WO2017028201A1 - Nuclear reactor coolant system main circuit arrangement structure - Google Patents
Nuclear reactor coolant system main circuit arrangement structure Download PDFInfo
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- WO2017028201A1 WO2017028201A1 PCT/CN2015/087352 CN2015087352W WO2017028201A1 WO 2017028201 A1 WO2017028201 A1 WO 2017028201A1 CN 2015087352 W CN2015087352 W CN 2015087352W WO 2017028201 A1 WO2017028201 A1 WO 2017028201A1
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- 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
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- 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
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C19/00—Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21D—NUCLEAR POWER PLANT
- G21D1/00—Details of nuclear power plant
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- 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
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- 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 belongs to the field of nuclear power plant design, and more particularly to the arrangement structure of a main circuit of a nuclear power plant reactor coolant system.
- nuclear power technology which is one of the clean energy technologies, is also constantly developing.
- the safety of nuclear power is also placed in an increasingly prominent position.
- the main circuit of the reactor coolant system is arranged in the reactor building.
- the pressure vessel is located in the center of the reactor building; the three steam generators and the three main pumps are respectively arranged at a 120° angle with the pressure vessel as the center; the voltage regulator is arranged on the heat pipe section of the main pipeline of the first circuit.
- the height difference L between the center of the main pipe 12 connected to the pressure vessel 10 and the inner surface 14 of the reactor floor of the reactor building is about 12.4 m.
- the seismic acceleration of the main circuit of the nuclear power plant reactor coolant system is basically designed according to 0.2g
- the seismic capacity of the reactor fuel assembly is basically designed according to 0.2g.
- This main circuit has at least the following disadvantages: 1) The seismic acceleration of the reactor is basically designed according to 0.2g, resulting in a smaller range of target sites for nuclear power plants and a relatively small seismic margin; 2) responding to external disasters such as earthquakes In terms of safety, the safety requirements are not high enough; 3) the requirements for the seismic structure design of the reactor fuel assembly are higher and more complex; 4) the internationally recognized three-generation nuclear power technical requirements are not met.
- the object of the present invention is to provide an arrangement structure of a main circuit of a nuclear power plant reactor coolant system with stronger earthquake resistance to solve the above problems.
- the present invention provides an arrangement structure of a main circuit of a nuclear power plant reactor coolant system, which comprises a reactor building, a pressure vessel, a steam generator, a voltage regulator, a main pump and a main pipeline, and is provided in the reactor building.
- a base plate the pressure vessel is installed in the reactor building and located above the base plate;
- the main pipe is connected between the pressure vessel, the steam generator and the main pump to form a main circuit, and the pressure regulator is arranged on the main pipe;
- the height difference L between the center of the main pipe connected to the pressure vessel and the inner surface of the reactor floor of the reactor building is 9.7 m to 10.8 m.
- the height difference L between the center of the main pipe connected to the pressure vessel and the inner surface of the reactor floor of the reactor building is 10.2 m to 10.5 m. .
- the height difference L between the center of the main pipe connected to the pressure vessel and the inner surface of the reactor floor of the reactor building is 10.2 m to 10.4 m. .
- the height difference L between the center of the main pipe connected to the pressure vessel and the inner surface of the reactor floor of the reactor building is 10.4 m.
- the steam generator and the main pump each have three.
- the three steam generators are arranged symmetrically with each other at an angle of 120° centered on the pressure vessel.
- the three main pumps are arranged symmetrically at an angle of 120° with each other centered on the pressure vessel.
- the number of the voltage regulators is one, which is arranged on the heat pipe section of the main pipe.
- the reactor building is provided with a containment water tank inside, and the structure is a double ring pool structure.
- the arrangement structure of the main circuit of the nuclear power plant reactor coolant system of the present invention adopts the main circuit sinking arrangement, so that the seismic acceleration of the reactor fuel assembly can be achieved without the large adjustment of the reactor fuel assembly structure design. Increased to 0.3g or more, which improves the seismic capacity of the reactor, enabling it to meet the internationally recognized seismic requirements for third-generation nuclear power technology.
- FIG. 1 is a schematic view showing the position of a pressure vessel of an arrangement structure of a main circuit of a nuclear power plant reactor coolant system.
- FIG. 2 is a partial cross-sectional view showing the arrangement structure of a main circuit of a nuclear power plant reactor coolant system according to the present invention.
