CN204242595U - Integrated pressurized water reactor with built-in steam pressurizer heat shield and its components - Google Patents
Integrated pressurized water reactor with built-in steam pressurizer heat shield and its components Download PDFInfo
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- CN204242595U CN204242595U CN201420793800.9U CN201420793800U CN204242595U CN 204242595 U CN204242595 U CN 204242595U CN 201420793800 U CN201420793800 U CN 201420793800U CN 204242595 U CN204242595 U CN 204242595U
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- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 title claims abstract description 72
- 238000009413 insulation Methods 0.000 claims abstract description 31
- 239000002826 coolant Substances 0.000 claims abstract description 20
- 239000002131 composite material Substances 0.000 claims abstract description 7
- 229910001220 stainless steel Inorganic materials 0.000 claims abstract description 4
- 239000010935 stainless steel Substances 0.000 claims abstract description 4
- 229920006395 saturated elastomer Polymers 0.000 claims description 18
- 239000011229 interlayer Substances 0.000 claims description 15
- 239000003351 stiffener Substances 0.000 claims description 13
- 239000010410 layer Substances 0.000 claims description 12
- 229910000963 austenitic stainless steel Inorganic materials 0.000 claims description 9
- 239000002184 metal Substances 0.000 claims description 8
- 229910052751 metal Inorganic materials 0.000 claims description 8
- 239000011888 foil Substances 0.000 claims description 3
- 239000003795 chemical substances by application Substances 0.000 claims 1
- 238000001816 cooling Methods 0.000 claims 1
- 230000001052 transient effect Effects 0.000 abstract description 4
- 238000010438 heat treatment Methods 0.000 abstract description 3
- 230000015572 biosynthetic process Effects 0.000 abstract 2
- 229910001566 austenite Inorganic materials 0.000 abstract 1
- 230000000694 effects Effects 0.000 description 6
- 230000005855 radiation Effects 0.000 description 5
- 238000002955 isolation Methods 0.000 description 4
- 238000000034 method Methods 0.000 description 3
- 230000009286 beneficial effect Effects 0.000 description 2
- 230000007797 corrosion Effects 0.000 description 2
- 238000005260 corrosion Methods 0.000 description 2
- 238000010586 diagram Methods 0.000 description 2
- 238000005485 electric heating Methods 0.000 description 2
- ZOXJGFHDIHLPTG-UHFFFAOYSA-N Boron Chemical compound [B] ZOXJGFHDIHLPTG-UHFFFAOYSA-N 0.000 description 1
- 229910052796 boron Inorganic materials 0.000 description 1
- 238000010612 desalination reaction Methods 0.000 description 1
- 238000005265 energy consumption Methods 0.000 description 1
- 238000005516 engineering process Methods 0.000 description 1
- 239000012774 insulation material Substances 0.000 description 1
- 230000010354 integration Effects 0.000 description 1
- 230000009916 joint effect Effects 0.000 description 1
- 239000007788 liquid Substances 0.000 description 1
- 238000004519 manufacturing process Methods 0.000 description 1
- 239000000463 material Substances 0.000 description 1
- 150000002739 metals Chemical class 0.000 description 1
- 238000010248 power generation Methods 0.000 description 1
- 230000000191 radiation effect Effects 0.000 description 1
- 239000013535 sea water Substances 0.000 description 1
- 239000003381 stabilizer Substances 0.000 description 1
- 230000008646 thermal stress Effects 0.000 description 1
- 230000003313 weakening effect Effects 0.000 description 1
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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
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Abstract
Description
技术领域 technical field
本实用新型涉及一种隔热板,具体涉及的是压水堆内置蒸汽稳压器隔热板及其构成的一体化压水堆。 The utility model relates to a heat insulation board, in particular to a heat insulation board for a built-in steam pressurizer in a pressurized water reactor and an integrated pressurized water reactor composed of the same.
背景技术 Background technique
传统外置电加热式蒸汽稳压器是一个高压容器,由汽液两相空间组成,其中上半部分为饱和蒸汽空间,下半部分是饱和水空间。在稳压器的汽空间设有喷雾器接管、卸压阀接管及安全阀接管;水空间内设有电加热器,底部通过波动管与反应堆冷却剂系统的热段管道连接。 The traditional external electric heating steam pressurizer is a high-pressure vessel consisting of a vapor-liquid two-phase space, the upper half of which is a saturated steam space and the lower half is a saturated water space. In the steam space of the pressurizer, there are sprayer connecting pipes, pressure relief valve connecting pipes and safety valve connecting pipes; in the water space, there is an electric heater, and the bottom is connected to the hot section pipe of the reactor coolant system through a wave pipe.
