WO2015188697A1 - 地下核电站放射性废水地下迁移防护系统 - Google Patents

地下核电站放射性废水地下迁移防护系统 Download PDF

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WO2015188697A1
WO2015188697A1 PCT/CN2015/079888 CN2015079888W WO2015188697A1 WO 2015188697 A1 WO2015188697 A1 WO 2015188697A1 CN 2015079888 W CN2015079888 W CN 2015079888W WO 2015188697 A1 WO2015188697 A1 WO 2015188697A1
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underground
layer
rock mass
nuclear power
water
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PCT/CN2015/079888
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English (en)
French (fr)
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钮新强
李洪斌
周述达
施华堂
韩前龙
徐年丰
何杰
鱼维娜
苏利军
房艳国
Original Assignee
长江勘测规划设计研究有限责任公司
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Priority claimed from CN201420318038.9U external-priority patent/CN203960913U/zh
Priority claimed from CN201410264273.7A external-priority patent/CN104060632B/zh
Application filed by 长江勘测规划设计研究有限责任公司 filed Critical 长江勘测规划设计研究有限责任公司
Priority to JP2017517170A priority Critical patent/JP2017524951A/ja
Priority to RU2017100889A priority patent/RU2648364C1/ru
Publication of WO2015188697A1 publication Critical patent/WO2015188697A1/zh
Priority to US15/376,635 priority patent/US10373720B2/en

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    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
    • G21F7/00—Shielded cells or rooms
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C13/00—Pressure vessels; Containment vessels; Containment in general
    • G21C13/08—Vessels characterised by the material; Selection of materials for pressure vessels
    • E—FIXED CONSTRUCTIONS
    • E02—HYDRAULIC ENGINEERING; FOUNDATIONS; SOIL SHIFTING
    • E02D—FOUNDATIONS; EXCAVATIONS; EMBANKMENTS; UNDERGROUND OR UNDERWATER STRUCTURES
    • E02D31/00—Protective arrangements for foundations or foundation structures; Ground foundation measures for protecting the soil or the subsoil water, e.g. preventing or counteracting oil pollution
    • E—FIXED CONSTRUCTIONS
    • E02—HYDRAULIC ENGINEERING; FOUNDATIONS; SOIL SHIFTING
    • E02D—FOUNDATIONS; EXCAVATIONS; EMBANKMENTS; UNDERGROUND OR UNDERWATER STRUCTURES
    • E02D29/00—Independent underground or underwater structures; Retaining walls
    • E02D29/045—Underground structures, e.g. tunnels or galleries, built in the open air or by methods involving disturbance of the ground surface all along the location line; Methods of making them
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C11/00—Shielding structurally associated with the reactor
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C13/00—Pressure vessels; Containment vessels; Containment in general
    • G21C13/08—Vessels characterised by the material; Selection of materials for pressure vessels
    • G21C13/093—Concrete vessels
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
    • G21F1/00—Shielding characterised by the composition of the materials
    • G21F1/02—Selection of uniform shielding materials
    • G21F1/04—Concretes; Other hydraulic hardening materials
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
    • G21F9/00—Treating radioactively contaminated material; Decontamination arrangements therefor
    • G21F9/04—Treating liquids
    • G21F9/20—Disposal of liquid waste
    • G21F9/22—Disposal of liquid waste by storage in a tank or other container
    • 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

Definitions

  • the invention relates to an underground nuclear power plant safety system, in particular to an underground nuclear power station radioactive wastewater underground migration protection system.
  • HSD101/06 Nuclear Power Plant Site Selection and Hydrogeology
  • HSD101/05 Hydrogeology
  • the migration of radionuclides in the ground is affected by groundwater. Movement (transport), propagation of pollution peaks (hydraulic dispersion), retention and release of radionuclides in the solid phase (interphase distribution).
  • the carrier medium to be transported is groundwater. Therefore, through engineering measures, blocking the movement of groundwater can protect the underground migration of radioactive wastewater containing nuclide.
  • radioactive wastewater In the case of serious accidents such as the collapse of the containment of the underground nuclear power plant, the internal radioactive waste water will migrate to the rock mass outside the reactor cavity, polluting the groundwater body and causing significant environmental pollution.