- FIG. 3 is a schematic diagram showing the structure of a main circuit of an arrangement structure of a main circuit of a nuclear power plant reactor coolant system according to the present invention.
- FIG. 4 is a schematic view showing the position of a pressure vessel of an arrangement structure of a main circuit of a nuclear power plant reactor coolant system according to the present invention.
- the first task is to make the design of the main circuit, especially the reactor fuel assembly, meet the seismic requirements of 0.3 g or more. That is to say, making the seismic capacity of the reactor fuel assembly 0.3 g or more is a necessary condition for the entire power station to achieve a seismic capacity of 0.3 g or more.
- reactor fuel assemblies are basically unable to improve the seismic capacity by modifying the structural design of the fuel assembly itself, and can only be achieved by other means.
- the inventors of the present application conducted sensitivity analysis on various main parameters affecting the dynamic response of the plant, repeated trial and error adjustment schemes, and finally found the main pipeline of the main circuit of the reactor coolant system of the nuclear power plant.
- the height difference L between the center and the surface of the reactor floor inside the reactor building is a critical parameter for the seismic performance of the reactor. The smaller the value of the height difference L, the stronger the seismic performance of the reactor. Therefore, it is conceivable to solve the above problem by reducing the seismic response of the fuel assembly position.
- the present invention reduces the elevation of the fuel assembly arrangement by the "sinking" arrangement of the reactor, ie the "sinking" arrangement of the main circuit, in order to minimize the central elevation of the main pipeline and the interior of the reactor building.
- the height difference between the surfaces is improved, and the structural rigidity of the reactor building is improved by optimizing the structural arrangement scheme, and the seismic action of the fuel assembly is reduced to achieve the seismic requirement of 0.3 g or more.
- the arrangement of the main circuit of the nuclear power plant reactor coolant system of the present invention includes a reactor building, a pressure vessel 30, a steam generator 36, a main pump 38, a main pipe 32, and a voltage regulator (not shown).
- the reactor building is provided with a crucible base plate, and the pressure vessel 30 is installed in the center of the reactor building and above the crucible base plate.
- the main pipe 32 is connected between the pressure vessel 30, the steam generator 36, and the main pump 38 to form a main circuit.
- three steam generators 36 and three main pumps 38 are respectively arranged at a 120° angle with each other centering on the pressure vessel 30; the regulator is disposed on the heat pipe section of the main pipe 32.
- the refueling tank 200 is provided in the reactor building, and the structure is a double ring pool structure.
- the height difference L between the center of the main pipe 32 connected to the pressure vessel 30 and the inner surface 34 of the reactor floor of the reactor building is 10.2 m to 10.5 m, preferably 10.4 m. This is because during the research, it was found that the height difference L between the center of the main pipe 32 of the main circuit and the surface of the base plate 34 of the reactor building can meet the seismic requirement of 0.3g of the fuel assembly when the height difference L is between 9.7m and 10.8m. Combined with the layout of the reactor building and the surrounding raft base plant, the height difference L is 10.2m ⁇ 10.5m, which is a relatively reasonable and feasible solution.
- the choice of height difference of 10.4m is the main circuit "sinking" arrangement
- the overall coordination of the structure and the overall layout of the reactor building and the surrounding raft base plant layout structure is the best. That is, the optimum height difference L between the center of the main circuit main pipe 32 of the present invention and the inner surface 34 of the reactor building is reduced by 2.0 m from the disclosed nuclear power plant.
- the present invention also optimizes the related structure: adjusting the wall structure of the main equipment compartment and the partial wall structure of the reactor pool; adjusting the elevation of the cooling and ventilation system of the containment in the reactor building
- the main equipment load-bearing layer is adjusted to the elevation above the operating platform; the pipeline connected to the main circuit is moved along with the main pipeline 32; the layout scheme of the refueling water tank 200 in the containment is changed from a single-ring pool to a double-ring pool structure.
- the present invention adopts a main circuit sinking arrangement, and the height difference L between the center of the main circuit main pipe 32 and the inner surface of the reactor floor of the reactor building is less than or equal to 10.4 m, and the height difference is relatively
- the open nuclear power plant has been reduced by 2.0m or more, so the seismic acceleration of the reactor fuel assembly can be increased to 0.3g or more without making large adjustments in the reactor fuel assembly structure design, thereby improving the seismic capacity of the reactor and enabling it to Reaching the internationally recognized earthquake resistance to the three generations of nuclear power technology begging.
