorable. The integrity of the annular crucible 4 is guaranteed, and the safety of the nuclear reactor is improved; (2) the overall structure of the device scheme is simple and does not require a large spreading space. This embodiment enhances the reliability of the device for the retention of the core melt 2 as a whole.

Abstract

一种用于核电厂严重事故下堆芯熔融物(2)滞留的装置，包括：用于捕集堆芯熔融物(2)的环状坩埚(4)，环状坩埚(4)包括：内管(8)、位于内管(8)外的外管(15)、分别与内管(8)、外管(15)底部连接的底板(16)，内管(8)、外管(15)、底板(16)围成环状坩埚(4)的容纳区(23)。装置用于对堆芯熔融物(2)进行压力容器(1)外容纳和整体冷却，增强了环状坩埚(4)的面积/体积比，提高了换热效率，散热效果好，有利于堆芯熔融物(2)冷却及环状坩埚(4)完整性的保证，提高了核反应堆安全性。

Description

用于核电厂严重事故下堆芯熔融物滞留的装置
本公开要求申请日为2020年11月26日、申请号为CN 202011344504.7、名称为“用于核电厂严重事故下堆芯熔融物滞留的装置”的中国专利申请的优先权，该申请的全部内容通过引用结合在本公开中。
技术领域
本发明属于核电技术领域，具体涉及一种用于核电厂严重事故下堆芯熔融物滞留的装置。
背景技术
核电作为清洁的能源，中国在过去的20多年来快速发展，但是核电却也存在其它方式的能源不具有的放射性风险。核电发展的史上发生了三次大的核事故。其中，1986年的切尔诺贝利事故十分严重，放射性物质被大量释放到环境中，并且部分熔融物掉入地坑(筏基未被熔穿)。采用熔融物堆内滞留(IVR)技术，放射性物质大部分能被包容在压力容器内，而不会泄漏到安全壳及环境中。对于电功率为1400MW或者更高的1700MW的大堆或者超大堆，IVR技术可能就不能适用了，则需要堆芯熔融物堆外滞留(EVR)装置，将堆芯熔融物滞留在该装置中，确保放射性物质不会因地基熔穿而被释放到环境中。堆芯熔融物滞留装置有利于提高核电厂的安全性。
关于堆芯捕集器的研究，国外起步较早，相关专利较多，如：美国麻省理工大学于1978年的专利，Core catcher for nuclear reactor core meltdown containment(US4113560)，该专利可视为EVR的设计雏形；法国原子能机构于1981年的专利，Core catcher device(US4280872),该专利将EVR技术提升到了工程应用的水平；1982年的专利，Molten core catcher and containment heat removal system(US4,342,621)提出将热管技术用于EVR；美国能源部 1983年的专利，Combination pipe rupture mitigator and in-vessel core catcher(US4,412,969)，首次提出了IVR的概念；此外的相关专利还有Retrofittable nuclear reactor core catcher(US4442065)、Nuclear reactor equipped with a core catcher(US5263066)、Nuclear reactor installation with a core catcher device and method for exterior cooling of the latter by natural circulation(US 5343506)、Core catcher cooling by heat pipe(US6353651)、Core catcher Cooling(US7558360)、Core catcher,manufacturing method thereof,reactor containment vessel and manufacturing method thereof(US8358732)等。