  • the underground migration of radioactive wastewater includes complex processes such as groundwater transportation, hydraulic dispersion and interphase distribution. There are many factors affecting the underground migration of radioactive wastewater, including the location of the source of the accident, the characteristics of the rock mass, the type of groundwater, and the migration route. Therefore, it is necessary to establish a corresponding protection system to avoid the impact of underground nuclear power plant radioactive wastewater migration.
  • the underground nuclear waste disposal site that has been built is generally disposed of by separating the nuclear waste steel can and sealing the outer layer of clay and placing it in the deep hole of the rock mass.
  • the migration protection of the underground nuclear power plant is very different in the layout of the building. Poor reference.
  • the underground migration of radioactive wastewater is not only complicated, but also has high protection requirements. It is difficult to ensure protection and safety by a single means. Multiple protection arrangements must be considered to ensure that the underground migration of radioactive wastewater is under controlled disposal in the event of a nuclear accident.
  • the invention provides an underground migration protection system for radioactive waste water of an underground nuclear power station with high efficiency and multiple protections for the situation that underground radioactive power plants may migrate outward under severe accident conditions.
  • the underground nuclear power station underground migration protection system designed by the present invention is special in that it includes: a reactor cavern protective layer and a nuclear island peripheral total protection, and the reactor cavity protection layer includes a surrounding reactor cavity An inner lining layer for preventing internal water extravasation, a water permeable concentrated drainage layer having a concentrated hydrophobic function, and a rock mass fissure filling and permeable layer; the total protection of the outer periphery of the nuclear island is disposed at the nuclear island (reactor cavity and auxiliary cavern)
  • the outer periphery of the co-constructed underground caverns consists of a water-repellent layer that blocks the groundwater of natural rock masses.
  • the rock mass fissure filling and isolating layer comprises an inner rock mass fissure filling layer and an outer rock mass fissure filling layer.
  • the protective layer of the reactor cavity is an inner liner layer, an inner rock body fissure filling layer, a water seepage concentrated drainage layer and an outer rock mass fissure filling layer from the inside to the outside.
  • the inner liner layer is composed of a reinforced concrete structure or a reinforced concrete plus waterproof plate.
  • the inner lining layer serves as a sealing function to avoid leakage of the reactor cavity into the outer rock mass after charging the cooling water under severe accident conditions.
  • the concrete is concrete with a high degree of impermeability.
  • the inner rock fissure filling layer and the outer rock mass fissure filling layer are both composed of grouting material and rock mass itself in the rock mass fissure.
  • the inner rock fissure filling layer is located in the cave wall and surrounding rock of the reactor cavity, which further enhances the seepage prevention of the cave wall and surrounding rock.
  • the outer rock mass fissure filling layer plays the role of groundwater hydraulic exchange between the rock mass of the barrier cavern group and the surrounding rock mass of the reactor building.
  • the water-distributing concentrated drainage layer is composed of a plurality of drainage holes and drainage holes that are vertically overlapped in the holes.
  • the water seepage and concentration layer can make the micro-seepage after the inner liner and the inner rock fissure filling layer which may occur under severe accident conditions be concentrated and discharged in the protection zone.
  • the drainage hole spacing should be less than 2m.
  • the peripheral total protective water-repellent layer is composed of a plurality of drainage holes and drainage holes which are drilled up and down in the holes.
  • the water-repellent layer can block the leakage of natural groundwater into the underground cavern group, reduce the groundwater seepage pressure, ensure the stability of the surrounding rock of the cavern, and block the hydraulic connection inside and outside the underground cavern group, so that the underground cavern group is in the rock mass Area.
  • the invention has the advantages that the underground nuclear power station has the characteristics of underground migration of radioactive waste water under severe accidents, and the protection of the reactor cavity is emphasized, and the inner protective layer, the water seepage and drainage layer and the rock mass crack are designed in combination with the natural protective performance of the rock mass.
  • the filling layer fully blocks the passage of underground migration of radioactive waste water, and sets up a collection, disposal and monitoring system. Radioactive waste water that may be generated during normal operation of nuclear power, especially in serious accidents, is intercepted in the engineering protection zone. Collection and disposal to prevent the possibility of large-scale radioactive material migration in order to comply with national nuclear safety related standards.