由于蒸汽稳压器是通过波动管与反应堆冷却剂系统连通,不可避免的存在发生潜在的因波动管破裂发生冷却剂失水事故(LOCA)的风险。设计人员为了提高反应堆的固有安全特性,从设计上消除波动管破裂导致的LOCA事故,因而需要将蒸汽稳压器内置于反应堆压力容器中。 Since the steam pressurizer is connected with the reactor coolant system through the surge tube, there is an inevitable risk of a potential loss of coolant accident (LOCA) due to the rupture of the surge tube. In order to improve the inherent safety characteristics of the reactor and eliminate the LOCA accident caused by the rupture of the surge tube, the designer needs to build the steam pressurizer into the reactor pressure vessel.
但由于反应堆冷却剂过冷水与内置稳压器中饱和水同处反应堆压力容器中,而且过冷水与饱和水一般存在约25℃的温差,因而必须设计一种新型隔热板实现过冷水与饱和水的隔离。 However, since the supercooled water of the reactor coolant and the saturated water in the built-in pressurizer are in the reactor pressure vessel, and there is generally a temperature difference of about 25°C between the supercooled water and the saturated water, a new type of heat shield must be designed to realize the supercooled water and saturated water. Water isolation.
且反应堆压力容器常常处于345℃左右的高温、15.5MPa的高压、高辐射的硼水环境中,其工作条件恶劣,因而需要一种内置蒸汽稳压器隔热板结构方案,其不仅仅要达到隔热的效果,而且还需要能够适应恶劣的工作条件,用于解决此类技术难题。 Moreover, the reactor pressure vessel is often in a high temperature of about 345 °C, a high pressure of 15.5 MPa, and a high-radiation boron water environment. The effect of heat insulation, but also need to be able to adapt to harsh working conditions, to solve such technical problems.
实用新型内容 Utility model content
本实用新型的目的在于解决现有技术中外置电加热式蒸汽稳压器与反应堆冷却剂系统通过波动管连接时存在潜在因波动管破裂导致冷却剂失水事故风险发生的问题,提供一种满足高温高压环境、隔热性能良好且实现反应堆在各种瞬态工况下过冷水与饱和水的双向快速波动的压水堆内置蒸汽稳压器隔热板;本实用新型还提供了该压水堆内置蒸汽稳压器隔热板构成的一体化压水堆。 The purpose of this utility model is to solve the problem in the prior art that there is a potential risk of coolant loss accidents caused by the rupture of the surge tube when the external electric heating steam pressurizer is connected to the reactor coolant system through the surge tube, and to provide a satisfying High-temperature and high-pressure environment, good thermal insulation performance, and two-way rapid fluctuation of supercooled water and saturated water in the reactor under various transient working conditions. An integrated pressurized water reactor composed of built-in steam pressurizer heat shields.
为解决上述缺点,本实用新型的技术方案如下: In order to solve the above-mentioned shortcoming, the technical scheme of the utility model is as follows:
压水堆内置蒸汽稳压器隔热板,包括由构成空气夹层的双层奥氏体不锈钢板组成的隔热板本体,以及设置在隔热板本体上方与其一体成型且组合构成倒帽形复合结构的连接体;所述隔热板本体上则设置有圆筒形波动孔。 The heat shield of the built-in steam pressurizer of the pressurized water reactor includes the heat shield body composed of double-layer austenitic stainless steel plates forming the air interlayer, and the upper part of the heat shield body is integrally formed and combined to form an inverted hat-shaped composite The connecting body of the structure; the heat insulation board body is provided with a cylindrical undulating hole.
本实用新型通过将压水堆内置蒸汽稳压器隔热板上的连接体焊接在反应堆压力容器内,通过隔热板本体即可有效实现稳压器中饱和水与反应堆冷却剂过冷水的隔离,达到隔离的效果。 The utility model welds the connecting body on the thermal insulation plate of the built-in steam pressurizer of the pressurized water reactor into the reactor pressure vessel, and can effectively realize the isolation of the saturated water in the pressurizer and the supercooled water of the reactor coolant through the thermal insulation plate body , to achieve the effect of isolation.