中国对堆芯捕集器的研究在从俄罗斯引进WWER核电系统之后逐渐增多，在引进美国AP1000核电技术之后形成了一系列专利，如：俄罗斯2007年在我国申请的专利，损坏的LWR核反应堆的衬层定位和冷却系统(CN200410031091.1)，该专利即为WWER的EVR方案；中核工业二十三建设有限公司2010年在WWER施工过程中形成的专利技术，一种核电站堆芯捕集器的安装方法(CN201010529073.1)；韩国水力原子力株式会社2010年的专利，具有集成冷却通道的堆芯捕集器(CN201080068588.4)，其主旨在于对熔融物覆盖底板的冷却；上海和工程研究设计院在AP1000引进消化吸收及CAP1400设计过程中逐渐形成的EVR技术，底部注水叠加外部冷却的大型非能动核电厂堆芯捕集器(CN201310005308.0)、一种大型非能动压水堆核电厂坩埚型堆芯摧集器(CN201310005342.8)、有熔融物扩展室的大型非能动压水堆核电厂堆芯捕集器(CN201310005579.6)、大型非能动核电厂熔融物堆内和堆外滞留相结合的装置(CN201310264749.2)、有熔融物扩展室的大型非能动压水堆核电厂堆芯捕集器(CN201320007203.4)、一种大型非能动压水堆核电厂堪竭型堆芯捕集器(CN201320007218.0)、大型非能动核电厂熔融物堆内和堆外滞留相结合的装置(CN201320007347.X)、底部注水叠加外部冷却的大型非能动核电厂堆芯捕集器(CN201320007522)。
上述所有堆芯捕集器的散热差，导致核反应堆安全性变差。
发明内容
本发明所要解决的技术问题是针对现有技术中存在的上述不足，提供一种用于核电厂严重事故下堆芯熔融物滞留的装置，散热效果好，提高了核反应堆安全性。
解决本发明技术问题所采用的技术方案是提供一种用于核电厂严重事故下堆芯熔融物滞留的装置，包括：用于捕集堆芯熔融物的环状坩埚，环状坩埚包括：内管、位于内管外的外管、分别与内管、外管底部连接的底板，内管、外管、底板围成环状坩埚的容纳区。
优选的是，所述的用于核电厂严重事故下堆芯熔融物滞留的装置，还包括：设置于内管顶部的引流件，引流件用于将堆芯熔融物引流到环状坩埚的容纳区。
优选的是，引流件为伞状结构，伞状结构的引流件的底部与内管顶部连接，伞状结构的引流件的顶部远离内管顶部。
优选的是，内管的管高高于外管的管高，高度高出外管的内管的管壁上设置有用于通气的通气孔，通气孔用于将吸热产生的蒸汽排出。
优选的是，内管的内径由底部到顶部逐渐变小，内管中空的管体内设置有至少两层支撑环，支撑环的外径小于对应支撑位置的内管的内径。
优选的是，所述的用于核电厂严重事故下堆芯熔融物滞留的装置，还包括：设置于容纳区内的牺牲材料，所述牺牲材料能够与堆芯熔融物反应，以对堆芯熔融物进行降温。
优选的是，容纳区内的牺牲材料上设置有能够承接最初的堆芯熔融物的凹坑。
优选的是，所述的用于核电厂严重事故下堆芯熔融物滞留的装置，还包括：呈漏斗结构的熔融物导流槽，熔融物导流槽用于对反应堆的堆坑内的压力容器流出的堆芯熔融物进行导流，熔融物导流槽的底部设置有导流孔，环状坩埚位于熔融物导流槽的下方的反应堆的堆坑内，所述装置还包括：用于堵塞导流孔的熔融物滞留塞，熔融物滞留塞适于被所述堆芯熔融物熔穿而允 许堆芯熔融物流出导流孔流入环状坩埚的容纳区。
优选的是，所述的用于核电厂严重事故下堆芯熔融物滞留的装置，还包括：位于反应堆的堆坑外的内置换热水箱、与内置换热水箱连接的坩埚内冷却管道，坩埚内冷却管道用于向坩埚的容纳区进水。