- the arrangement structure of the main circuit of the nuclear power plant reactor coolant system of the invention has at least the following advantages: 1) using the main circuit sinking arrangement structure, the seismic acceleration of the reactor is increased to 0.3 g or more, and the target site selection will be more in the world. Wide, the seismic margin will be relatively larger, so it can meet the seismic requirements of more sites; 2) greatly enhance the ability of nuclear power plants to cope with external disasters such as earthquakes, and the safety of nuclear power plants has been significantly strengthened, helping to eliminate the public's nuclear power plants.
- the seismic acceleration of the reactor has increased from 0.2g to 0.3g or more, and the seismic acceleration of nuclear power plants has also increased from 0.2g to 0.3g or more, enabling nuclear power plants to withstand external disasters such as stronger earthquakes and improve public Confidence and acceptance of nuclear power plant safety; 3)
- the seismic design of nuclear power plants meet the internationally recognized three-generation nuclear power technical requirements, meet the requirements of EUR and URD: the seismic acceleration of the reactor is 0.3g or more, and the three-generation nuclear power technology that has been published Compared with 0.25g and 0.30g, it has reached the internationally recognized technical requirements of three generations of nuclear power users; 4) It can effectively reduce the difficulty in designing the seismic structure of the reactor fuel assembly, avoiding the large design modification of the reactor fuel assembly structure design due to the improvement of seismic requirements, which is beneficial to shorten the fuel assembly structure design time.
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Abstract
Description
本发明属于核电站设计领域，更具体地说，本发明涉及一种核电站反应堆冷却剂系统主回路的布置结构。The invention belongs to the field of nuclear power plant design, and more particularly to the arrangement structure of a main circuit of a nuclear power plant reactor coolant system.
随着经济发展和环境保护要求的日益提高，作为清洁能源技术之一的核电技术也在不断向前发展，核电站设计在更新换代过程中，核电的安全性也被摆在愈加突出的位置。With the increasing requirements of economic development and environmental protection, nuclear power technology, which is one of the clean energy technologies, is also constantly developing. In the process of upgrading nuclear power plants, the safety of nuclear power is also placed in an increasingly prominent position.
在已公开的核电站中，反应堆冷却剂系统主回路布置在反应堆厂房内。其中，压力容器位于反应堆厂房中心；3台蒸汽发生器和3台主泵分别以压力容器为中心，彼此呈120°夹角对称布置；稳压器布置在一回路主管道的热管段上。请参阅图1，在上述反应堆冷却剂系统的主回路中，与压力容器10连接的主管道12的中心和反应堆厂房内部筏基底板上表面14之间的高差L约为12.4m。In the disclosed nuclear power plant, the main circuit of the reactor coolant system is arranged in the reactor building. The pressure vessel is located in the center of the reactor building; the three steam generators and the three main pumps are respectively arranged at a 120° angle with the pressure vessel as the center; the voltage regulator is arranged on the heat pipe section of the main pipeline of the first circuit. Referring to Fig. 1, in the main circuit of the above reactor coolant system, the height difference L between the center of the
但是，上述核电站反应堆冷却剂系统主回路的抗震加速度基本上是按0.2g进行设计，其反应堆燃料组件的抗震能力也基本上是按0.2g进行设计。这种主回路至少具有以下缺点：1)反应堆的抗震加速度基本上按0.2g进行设计，导致核电站在目标厂址选择上范围更小，抗震裕量也相对较小；2)在应对地震等外部灾害方面，安全性不够高；3)对反应堆燃料组件抗震结构设计方面的要求更高、更复杂；4)达不到国际上公认的三代核电技术要求。However, the seismic acceleration of the main circuit of the nuclear power plant reactor coolant system is basically designed according to 0.2g, and the seismic capacity of the reactor fuel assembly is basically designed according to 0.2g. This main circuit has at least the following disadvantages: 1) The seismic acceleration of the reactor is basically designed according to 0.2g, resulting in a smaller range of target sites for nuclear power plants and a relatively small seismic margin; 2) responding to external disasters such as earthquakes In terms of safety, the safety requirements are not high enough; 3) the requirements for the seismic structure design of the reactor fuel assembly are higher and more complex; 4) the internationally recognized three-generation nuclear power technical requirements are not met.