  • Figure 1 is a schematic view showing the structure of a underground migration protection system for radioactive waste water from underground nuclear power plants.
  • Fig. 2 is a contour diagram (unit: m) of the water head of the seepage field in the protection system shown in Fig. 1 under simulated working condition 1, working condition 2 and working condition 3.
  • Figure 3 is a contour diagram (unit: m) of the head of the seepage field of the protection system shown in Figure 1 under simulated condition 4.
  • reactor layer protective layer S inner lining S 1 , rock mass fissure filling layer S 2 , inner rock mass fissure filling layer S 2-1 , outer rock mass fissure filling layer S 2-2 , water seepage concentration Layer S 3 , drainage hole S 3-1 , drainage hole S 3-2 , total protective water barrier Z around the nuclear island, drainage hole Z 1 , drainage hole Z 2 , centralized treatment of seepage water A, monitoring point B, inspection, Transmission and report visualization system C.
  • the tunnel protection layer S includes an inner liner S 1 surrounding the reactor cavity with internal water leakage prevention, a water seepage and drainage layer S 3 having a concentrated hydrophobic function, and a rock mass fracture layer S 2 , wherein the rock mass crack
  • the filling layer S 2 includes an inner rock fissure filling layer S 2-1 and an outer rock mass fissure filling layer S 2-2 , and a nuclear island peripheral total protective Z is disposed at a periphery of the underground cavern group formed by the reactor cavity and the auxiliary cavern. .
  • the reactor building completely retains all nuclear safety protection measures for the ground nuclear power plant, that is, the original monitoring, collection, storage and disposal facilities are kept inside the containment and outside the containment, and monitoring and special discharge facilities are set at the discharge point.
  • the radioactive waste water of the underground nuclear power station mainly comes from the extravasation of the reactor building under severe accident conditions. For this reason, the protection of the reactor building caverns is based on the safety protection measures of the ground nuclear power plant.
  • the specific structure of the four levels of protective measures is as follows: Shown as follows:
  • the inner lining layer S 1 is disposed on the inner wall of the reactor building, and the inner lining layer S 1 is composed of a high-impregnity reinforced concrete lining layer, wherein the thickness of the lining concrete of the top arch and the surrounding circle is initially set to 0.5 m to 1 m; The thickness can be appropriately thickened as needed.
  • the lining concrete is impervious to grade W12 and has a permeability coefficient of about 1.3 ⁇ 10 -9 cm/s. At the same time, all surrounding rock cracks in the reactor wall of the reactor building are closed by high-impregnated material quilting.
  • the lining concrete with impermeability rating of W12 is resistant to 120m head pressure without concrete seepage.
  • the world's highest Shuibuya concrete face rockfill dam has a maximum dam height of 233m.
  • the dam body is completely reliant on concrete slabs.
  • the impermeability rating of this slab is W12, and its maximum thickness is only 1.1m. It has been in operation for many years and no abnormalities have occurred.
  • the cavern can be filled with water and cooled. According to the water filling depth of about 20m, it is far lower than the water head on the slab of the Shuibuya dam.
  • the analogy is that the impermeability is obvious.
  • Grade W12 lining concrete can effectively prevent the occurrence of extravasation after the reactor cavity is filled with cooling water.
  • the inner lining layer S 1 is provided with an inner rock mass fissure filling layer S 2-1 , and the inner rock mass fissure filling layer S 2-1 is a high-density grouting for the surrounding rock of the reactor building wall wall, and the rock mass gap is closed, so that The rock mass and the grouting material together form a closed layer, which further improves the integrity and impermeability of the surrounding rock of the cave wall, and the comprehensive anti-seepage performance of the rock mass in the closed area reaches 10 -6 cm/s.
  • the grouting hole spacing is initially set at 1m ⁇ 1m ⁇ 2m ⁇ 2m, and the treatment depth is 8m ⁇ 12m.
  • a passive water-distributing layer S 3 capable of self-hydrophobicity is disposed on the periphery of the fractured-filled layer S 2-1 of the inner rock body, and the water-distributing layer S 3 is composed of multiple layers.