优选的是，所述的用于核电厂严重事故下堆芯熔融物滞留的装置，还包括：与内置换热水箱连接的堆坑冷水管道，环状坩埚的外壁与其所在反应堆的堆坑内的隔间之间形成冷却腔，堆坑冷水管道用于向冷却腔进水。
优选的是，所述的用于核电厂严重事故下堆芯熔融物滞留的装置，还包括：设置于环状坩埚所在反应堆的堆坑内的隔间，隔间内壁上设置有防高温材料层，防高温材料层内嵌有钢板。
本发明中的用于核电厂严重事故下堆芯熔融物滞留的装置，用于对堆芯熔融物进行压力容器外容纳和整体冷却。本发明有以下几点突出优势：(1)该发明装置中增强了环状坩埚的面积/体积比，即提高了换热效率，散热效果好，更有利于堆芯熔融物冷却及环状坩埚完整性的保证，提高了核反应堆安全性；(2)该装置方案整体结构简单，不需要较大的铺展空间。该项发明从整体上增强堆芯熔融物滞留的装置的可靠性。
附图说明
图1是本发明实施例2中的用于核电厂严重事故下堆芯熔融物滞留的装置的结构示意图；
图2是本发明实施例2中的环状坩埚的局部机构示意图；
图3是实施例2的装置中的熔融物滞留塞滞留堆芯熔融物的示意图；
图4是实施例2的装置中的熔融物滞留塞被堆芯熔融物熔穿的示意图；
图5是实施例2的装置中的牺牲材料被融化的示意图。
图中：1-压力容器；2-熔融物；3-熔融物导流槽；4-环状坩埚；5-堆坑；6-支撑环；7-牺牲材料；8-内管；9-熔融物滞留塞；10-引流件；11-内置换热水箱；12-第一阀门；13-第二阀门；14-排气孔；15-外管；16-底板；17-通气 孔；18-凹坑；19-导流孔；20-坩埚内冷却管道；21-堆坑冷水管道；22-隔间；23-容纳区。
具体实施方式
为使本领域技术人员更好地理解本公开的技术方案，下面结合附图和实施例对本公开作进一步详细描述。
下面详细描述本专利的实施例，所述实施例的示例在附图中示出，其中自始至终相同或类似的标号表示相同或类似的元件或具有相同或类似功能的元件。下面通过参考附图描述的实施例是示例性的，仅用于解释本专利，而不能理解为对本专利的限制。
实施例1
本实施例提供一种用于核电厂严重事故下堆芯熔融物滞留的装置，包括：用于捕集堆芯熔融物的环状坩埚，环状坩埚包括：内管、位于内管外的外管、分别与内管、外管底部连接的底板，内管、外管、底板围成环状坩埚的容纳区。
本实施例中的用于核电厂严重事故下堆芯熔融物滞留的装置，用于对堆芯熔融物进行压力容器外容纳和整体冷却。本实施例有以下几点突出优势：(1)该实施例装置中增强了环状坩埚的面积/体积比，即提高了换热效率，散热效果好，更有利于堆芯熔融物冷却及环状坩埚完整性的保证，提高了核反应堆安全性；(2)该装置方案整体结构简单，不需要较大的铺展空间。该项实施例从整体上增强堆芯熔融物滞留的装置的可靠性。
实施例2
如图1、2所示，本实施例提供一种用于核电厂严重事故下堆芯熔融物2滞留的装置，包括：用于捕集堆芯熔融物2的环状坩埚4，环状坩埚4包括：内管8、位于内管8外的外管15、分别与内管8、外管15底部连接的底板16， 内管8、外管15、底板16围成环状坩埚4的容纳区23。通过环状坩埚4对堆芯熔融物2提供持续冷却，确保堆芯熔融物2滞留于环状坩埚4的容纳区23，内管8为中空结构增大了换热面积，增强了换热。环状坩埚4增大了换热面积，增强环状坩埚4整体的换热，减少了环状坩埚4底部换热失效的几率，使得核电厂事故后放射性外泄的可能性进一步降低。具体的，本实施例中的底板16由内管8、外管15分别向内管8与外管15之间区域的底部延伸并连接形成。
优选的是，所述的用于核电厂严重事故下堆芯熔融物2滞留的装置，还包括：设置于内管8顶部的引流件10，引流件10用于将堆芯熔融物2引流到环状坩埚4的容纳区23。
优选的是，引流件10为伞状结构，伞状结构的引流件10的底部与内管8顶部连接，伞状结构的引流件10的顶部远离内管8顶部。
优选的是，内管8的管高高于外管15的管高，高度高出外管15的内管8的管壁上设置有用于通气的通气孔17，通气孔17用于将吸热产生的蒸汽排出。通气孔17为倾斜的通气孔17。堆坑5上设置有排气孔14，用于排出蒸汽。