发明内容Summary of the invention
本发明的目的在于：提供一种抗震能力更强的核电站反应堆冷却剂系统主回路的布置结构，以解决上述问题。 The object of the present invention is to provide an arrangement structure of a main circuit of a nuclear power plant reactor coolant system with stronger earthquake resistance to solve the above problems.
为了实现上述发明目的，本发明提供了一种核电站反应堆冷却剂系统主回路的布置结构，其包括反应堆厂房、压力容器、蒸汽发生器、稳压器、主泵和主管道，反应堆厂房内设有筏基底板；压力容器安装在反应堆厂房中，并位于筏基底板的上方；主管道连接在压力容器、蒸汽发生器、主泵之间而形成主回路，稳压器布置在主管道上；所述与压力容器连接的主管道的中心和反应堆厂房内部筏基底板上表面之间的高差L为9.7m～10.8m。In order to achieve the above object, the present invention provides an arrangement structure of a main circuit of a nuclear power plant reactor coolant system, which comprises a reactor building, a pressure vessel, a steam generator, a voltage regulator, a main pump and a main pipeline, and is provided in the reactor building. a base plate; the pressure vessel is installed in the reactor building and located above the base plate; the main pipe is connected between the pressure vessel, the steam generator and the main pump to form a main circuit, and the pressure regulator is arranged on the main pipe; The height difference L between the center of the main pipe connected to the pressure vessel and the inner surface of the reactor floor of the reactor building is 9.7 m to 10.8 m.
作为本发明核电站反应堆冷却剂系统主回路的布置结构的一种改进，所述与压力容器连接的主管道的中心和反应堆厂房内部筏基底板上表面之间的高差L为10.2m～10.5m。As an improvement of the arrangement structure of the main circuit of the nuclear power plant reactor coolant system of the present invention, the height difference L between the center of the main pipe connected to the pressure vessel and the inner surface of the reactor floor of the reactor building is 10.2 m to 10.5 m. .
作为本发明核电站反应堆冷却剂系统主回路的布置结构的一种改进，所述与压力容器连接的主管道的中心和反应堆厂房内部筏基底板上表面之间的高差L为10.2m～10.4m。As an improvement of the arrangement structure of the main circuit of the nuclear power plant reactor coolant system of the present invention, the height difference L between the center of the main pipe connected to the pressure vessel and the inner surface of the reactor floor of the reactor building is 10.2 m to 10.4 m. .
作为本发明核电站反应堆冷却剂系统主回路的布置结构的一种改进，所述与压力容器连接的主管道的中心和反应堆厂房内部筏基底板上表面之间的高差L为10.4m。As an improvement of the arrangement of the main circuit of the nuclear power plant reactor coolant system of the present invention, the height difference L between the center of the main pipe connected to the pressure vessel and the inner surface of the reactor floor of the reactor building is 10.4 m.
作为本发明核电站反应堆冷却剂系统主回路的布置结构的一种改进，所述蒸汽发生器和主泵各有三台。As an improvement of the arrangement of the main circuit of the nuclear power plant reactor coolant system of the present invention, the steam generator and the main pump each have three.
作为本发明核电站反应堆冷却剂系统主回路的布置结构的一种改进，所述三台蒸汽发生器以压力容器为中心，彼此呈120°夹角对称布置。As an improvement of the arrangement of the main circuit of the nuclear power plant reactor coolant system of the present invention, the three steam generators are arranged symmetrically with each other at an angle of 120° centered on the pressure vessel.
作为本发明核电站反应堆冷却剂系统主回路的布置结构的一种改进，所述三台主泵以压力容器为中心，彼此呈120°夹角对称布置。As an improvement of the arrangement structure of the main circuit of the nuclear power plant reactor coolant system of the present invention, the three main pumps are arranged symmetrically at an angle of 120° with each other centered on the pressure vessel.
作为本发明核电站反应堆冷却剂系统主回路的布置结构的一种改进，所述稳压器的数量为一台，其布置在主管道的热管段上。As an improvement of the arrangement of the main circuit of the nuclear power plant reactor coolant system of the present invention, the number of the voltage regulators is one, which is arranged on the heat pipe section of the main pipe.
作为本发明核电站反应堆冷却剂系统主回路的布置结构的一种改进，所述反应堆厂房内设置有安全壳内换料水箱，其结构为双环池结构。 As an improvement of the arrangement structure of the main circuit of the nuclear power plant reactor coolant system of the present invention, the reactor building is provided with a containment water tank inside, and the structure is a double ring pool structure.