  • the drainage hole and the drainage hole in the upper and lower sides of the hole are formed, and the distance between the drainage holes is initially set at 1 m to 2 m.
  • an outer rock mass fissure filling layer S 2-2 is arranged on the periphery of the seepage drainage layer S 3 , and the outer rock mass fissure filling layer S 2-2 is passed through the multi-layer grouting.
  • the flat hole and the curtain hole which are drilled up and down in the hole are filled and grouted to seal the rock mass crack, and the rock mass and the grout together form a closed layer.
  • the curtain standard is controlled at the highest level of current grouting process of 0.5Lu, and the permeability coefficient is equivalent to about 5 ⁇ 10 -6 cm/s.
  • the water curtains were initially arranged in a single row with a hole spacing of 2 m. According to the grouting test and the anti-seepage effect check, it can also be arranged in multiple rows, and the hole pitch can be further reduced.
  • the combined effect of the inner lining layer S 1 and the inner rock mass fracture filling layer S 2-1 can make the seepage prevention performance of the reactor wall of the reactor plant reach the order of 10 -9 cm/s, and basically block serious accident conditions.
  • the internal water infiltration of the reactor building after charging cooling water; the water seepage and drainage layer S 3 is concentrated on the possible distribution of trace extravasation wastewater to ensure the controlled collection and disposal of radioactive wastewater; the outer rock mass fracture layer S 2- 2
  • the role of the groundwater hydraulic exchange between the rock mass of the barrier cavern group and the surrounding rock mass of the reactor building Under severe accident conditions, it not only blocks the infiltration of external water, but also blocks the trace amount of radioactive waste water in the set area, further improving Protection against serious accidents.
  • the total protective water barrier Z around the nuclear island is to block the leakage of groundwater from the natural rock mass to the underground cavern group, reduce the groundwater seepage pressure, ensure the stability of the surrounding rock of the cavern, and block the hydraulic connection inside and outside the underground cavern group. So that the underground cavern group is in the rock mass dewatering area.
  • the peripheral total protective water-repellent layer Z is disposed about 25m away from the cavern group, and is composed of a multi-layer drainage hole Z 2 and a drainage hole Z 1 which is drilled up and down in the hole, and the spacing of the drainage hole Z 1 is initially determined. It is 1m ⁇ 2m, the entire peripheral total protective water barrier Z is fully enclosed.
  • monitoring points B are arranged in multiple areas of the underground nuclear power plant underground migration protection system.
  • the monitoring points are holes or holes, and the inspection, transmission and report visualization system C is installed at the monitoring points. Real-time control of the state of groundwater and the degree of radioactivity, and take corresponding measures according to the monitoring situation.
  • the above design and arrangement form the inner lining layer S 1 of the underground nuclear power station from the center of the reactor cavity to the outer rock mass, the inner rock mass fissure filling layer S 2-1 , the seepage and drainage layer S 3 , and the outer rock mass fissure filling layer S
  • the multi-channel safety barrier of 2-2 makes full use of the protective performance of underground nuclear power natural rock mass. Under severe accident conditions, that is, the containment is damaged, the pile is piled up, and the underground reactor building part is filled with cooling water, it may leak. The radioactive waste water is sealed in the key protection zone and controlled to release after reaching safety standards, effectively preventing the underground migration and extravasation of radioactive wastewater.
  • the quasi-three-dimensional model of equivalent continuous porous fracture media was established by underground nuclear power plant simulation site to analyze the effect of protective measures.
  • the role of the inner liner S1 (as a safety reserve) is not considered under seismic conditions.
  • the calculation conditions include: 1 normal operating conditions; 2 design basis accident conditions; 3 severe accident conditions caused by non-earthquakes (safety shell rupture, to prevent melting, the cave interior is filled with cooling water 20m deep); Serious accident conditions, etc.
  • a small local area near the reactor cavity is formed in the large dewatering area of the cavern group. Seepage field, but the small seepage field has no hydraulic connection with the surrounding seepage field (see Figure 3), and the radioactive wastewater released from the reactor cavity to the surrounding rock mass is only 0.60m 3 /h, which is blocked and drained by the water curtain in the reactor cavity.