通过双层奥氏体不锈钢板组成空气夹层可有效达到隔热的效果,由于空气夹层内的空气处于封闭状态中,该空气几乎无流动,有效降低饱和水及过冷水之间的对流传热,在该状态下空气的导热系数仅为0.023 ,是高温辐照环境下极其理想的高效隔热材料;同时奥氏体不锈钢的导热系数基本在10~30 范围内,是导热性最差的金属之一;因而带空气夹层的双层奥氏体不锈钢板复合结构可有效降低饱和水及过冷水之间的热传导。 The air interlayer composed of double-layer austenitic stainless steel plates can effectively achieve the effect of heat insulation. Since the air in the air interlayer is in a closed state, the air has almost no flow, which effectively reduces the convective heat transfer between saturated water and supercooled water. In this state the thermal conductivity of air is only 0.023 , is an extremely ideal high-efficiency heat insulation material in a high-temperature radiation environment; at the same time, the thermal conductivity of austenitic stainless steel is basically 10~30 Within the range, it is one of the metals with the worst thermal conductivity; therefore, the double-layer austenitic stainless steel plate composite structure with air interlayer can effectively reduce the heat conduction between saturated water and supercooled water.
本实用新型通过不易活化的空气及奥氏体不锈钢材料组合有效解决耐高温、耐辐照、耐腐蚀的难题。 The utility model effectively solves the problems of high temperature resistance, radiation resistance and corrosion resistance through the combination of air which is not easily activated and austenitic stainless steel materials.
并且,通过隔热板本体上设置的圆筒形波动孔,可使反应堆在各种瞬态工况下饱和水及过冷水双向快速波动;同时,通过倒帽形复合结构可以自适应反应堆压力容器顶盖封头在运行工况下径向膨胀导致隔热板的径向拉伸,有效降低热应力,进而提高使用寿命,效果十分显著。 In addition, through the cylindrical wave hole set on the heat shield body, the reactor can make the saturated water and supercooled water fluctuate rapidly in both directions under various transient conditions; at the same time, the inverted hat-shaped composite structure can adapt to the reactor pressure vessel The radial expansion of the top cover head under operating conditions leads to radial stretching of the heat shield, which effectively reduces thermal stress and improves service life. The effect is very significant.
作为一种优选,所述圆筒形波动孔位于隔热板本体的中央部位。 As a preference, the cylindrical wave hole is located in the central part of the heat insulation board body.
进一步,所述隔热板本体上设置有将空气夹层分隔成多个空腔的径向加劲板及环向加劲板。 Further, the heat insulation board body is provided with radial stiffeners and hoop stiffeners that divide the air interlayer into multiple cavities.
通过径向加劲板及环向加劲板将空气夹层分隔成多个空腔,更加有效地防止空气的流动,进一步加强隔热的效果;同时,该径向加劲板及环向加劲板还使隔热板本体能够承受反应堆内高达21MPa的高压环境。 The air interlayer is divided into multiple cavities by the radial stiffening plate and the circumferential stiffening plate, which can more effectively prevent the flow of air and further enhance the effect of heat insulation; at the same time, the radial stiffening plate and the circumferential stiffening plate also make the insulation The hot plate body can withstand the high pressure environment up to 21MPa in the reactor.
更进一步,所述空腔内水平叠放有波纹状镜面不锈钢箔片构成的金属反射层。该空腔内的金属反射层可有效降低热辐射效应,因而,通过减弱该辐射的传热方式,并结合上述减弱的传导和对流的传热方式,得到了极好地减弱传热的效果,进而使隔热板本体具有良好隔热性能,实现了一体化压水堆内稳压器中饱和水与反应堆冷却剂过冷水的隔离,有利于稳压器汽空间的建立,并降低稳压器运行能耗。 Furthermore, a metal reflective layer made of corrugated mirror stainless steel foil is stacked horizontally in the cavity. The metal reflective layer in the cavity can effectively reduce the heat radiation effect. Therefore, by weakening the heat transfer mode of the radiation and combining the above weakened conduction and convection heat transfer modes, an excellent effect of reducing heat transfer is obtained. Furthermore, the heat shield body has good heat insulation performance, and the isolation of the saturated water in the pressurizer in the integrated pressurized water reactor and the supercooled water of the reactor coolant is realized, which is beneficial to the establishment of the steam space of the pressurizer and reduces the pressure of the pressurizer. Operating energy consumption.