优选的是，内管8的内径由底部到顶部逐渐变小，内管8中空的管体内设置有至少两层支撑环6，支撑环6的外径小于对应支撑位置的内管8的内径。支撑环6的存在提升了内管8的强度，保证了环状坩埚4整体的完整性。支撑环6提高了环状坩埚4整体结构稳定性。
优选的是，所述的用于核电厂严重事故下堆芯熔融物2滞留的装置，还包括：设置于容纳区23内的牺牲材料7。牺牲材料7用于与堆芯熔融物2反应，对堆芯熔融物2进行降温，改变堆芯熔融物2的流动性。牺牲材料7为Fe 2O 3、SiO 2、Al 2O 3中的任意一种或几种。
优选的是，容纳区23内的牺牲材料7上设置有凹坑18。凹坑18设置于牺牲材料7的中心，凹坑18用于承接最初的熔融物2，防止熔融物2旁溢。伞状结构的引流件10起到了保护内管8的作用，同时起到将堆芯熔融物2向凹坑18分流的作用。
优选的是，所述的用于核电厂严重事故下堆芯熔融物2滞留的装置，还包括：呈漏斗结构的熔融物导流槽3，熔融物导流槽3用于对反应堆的堆坑5内的压力容器1流出的堆芯熔融物2进行导流，熔融物导流槽3的底部设置有导流孔19，环状坩埚4位于熔融物导流槽3的下方的反应堆的堆坑5内，所述装置还包括：用于堵塞导流孔19的熔融物滞留塞9，熔融物滞留塞9适于被所述堆芯熔融物2熔穿而允许堆芯熔融物2流出导流孔19流入环状坩埚4的容纳区23。
漏斗结构的熔融物导流槽3由多块导流板分块拼接而成，能保证压力容器1不同位置破口的堆芯熔融物2最终都能被有效的接住，并导流至熔融物滞留塞9。熔融物滞留塞9用于将最初压力容器1破口的堆芯熔融物2进行滞留，降低不同事故堆芯熔融物2流出压力容器1的不确定性。在一定时间之后，熔融物滞留塞9被熔穿，堆芯熔融物2跌落至环状坩埚4内。
优选的是，所述的用于核电厂严重事故下堆芯熔融物2滞留的装置，还包括：位于反应堆的堆坑5外的内置换热水箱11、与内置换热水箱11连接的坩埚内冷却管道20，坩埚内冷却管道20用于向坩埚的容纳区23进水。坩埚内冷却管道20上设置有第一阀门12。
优选的是，所述的用于核电厂严重事故下堆芯熔融物2滞留的装置，还包括：与内置换热水箱11连接的堆坑冷水管道21，环状坩埚4的外壁与其所在反应堆的堆坑5内的隔间22之间形成冷却腔，堆坑冷水管道21用于向冷却腔进水。堆坑冷水管道21上设置有第二阀门13。
优选的是，所述的用于核电厂严重事故下堆芯熔融物2滞留的装置，还包括：设置于环状坩埚4所在反应堆的堆坑5内的隔间22，隔间22内壁上设置有防高温材料层，防高温材料层内嵌有钢板。
核电厂严重事故下，堆芯熔融物2滞留的装置的工作过程如下：
首先，如图3所示，在压力容器1的下封头水蒸干，且IVR(压力容器1内熔融物2的冷却与保持)失效的情况下，熔融物2开始从下封头漏出，由熔融物导流槽3导引，并被熔融物滞留塞9滞留。在事故进入到一定程度，如图4所示，熔融物滞留塞9被堆芯熔融物2熔穿，伞状结构的引流件10将 保证熔融物2不会进入内管8中空的管体内，熔融物2通过伞状结构的引流件10引导滑落至环状坩埚4的容纳区23中，熔融物2开始与环状坩埚4的容纳区23内的牺牲材料7进行反应并熔化牺牲材料7，形成堆芯熔融物2与牺牲材料7的混合物，这时形成的混合物温度初步下降。混合物开始融化坩埚内的牺牲材料7，这时混合物温度进一步降低，如图5所示。
然后，由于牺牲材料7被熔化，环状坩埚4升温，外部开始沸腾，产生蒸汽，蒸汽上升，带走热量。另外内管8的存在，增大了换热面积，能更好的带走热量，保证环状坩埚4的完整性。内管8壁面产生的蒸汽，通过内管8上部的倾斜的通气孔17排出。
进一步，这时环状坩埚4所处位置有内置换热水箱11进水，淹没深度坩埚深度约为3.5m。
进一步，如上所述的环状坩埚4容纳与上部牺牲材料7混合后的混合物，混合物与坩埚内的分布式牺牲材料7反应并熔化，混合物温度再度被降低。
进一步，如上所述的环状坩埚4的容纳区23由内管8、外管15、底板16围成，用于作为整个堆芯熔融物2滞留的装置的底部。