  • the curtain drainage and through the special collection and treatment system can make the micro-released radioactive waste water controlled in the protection zone, prevent the possibility of large-scale migration of radioactive wastewater in the underground, and conform to the concept of nuclear power safety multi-layer defense.

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Abstract

一种地下核电站放射性废水地下迁移防护系统，包括反应堆洞室防护层（S）和具有阻隔天然岩体地下水作用的核岛外围总防护隔水层（Z），反应堆洞室防护层（S）包括围绕反应堆洞室的具有防止内水外渗的内衬层（S1）、具有集中疏水功能的渗水集中疏排层（S3）和岩体裂隙充填层（S2），外围总防护隔水层（Z）设置在反应堆洞室和辅助洞室共同组成的地下洞室群外围。

Description

地下核电站放射性废水地下迁移防护系统 技术领域
本发明涉及地下核电站安全系统，具体指一种地下核电站放射性废水地下迁移防护系统。
技术背景
根据国家核安全局《核电厂厂址选择与水文地质的关系》(HAD101/06)及《核电厂厂址中放射性物质水力弥散问题》(HAD101/05)准则，放射性核素在地下的迁移是受地下水运动(输送)、污染峰的传播(水力弥散)、固相中放射性核素的滞留和释放(相间分布)控制的。核素在地下水输送、水力弥散及相间分布等不同迁移过程中，迁移的载体介质均是地下水。因此，通过工程措施，阻断地下水的运动即可对含核素的放射性废水地下迁移起到防护作用。地下核电站如发生安全壳破裂等严重事故工况，内部放射性废水将会向反应堆洞室外部岩体迁移，污染地下水体，造成重大环境污染。放射性废水地下迁移包括地下水输送、水力弥散及相间分布等复杂过程，影响放射性废水地下迁移的因素众多，涉及事故源点的位置、岩体特征、地下水类型、迁移途径等。因此，需要建立相应的防护系统，避免地下核电站放射性废水在地下迁移带来的影响。
目前，国内外尚无投入商业运行的大型地下核电站，相应的地下核电站放射性废水地下迁移防护系统研究属于全新的技术领域。已建的地下核废料处置场一般通过将核废料钢罐密封、外覆粘土等隔离层并置于岩体深洞井中处置，与地下核电站的迁移防护在建筑物布置上存在很大差异，可借鉴性差。此外，放射性废水地下迁移不仅影响因素复杂，而且防护要求极高，单一的手段难以确保防护安全，必须综合考虑多重防护布置形式，以确保发生核事故时，放射性废水地下迁移处于受控处置状态。
发明内容
本发明针对地下核电站在严重事故状态下放射性废水可能向外迁移的状况，提供一种具有高效、多重防护的地下核电站放射性废水地下迁移防护系统。
经过创新研发，结合核电技术与地下岩体工程渗控技术，对地下核电站严重事故工 况下的放射性废水地下迁移防护布置形式与措施进行分析，创新的将水电站工程的渗流控制措施应用于地下核电站放射性废水地下迁移防护中，综合设置地下核电站放射性废水地下迁移多重防护措施。