作为一种优选地设置方式,所述空气夹层由八个径向加劲板及四个环向加劲板分隔成33个空腔。 As a preferred arrangement, the air interlayer is divided into 33 cavities by eight radial stiffening plates and four circumferential stiffening plates.
本实用新型还公开了利用上述压水堆内置蒸汽稳压器隔热板将蒸汽稳压器内置在压水堆内的一体化压水堆,其具体结构如下: The utility model also discloses an integrated pressurized water reactor in which the steam pressurizer is built into the pressurized water reactor by using the heat insulation board of the built-in steam pressurizer of the above pressurized water reactor, and its specific structure is as follows:
包括具有顶盖封头的反应堆压力容器,位于反应堆压力容器内的反应堆冷却剂过冷水,位于反应堆冷却剂过冷水上方的内置稳压器饱和水,以及焊接在顶盖封头内用于分隔反应堆冷却剂过冷水和内置稳压器饱和水的上述压水堆内置蒸汽稳压器。 Includes reactor pressure vessel with top head, reactor coolant subcooled water inside the reactor vessel, built-in pressurizer saturation water above the reactor coolant subcooler, and welded into the top head to separate the reactor The above-mentioned pressurized water reactor has a built-in steam pressurizer for the supercooled water of the coolant and the saturated water of the built-in pressurizer.
本实用新型与现有技术相比,具有以下优点及有益效果: Compared with the prior art, the utility model has the following advantages and beneficial effects:
1、本实用新型中的隔热板结构具有耐高温、耐高压、耐辐照、耐腐蚀,隔热性能良好等优点,且该隔热板实现了反应堆在各种瞬态工况下一体化压水堆内过冷水与饱和水的双向快速波动,效果十分显著; 1. The heat shield structure in this utility model has the advantages of high temperature resistance, high pressure resistance, radiation resistance, corrosion resistance, good heat insulation performance, etc., and the heat shield realizes the integration of the reactor under various transient working conditions The two-way rapid fluctuation of supercooled water and saturated water in the pressurized water reactor is very effective;
2、本实用新型的使用寿命长,其设计寿命预期长达60年; 2. The utility model has a long service life, and its designed service life is expected to be as long as 60 years;
3、本实用新型具有高安全性,为核能作为分布式清洁能源创造了条件,可用于核能发电、核能城市区域供热、核能工业工艺供热及核能海水淡化等领域,其应用范围广泛; 3. The utility model has high safety and creates conditions for nuclear energy as a distributed clean energy source. It can be used in the fields of nuclear energy power generation, nuclear energy urban district heating, nuclear energy industrial process heating and nuclear energy seawater desalination, etc., and its application range is wide;
4、本实用新型解决了一体化压水堆内置蒸汽稳压器最核心的关键结构技术难题,该隔热板技术可广泛应用于军用、民用革新型一体化压水堆,为提高核能及核动力推进反应堆安全性具有革命性意义。 4. The utility model solves the key structural technical problem of the built-in steam pressurizer in the integrated pressurized water reactor. The heat shield technology can be widely used in military and civilian innovative integrated pressurized water reactors. Power propulsion reactor safety is revolutionary.
附图说明 Description of drawings
图1为本实用新型的纵剖面结构示意图。 Fig. 1 is a schematic view of the longitudinal section of the utility model.
图2为本实用新型的俯视结构示意图。 Fig. 2 is a top view structural diagram of the utility model.
图3为图1中A-A向的剖面结构示意图。 Fig. 3 is a schematic cross-sectional structure diagram along the direction A-A in Fig. 1 .
图4为本实用新型安装在反应堆压力容器中的结构示意图。 Fig. 4 is a structural schematic view of the utility model installed in a reactor pressure vessel.
其中,图中附图标记对应的零部件名称为: Among them, the names of parts corresponding to the reference signs in the figure are:
1-隔热板本体,2-空气夹层,3-连接体,4-圆筒形波动孔,5-径向加劲板,6-环向加劲板,7-金属反射层,8-反应堆压力容器,9-反应堆冷却剂过冷水,10-内置稳压器饱和水。 1-insulation plate body, 2-air interlayer, 3-connector, 4-cylindrical wave hole, 5-radial stiffener, 6-circular stiffener, 7-metal reflector, 8-reactor pressure vessel , 9-reactor coolant supercooled water, 10-built-in stabilizer saturated water.