与现有技术相比，本发明核电站反应堆冷却剂系统主回路的布置结构采用了主回路下沉布置，因此能够在反应堆燃料组件结构设计不做大的调整的情况下，将反应堆燃料组件抗震加速度提高到0.3g或以上，从而提高了反应堆抗震能力，使其能够达到国际上公认的对三代核电技术的抗震要求。Compared with the prior art, the arrangement structure of the main circuit of the nuclear power plant reactor coolant system of the present invention adopts the main circuit sinking arrangement, so that the seismic acceleration of the reactor fuel assembly can be achieved without the large adjustment of the reactor fuel assembly structure design. Increased to 0.3g or more, which improves the seismic capacity of the reactor, enabling it to meet the internationally recognized seismic requirements for third-generation nuclear power technology.
下面结合附图和具体实施方式，对本发明核电站反应堆冷却剂系统主回路的布置结构及其有益效果进行详细说明。The arrangement structure of the main circuit of the nuclear power plant reactor coolant system of the present invention and its beneficial effects will be described in detail below with reference to the accompanying drawings and specific embodiments.
图1为已公开核电站反应堆冷却剂系统主回路的布置结构的压力容器位置示意图。1 is a schematic view showing the position of a pressure vessel of an arrangement structure of a main circuit of a nuclear power plant reactor coolant system.
图2为本发明核电站反应堆冷却剂系统主回路的布置结构的部分剖视示意图。2 is a partial cross-sectional view showing the arrangement structure of a main circuit of a nuclear power plant reactor coolant system according to the present invention.
图3为本发明核电站反应堆冷却剂系统主回路的布置结构的主回路结构示意图。3 is a schematic diagram showing the structure of a main circuit of an arrangement structure of a main circuit of a nuclear power plant reactor coolant system according to the present invention.
图4为本发明核电站反应堆冷却剂系统主回路的布置结构的压力容器位置示意图。4 is a schematic view showing the position of a pressure vessel of an arrangement structure of a main circuit of a nuclear power plant reactor coolant system according to the present invention.
为了使本发明的目的、技术方案及其有益技术效果更加清晰，以下结合附图和具体实施方式，对本发明进行进一步详细说明。应当理解的是，本说明书中描述的具体实施方式仅仅是为了解释本发明，并非为了限定本发明。The present invention will be further described in detail below with reference to the accompanying drawings and specific embodiments. The specific embodiments described in the specification are to be construed as illustrative only and not limiting.
为了提高核电站的抗震水平、提高核电站的安全性，满足三代核电技术主要特征参数要求，有必要将核电站抗震设计要求提高至0.3g或以上。为了实现这一目标，首要任务是使主回路特别是反应堆燃料组件的设计满足0.3g或以上抗震要求。也就是说，使反应堆燃料组件的抗震能力达到0.3g或以上是整个电站达到0.3g或以上抗震能力的必要条件。 In order to improve the seismic level of nuclear power plants, improve the safety of nuclear power plants, and meet the main characteristics of the three generations of nuclear power technology, it is necessary to increase the seismic design requirements of nuclear power plants to 0.3g or more. In order to achieve this goal, the first task is to make the design of the main circuit, especially the reactor fuel assembly, meet the seismic requirements of 0.3 g or more. That is to say, making the seismic capacity of the reactor fuel assembly 0.3 g or more is a necessary condition for the entire power station to achieve a seismic capacity of 0.3 g or more.
但是，反应堆燃料组件由于自身结构的特殊性，基本无法通过修改燃料组件本身的结构设计来提高抗震能力，只能通过其他途径实现。为了不对反应堆燃料组件结构设计做大的调整，本申请的发明人对影响厂房动力响应的各个主要参数进行了敏感性分析，反复试算调整方案，终于发现核电站反应堆冷却剂系统主回路的主管道中心和反应堆厂房内部筏基底板上表面之间的高差L对于反应堆抗震性能是至关重要的参数，即高差L的值越小，反应堆的抗震性能就越强。因此，可以考虑通过降低燃料组件位置的地震响应来解决上述问题。However, due to the particularity of its structure, reactor fuel assemblies are basically unable to improve the seismic capacity by modifying the structural design of the fuel assembly itself, and can only be achieved by other means. In order not to make major adjustments to the structural design of the reactor fuel assembly, the inventors of the present application conducted sensitivity analysis on various main parameters affecting the dynamic response of the plant, repeated trial and error adjustment schemes, and finally found the main pipeline of the main circuit of the reactor coolant system of the nuclear power plant. The height difference L between the center and the surface of the reactor floor inside the reactor building is a critical parameter for the seismic performance of the reactor. The smaller the value of the height difference L, the stronger the seismic performance of the reactor. Therefore, it is conceivable to solve the above problem by reducing the seismic response of the fuel assembly position.