为了实现上述目的，本发明所设计的地下核电站放射性废水地下迁移防护系统，其特殊之处在于：包括反应堆洞室防护层和核岛外围总防护，所述反应堆洞室防护层包括围绕反应堆洞室的具有防止内水外渗的内衬层、具有集中疏水功能的渗水集中疏排层和岩体裂隙充填隔渗层；所述核岛外围总防护设置在核岛(反应堆洞室和辅助洞室共同组成的地下洞室群)外围，由起阻隔天然岩体地下水作用的隔水层构成。其中，所述岩体裂隙充填隔渗层包括内岩体裂隙充填层和外岩体裂隙充填层。
优选地，所述的反应堆洞室防护层由内往外依次是内衬层、内岩体裂隙充填层、渗水集中疏排层和外岩体裂隙充填层。
进一步地，所述内衬层由钢筋混凝土结构构成或钢筋混凝土加防水板材综合构成。内衬层起封闭作用，避免严重事故工况下反应堆洞室充冷却水后向外部岩体渗漏的可能。为了使此结构具有更高的防渗性，所述混凝土为具有高防渗等级的混凝土。
更进一步地，所述内岩体裂隙充填层和外岩体裂隙充填层均由岩体裂隙内的灌浆物和岩体本身构成。内岩体裂隙充填层位于反应堆洞室洞壁及围岩部位，进一步增强洞壁及围岩的防渗性。外岩体裂隙充填层起阻隔洞室群岩体与反应堆厂房洞室周岩体地下水水力交换的作用。
再进一步地，所述渗水集中疏排层由多层排水洞及洞内钻设的上下相互搭接的排水孔组成。渗水集中疏排层使严重事故工况下可能发生的经内衬层、内岩体裂隙充填层后的微量渗水在防护区内集中疏排。为了保证疏排效果，所述排水孔间隔应小于2m。
再进一步地，所述外围总防护隔水层由多层排水洞及洞内钻设的上下相互搭接的排水孔组成。隔水层可阻隔天然地下水向地下洞室群的渗漏，降低地下水渗压，保证洞室的围岩稳定，并阻隔地下洞室群内外的水力联系，使地下洞室群处于岩体疏干区。
本发明的优点在于：针对地下核电站在严重事故下放射性废水地下迁移的特点，重点对反应堆洞室进行防护，结合岩体的天然防护性能设计有内衬层、渗水集中疏排层和岩体裂隙充填层，充分的隔断放射性废水地下迁移的通道，并设收集、处置、监测系统。对核电正常运行、特别是在严重事故下可能产生的放射性废水在工程防护区内进行拦截、 收集与处置，防止大规模放射性物质迁移的可能性，以符合国家核安全相关标准。
附图说明
图1为一种地下核电站放射性废水地下迁移防护系统的结构示意图。
图2为图1所示防护系统在模拟工况1、工况2、工况3下渗流场水头等值线分布图(单位：m)。
图3为图1所示防护系统在模拟工况4下渗流场水头等值线分布图(单位：m)。
图中：反应堆洞室防护层S，内衬层S1，岩体裂隙充填层S2，内岩体裂隙充填层S2-1，外岩体裂隙充填层S2-2，渗水集中疏排层S3，排水孔S3-1，排水洞S3-2，核岛外围总防护隔水层Z，排水孔Z1，排水洞Z2，集中处理收集渗水A，监测点B，检、传、报可视化系统C。
具体实施方式
下面结合附图和具体实例对本发明作进一步的详细描述：
图1中所示的地下核电站放射性废水地下迁移防护系统，包括反应堆洞室防护层S和具有阻隔天然岩体地下水作用的核岛外围总防护隔水层Z，各防护层均为封闭结构，反应堆洞室防护层S包括围绕反应堆洞室的具有防止内水外渗的内衬层S1、具有集中疏水功能的渗水集中疏排层S3和岩体裂隙充填层S2，其中，岩体裂隙充填层S2包括内岩体裂隙充填层S2-1和外岩体裂隙充填层S2-2，核岛外围总防护Z设置在反应堆洞室和辅助洞室共同组成的地下洞室群外围。
反应堆厂房完全保留地面核电站所有核安全防护措施，即在安全壳内及安全壳外部保留原监控、收集、贮存和处置设施，在排放点设置监控及专用排放设施等。地下核电站放射性废水主要来源于反应堆厂房在严重事故工况下的外渗，为此，针对反应堆厂房洞室在保留地面核电站安全防护措施的基础上重点加强防护，四个层次的防护措施具体结构如下所示：
1)高性能洞壁防护区，即内衬层S1：