进一步，环状坩埚4所在隔间22内壁布置一层防高温材料，防高温材料内层嵌一层钢板，增加其强度。
堆芯熔融物2滞留的装置从总体上增强了核电厂缓解严重事故的能力，降低了放射性物质因地基被熔穿的风险，有利于核电厂安全水平的提高。
本实施例中的用于核电厂严重事故下堆芯熔融物2滞留的装置，用于对堆芯熔融物2进行压力容器1外容纳和整体冷却。本实施例有以下几点突出优势：(1)该实施例装置中增强了环状坩埚的面积/体积比，即提高了换热效率，散热效果好，更有利于堆芯熔融物2冷却及环状坩埚4完整性的保证，提高了核反应堆安全性；(2)该装置方案整体结构简单，不需要较大的铺展空间。该项实施例从整体上增强堆芯熔融物2滞留的装置的可靠性。
可以理解的是，以上实施方式仅仅是为了说明本发明的原理而采用的示例性实施方式，然而本发明并不局限于此。对于本领域内的普通技术人员而 言，在不脱离本发明的精神和实质的情况下，可以做出各种变型和改进，这些变型和改进也视为本发明的保护范围。

Claims (11)

  1. 一种用于核电厂严重事故下堆芯熔融物滞留的装置，其特征在于，包括：用于捕集堆芯熔融物的环状坩埚，环状坩埚包括：内管、位于内管外的外管、分别与内管、外管底部连接的底板，内管、外管、底板围成环状坩埚的容纳区。
  2. 根据权利要求1所述的用于核电厂严重事故下堆芯熔融物滞留的装置，其特征在于，还包括：设置于内管顶部的引流件，引流件用于将堆芯熔融物引流到环状坩埚的容纳区。
  3. 根据权利要求2所述的用于核电厂严重事故下堆芯熔融物滞留的装置，其特征在于，引流件为伞状结构，伞状结构的引流件的底部与内管顶部连接，伞状结构的引流件的顶部远离内管顶部。
  4. 根据权利要求1～3任意一项所述的用于核电厂严重事故下堆芯熔融物滞留的装置，其特征在于，内管的管高高于外管的管高，高度高出外管的内管的管壁上设置有用于通气的通气孔，通气孔用于将吸热产生的蒸汽排出。
  5. 根据权利要求1所述的用于核电厂严重事故下堆芯熔融物滞留的装置，其特征在于，内管的内径由底部到顶部逐渐变小，内管中空的管体内设置有至少两层支撑环，支撑环的外径小于对应支撑位置的内管的内径。
  6. 根据权利要求1～3、5任意一项所述的用于核电厂严重事故下堆芯熔融物滞留的装置，其特征在于，还包括：设置于容纳区内的牺牲材料，所述牺牲材料能够与堆芯熔融物反应，以对堆芯熔融物进行降温。
  7. 根据权利要求6所述的用于核电厂严重事故下堆芯熔融物滞留的装 置，其特征在于，容纳区内的牺牲材料上设置有能够承接最初的堆芯熔融物的凹坑。
  8. 根据权利要求1～3、5、7任意一项所述的用于核电厂严重事故下堆芯熔融物滞留的装置，其特征在于，还包括：呈漏斗结构的熔融物导流槽，熔融物导流槽用于对反应堆的堆坑内的压力容器流出的堆芯熔融物进行导流，熔融物导流槽的底部设置有导流孔，环状坩埚位于熔融物导流槽的下方的反应堆的堆坑内，所述装置还包括：用于堵塞导流孔的熔融物滞留塞，熔融物滞留塞适于被所述堆芯熔融物熔穿而允许堆芯熔融物流出导流孔流入环状坩埚的容纳区。
  9. 根据权利要求8所述的用于核电厂严重事故下堆芯熔融物滞留的装置，其特征在于，还包括：位于反应堆的堆坑外的内置换热水箱、与内置换热水箱连接的坩埚内冷却管道，坩埚内冷却管道用于向坩埚的容纳区进水。
  10. 根据权利要求9所述的用于核电厂严重事故下堆芯熔融物滞留的装置，其特征在于，还包括：与内置换热水箱连接的堆坑冷水管道，环状坩埚的外壁与其所在反应堆的堆坑内的隔间之间形成冷却腔，堆坑冷水管道用于向冷却腔进水。
  11. 根据权利要求1～3、5、7、9、10任意一项所述的用于核电厂严重事故下堆芯熔融物滞留的装置，其特征在于，还包括：设置于环状坩埚所在反应堆的堆坑内的隔间，隔间内壁上设置有防高温材料层，防高温材料层内嵌有钢板。
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