以上述研究为基础，本发明通过反应堆的“下沉”布置，也即主回路“下沉”布置来降低燃料组件布置的标高，以尽可能缩小主管道中心标高与反应堆厂房内部筏基底板上表面之间高差，同时通过优化结构布置方案，提高反应堆厂房内部结构刚度，降低燃料组件承受的地震作用，使之达到0.3g或以上的抗震要求。Based on the above studies, the present invention reduces the elevation of the fuel assembly arrangement by the "sinking" arrangement of the reactor, ie the "sinking" arrangement of the main circuit, in order to minimize the central elevation of the main pipeline and the interior of the reactor building. The height difference between the surfaces is improved, and the structural rigidity of the reactor building is improved by optimizing the structural arrangement scheme, and the seismic action of the fuel assembly is reduced to achieve the seismic requirement of 0.3 g or more.
请参阅图2和图3，本发明核电站反应堆冷却剂系统主回路的布置结构包括反应堆厂房、压力容器30、蒸汽发生器36、主泵38、主管道32和稳压器(图未示)。反应堆厂房内设有筏基底板，压力容器30安装在反应堆厂房的中心，并位于筏基底板的上方。主管道32连接在压力容器30、蒸汽发生器36、主泵38之间而形成主回路。其中，3台蒸汽发生器36和3台主泵38分别以压力容器30为中心，彼此呈120°夹角对称布置；稳压器布置在主管道32的热管段上。反应堆厂房内设置有安全壳内换料水箱200，其结构为双环池结构。Referring to Figures 2 and 3, the arrangement of the main circuit of the nuclear power plant reactor coolant system of the present invention includes a reactor building, a
请参阅图4，与压力容器30连接的主管道32的中心和反应堆厂房内部筏基底板上表面34之间的高差L为10.2m～10.5m，优选为10.4m。这是因为在研究过程中发现，主回路的主管道32中心和反应堆厂房内部筏基底板上表面34之间的高差L在9.7m～10.8m时都能满足燃料组件0.3g抗震要求，而结合反应堆厂房及周边共用筏基厂房的布置情况，高差L在10.2m～10.5m是一个相对合理、可行的方案，进一步综合考虑工程可实施性(比如设备、阀门安装、操作便利
性)、人员通行便利性(相关楼层通道净空要求等)和安全壳内换料水箱200布置方案(外环池施工便利性)等因素，选择高差为10.4m是主回路“下沉”布置结构与反应堆厂房整体布置结构及周边共用筏基厂房布置结构整体协调性最好的方案。也就是说，本发明的主回路主管道32的中心和反应堆厂房内部筏基底板上表面34之间的最佳高差L相对已公开的核电站减少了2.0m。Referring to Fig. 4, the height difference L between the center of the
为了配合主回路“下沉”布置，本发明还同时对相关的结构进行了以下优化：调整主设备隔间墙体结构和反应堆水池局部墙体结构；调整反应堆厂房内安全壳冷却通风系统布置标高，由主设备承重层调至操作平台以上标高布置；使与主回路相连的管道随主管道32一起移动；将安全壳内换料水箱200布置方案由单环池改为双环池结构等。In order to meet the "sinking" arrangement of the main circuit, the present invention also optimizes the related structure: adjusting the wall structure of the main equipment compartment and the partial wall structure of the reactor pool; adjusting the elevation of the cooling and ventilation system of the containment in the reactor building The main equipment load-bearing layer is adjusted to the elevation above the operating platform; the pipeline connected to the main circuit is moved along with the
需要说明的是，虽然主回路主管道32的中心和反应堆厂房内部筏基底板上表面34之间的高差L越小，反应堆的抗震性能就越强，但是L也并不能无限制地缩小，原因如下：一是为了使反应堆厂房内与已公开核电站相比有大致相同条件的布置空间和相似结构，以避免后续出现无法解决的未知问题；二是L过小将会导致外环池202上部的环形空间净高过低，以至于无法满足阀门布置空间要求和人员通行要求，使得反应堆厂房底部安全壳内换料水箱200的外环池202施工困难；三是L过小还会导致周边的安全厂房、燃料厂房局部区域布置不合理，尤其是燃料厂房乏池屏蔽水层厚度将不能满足要求。因此，在利用主回路“下沉”布置来提高反应堆燃料组件抗震能力时，还必须对L的最低值有所限定。It should be noted that although the height difference L between the center of the main circuit
与现有技术相比，本发明采用了主回路下沉布置，其主回路主管道32中心和反应堆厂房内部筏基底板上表面34之间的高差L小于等于10.4m，此高差相对已公开的核电站减少了2.0m或以上，因此能够在反应堆燃料组件结构设计不做大的调整的情况下，将反应堆燃料组件抗震加速度提高到0.3g或以上，从而提高了反应堆抗震能力，使其能够达到国际上公认的对三代核电技术的抗震要
求。Compared with the prior art, the present invention adopts a main circuit sinking arrangement, and the height difference L between the center of the main circuit