内衬层S1设置在反应堆厂房洞室内壁，内衬层S1由高防渗性钢筋混凝衬砌层构成，其中，顶拱及周圈衬砌混凝土厚度初定0.5m～1m；底板衬砌混凝土厚度可根据需要适当 加厚。衬砌混凝土为抗渗等级W12，渗透系数约1.3×10-9cm/s。同时，对反应堆厂房洞壁所有围岩裂隙采用高防渗材料崁缝封闭。为防止地震作用对反应堆洞室衬砌混凝土开裂的影响导致充冷却水后渗漏量加大，亦可在反应堆洞室底板及四周采用钢衬方案。在地震引起的严重事故工况下，既可在钢衬洞室内充冷却水防止堆芯熔化事故的发生，又可避免发生洞内冷却水向外部岩体渗漏的可能，以确保核防护安全。
抗渗等级为W12的衬砌混凝土可抵抗120m水头压力作用而不发生混凝土渗水。如国内已建成的世界最高的水布垭面板堆石坝，最大坝高233m，该坝型坝体隔渗完全依靠混凝土面板，该面板抗渗等级为W12，其最大厚度仅1.1m，工程已投入运行多年，未发生异常。地下核电安全壳破裂的严重事故工况下，为防止熔堆，洞室内可充水冷却，按充水深度约20m计，远低于水布垭大坝面板上作用水头，类比可知，抗渗等级W12衬砌混凝土可有效防止反应堆洞室内充冷却水后外渗情况的发生。
2)高密度灌浆裂隙封闭区，即内岩体裂隙充填层S2-1：
内衬层S1外设置有内岩体裂隙充填层S2-1，内岩体裂隙充填层S2-1是对反应堆厂房洞壁围岩采取高密度灌浆，对岩体缝隙进行封闭，使岩体和灌浆物质共同形成封闭的层，进一步提高洞壁围岩的整体性、防渗性，封闭区岩体的综合防渗性能达10-6cm/s。灌浆孔排距初定1m×1m～2m×2m，处理深度8m～12m。
3)高效疏排区，即渗水集中疏排层S3：
为了进一步的防止少量放射性水的渗漏，在内岩体裂隙充填层S2-1的外围设置了能自动疏水的非能动渗水集中疏排层S3，渗水集中疏排层S3由多层排水洞及洞内钻设的上下相互搭接的排水孔组成，排水孔间距初定1m～2m。
4)隔水帷幕区，即外岩体裂隙充填层S2-2：
为了更好的阻隔内外水之间的交换，在渗水集中疏排层S3的外围还布置有外岩体裂隙充填层S2-2，外岩体裂隙充填层S2-2通过多层灌浆平洞及洞内钻设的上下相互搭接的帷幕孔，对岩体裂隙进行充填灌浆封闭，由岩体和灌浆物共同形成封闭层。帷幕标准按目前灌浆工艺最高水平0.5Lu控制，渗透系数约相当于5×10-6cm/s。隔水帷幕初定为单排布置，孔距2m。根据灌浆试验和防渗效果检查，也可布置成多排，孔距亦可进一步减小。
上述多重防护系统中，内衬层S1和内岩体裂隙充填层S2-1的综合作用可使反应堆厂 房洞壁防渗性能达到10-9cm/s量级，基本阻隔严重事故工况下反应堆厂房充冷却水后的内水外渗；渗水集中疏排层S3针对可能产生的微量外渗废水集中疏排，确保放射性废水受控收集、处置；外岩体裂隙充填层S2-2起阻隔洞室群岩体与反应堆厂房洞周岩体地下水水力交换的作用，严重事故工况下，既阻隔外水内渗，又可将微量的放射性废水阻隔在设定区域内，进一步提高严重事故工况下的防护安全。
此外，核岛外围总防护隔水层Z是为了阻隔天然岩体地下水向地下洞室群的渗漏，降低地下水渗压，保证洞室的围岩稳定，并阻隔地下洞室群内外的水力联系，使地下洞室群处于岩体疏干区。外围总防护隔水层Z设置在距离洞室群四周约25m处，由多层排水洞Z2及洞内钻设的上下相互搭接的排水孔Z1组成，排水孔Z1的间距初定为1m～2m，整个外围总防护隔水层Z为全封闭形式。
上述设计中，分别在核岛外围总防护隔水层Z及反应堆洞室渗水集中疏排层S3的最底层分区设置专用沟、管、井、洞、池、罐及相关设施集中处理收集渗水A，并制定稀释、浓缩、吸附、固化等处置预案，根据实测浓度进行处置。储存装置及处置设备根据反应堆洞室水头、岩体渗透特性、防护系统功能进行渗流量计算，确保设置有足够安全裕度。
为了监测地下核电站放射性废水地下迁移的情况，在地下核电站放射性废水地下迁移防护系统多个区域布设监测点B，监测点为孔或者洞，并在监测点加装检、传、报可视化系统C，实时掌握地下水的状态及放射性程度，并根据监测情况采取相应处理措施。
上述设计及布置形式形成地下核电站由反应堆洞室中心至外部岩体的内衬层S1、内岩体裂隙充填层S2-1、渗水集中疏排层S3、外岩体裂隙充填层S2-2的多道安全屏障，充分利用了地下核电天然岩体的防护性能，在严重事故工况下，即安全壳破损、熔堆且地下反应堆厂房洞室部分充冷却水时，使可能泄露的放射性废水封堵在重点防护区内，并处置达安全标准后控放，有效防止放射性废水的地下迁移外渗。
以地下核电站模拟厂址建立等效连续多孔裂隙介质准三维模型进行防护措施效果分析。计算模型中，地震工况下不考虑内衬层S1的作用(作为安全储备)。计算工况包括：①正常运行工况；②设计基准事故工况；③非地震引起的严重事故工况(安全壳破裂，为防止熔堆，洞室内充冷却水20m深)；④地震引起的严重事故工况等。
综合防护措施布置及各工况的计算成果分析可知：①在正常运行工况、设计基准事 故工况及非地震引起的严重事故工况下，地下核电站可能产生的放射性废水与周围岩体均没有发生水力联系，其放射性废水的渗漏量基本为零。此时，防护系统的作用是将地下核电洞室群形成疏干区，确保洞室围岩稳定及良好的工作环境(见图2)。②在地震引起的安全壳破裂的严重事故工况下，为防止堆芯恶化，反应堆洞室充冷却水20m深，此时，在洞室群大疏干区内形成反应堆洞室附近的局部小渗流场，但该小渗流场与周边渗流场没有水力联系(见图3)，且反应堆洞室向周边岩体释放的放射性废水仅0.60m3/h，经反应堆洞周隔水帷幕阻隔和排水幕疏排，并通过专设的收集、处理系统，可使微量释放的放射性废水在防护区内受控处置，防止放射性废水在地下大规模迁移的可能性，符合核电安全多层防御的理念。

Claims (8)

  1. 地下核电站放射性废水地下迁移防护系统，其特征在于：包括反应堆洞室防护层(S)和具有阻隔天然岩体地下水作用的核岛外围总防护隔水层(Z)，所述反应堆防护层(S)包括围绕反应堆洞室的具有防止内水外渗的内衬层(S1)、具有集中疏水功能的渗水集中疏排层(S3)和岩体裂隙充填层(S2)，所述外围总防护隔水层(Z)设置在反应堆洞室和辅助洞室共同组成的地下洞室群外围。
  2. 根据权利要求1所述的地下核电站放射性废水地下迁移防护系统，其特征在于：所述岩体裂隙充填层(S2)包括内岩体裂隙充填层(S2-1)和外岩体裂隙充填层(S2-2)。
  3. 根据权利要求2所述的地下核电站放射性废水地下迁移防护系统，其特征在于：所述的反应堆洞室防护层由内往外依次是内衬层(S1)、内岩体裂隙充填层(S2-1)、渗水集中疏排层(S3)和外岩体裂隙充填层(S2-2)。
  4. 根据权利要求3所述的地下核电站放射性废水地下迁移防护系统，其特征在于：所述内衬层(S1)由钢筋混凝土结构或钢筋混凝土加防水板材构成。
  5. 根据权利要求4所述的，其特征在于：所述混凝土为具有高防渗等级的混凝土。
  6. 根据权利要求3所述的地下核电站放射性废水地下迁移防护系统，其特征在于：所述内岩体裂隙充填层(S2-1)和外岩体裂隙充填层(S2-2)均由岩体裂隙内的灌浆物和岩体本身构成。
  7. 根据权利要求3所述的地下核电站放射性废水地下迁移防护系统，其特征在于：所述渗水集中疏排层(S3)由多层排水洞S3-2及洞内钻设的上下相互搭接的排水孔S3-1组成。
  8. 根据权利要求1所述的地下核电站放射性废水地下迁移防护系统，其特征在于：所述外围总防护(Z)由多层排水洞Z2及洞内钻设的上下相互搭接的排水孔Z1组成。
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