本发明核电站反应堆冷却剂系统主回路的布置结构至少具有以下优点：1)采用主回路下沉布置结构，将反应堆抗震加速度提升至0.3g或以上，在世界范围内目标厂址选择上，范围将更广，抗震裕量也将相对更大，因此可以满足更多厂址的抗震要求；2)极大地提升了核电站应对地震等外部灾害方面能力，核电站安全性得到明显加强，有助于消除公众对核电站安全性疑虑和恐惧心理：反应堆抗震加速度从0.2g提升至0.3g或以上，核电站的抗震加速度也从0.2g提升至0.3g或以上，使核电站能抵御更强的地震等外部灾害，提高公众对核电站安全的信心与接受度；3)在核电站抗震设计方面，达到国际上公认的三代核电技术要求，满足EUR和URD要求：反应堆抗震加速度为0.3g或以上，和目前已公开的三代核电技术的0.25g、0.30g相比，已达到国际公认的三代核电用户技术要求；4)可以有效降低反应堆燃料组件抗震结构设计方面的难度，避免了因为抗震要求的提高而对反应堆燃料组件结构设计进行大的设计修改，有利于缩短燃料组件结构设计时间。The arrangement structure of the main circuit of the nuclear power plant reactor coolant system of the invention has at least the following advantages: 1) using the main circuit sinking arrangement structure, the seismic acceleration of the reactor is increased to 0.3 g or more, and the target site selection will be more in the world. Wide, the seismic margin will be relatively larger, so it can meet the seismic requirements of more sites; 2) greatly enhance the ability of nuclear power plants to cope with external disasters such as earthquakes, and the safety of nuclear power plants has been significantly strengthened, helping to eliminate the public's nuclear power plants. Safety concerns and fears: The seismic acceleration of the reactor has increased from 0.2g to 0.3g or more, and the seismic acceleration of nuclear power plants has also increased from 0.2g to 0.3g or more, enabling nuclear power plants to withstand external disasters such as stronger earthquakes and improve public Confidence and acceptance of nuclear power plant safety; 3) In the seismic design of nuclear power plants, meet the internationally recognized three-generation nuclear power technical requirements, meet the requirements of EUR and URD: the seismic acceleration of the reactor is 0.3g or more, and the three-generation nuclear power technology that has been published Compared with 0.25g and 0.30g, it has reached the internationally recognized technical requirements of three generations of nuclear power users; 4) It can effectively reduce the difficulty in designing the seismic structure of the reactor fuel assembly, avoiding the large design modification of the reactor fuel assembly structure design due to the improvement of seismic requirements, which is beneficial to shorten the fuel assembly structure design time.
根据上述说明书的揭示和教导，本发明所属领域的技术人员还可以对上述实施方式进行适当的变更和修改。因此，本发明并不局限于上面揭示和描述的具体实施方式，对本发明的一些修改和变更也应当落入本发明的权利要求的保护范围内。此外，尽管本说明书中使用了一些特定的术语，但这些术语只是为了方便说明，并不对本发明构成任何限制。 The above embodiments may be modified and modified as appropriate by those skilled in the art in light of the above disclosure. Therefore, the invention is not limited to the specific embodiments disclosed and described herein, and the modifications and variations of the invention are intended to fall within the scope of the appended claims. In addition, although specific terms are used in the specification, these terms are merely for convenience of description and do not limit the invention.
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