具体实施方式 Detailed ways
下面结合实施例及其附图,对本实用新型作进一步地详细说明,但本实用新型的实施方式不限于此。 The utility model will be described in further detail below in conjunction with the embodiments and accompanying drawings, but the implementation of the utility model is not limited thereto.
实施例1 Example 1
压水堆内置蒸汽稳压器隔热板,如图1和图2所示,包括由构成空气夹层2的双层奥氏体不锈钢板组成的隔热板本体1,以及设置在隔热板本体1上方与其一体成型且组合构成倒帽形复合结构的连接体3;所述隔热板本体1上则设置有圆筒形波动孔4。 The heat shield of the built-in steam pressurizer of the pressurized water reactor, as shown in Figure 1 and Figure 2, includes the heat shield body 1 composed of double-layer austenitic stainless steel plates forming the air interlayer 2, and the heat shield body 1 arranged on the heat shield body 1 and its upper part are integrally formed and combined to form a connecting body 3 of an inverted hat-shaped composite structure; the heat shield body 1 is provided with a cylindrical undulating hole 4 .
连接体3为圆环状结构,连接体3内径与隔热板本体1的外侧壁外径相同,隔热板本体1的外侧壁外径向上延伸,该连接体3固定在隔热板本体1外侧壁延伸部位且隔热板本体1与连接体3一体成型,该隔热板本体1与连接体3组合后即构成本实用新型中的倒帽形复合结构,如图1所示。 The connecting body 3 is a ring-shaped structure, the inner diameter of the connecting body 3 is the same as the outer diameter of the outer wall of the heat insulating board body 1, and the outer diameter of the outer wall of the heat insulating board body 1 extends upward, and the connecting body 3 is fixed on the heat insulating board body 1 The extended part of the outer wall and the heat shield body 1 and the connecting body 3 are integrally formed. After the heat shield body 1 and the connecting body 3 are combined, the inverted hat-shaped composite structure in the present invention is formed, as shown in FIG. 1 .
本实用新型中该隔热板本体1和连接体3为一体成型结构且均由奥氏体不锈钢材料制成。如图2所示,该压水堆内置蒸汽稳压器隔热板的内径约为2500mm,总厚度约为350mm,该双层奥氏体不锈钢板的厚度设置为约20mm,空气夹层2的厚度约为210mm;该隔热板本体1上的圆筒形波动孔4的直径约为140mm。将本实用新型的压水堆内置蒸汽稳压器隔热板焊接在反应堆压力容器顶盖封头内,其可适用于热功率为200~1000MW的一体化压水堆。 In the utility model, the heat shield body 1 and the connecting body 3 are integrally formed, and both are made of austenitic stainless steel. As shown in Figure 2, the internal diameter of the heat shield of the built-in steam pressurizer of the pressurized water reactor is about 2500 mm, and the total thickness is about 350 mm. The thickness of the double-layer austenitic stainless steel plate is set to about 20 mm, and the thickness of the air interlayer 2 It is about 210mm; the diameter of the cylindrical wave hole 4 on the heat shield body 1 is about 140mm. The heat insulation plate of the built-in steam pressurizer of the pressurized water reactor of the utility model is welded in the head of the top cover of the reactor pressure vessel, which is applicable to an integrated pressurized water reactor with a thermal power of 200-1000 MW.
实施例2 Example 2
本实施例与实施例1的区别在于:本实施例中优化了压水堆内置蒸汽稳压器隔热板的具体结构。 The difference between this embodiment and Embodiment 1 is that in this embodiment, the specific structure of the heat shield of the built-in steam pressurizer of the PWR is optimized.
如图1~图3所示,本实施例中该圆筒形波动孔4位于隔热板本体1的中央部位。本实施例中还增加了径向加劲板5、环向加劲板6以及金属反射层7,其具体设置方式如下: As shown in FIGS. 1 to 3 , the cylindrical undulation hole 4 is located at the center of the heat shield body 1 in this embodiment. In this embodiment, a radial stiffening plate 5, a circumferential stiffening plate 6 and a metal reflective layer 7 are also added, and the specific setting method is as follows:
本实施例中,该环向加劲板6的数量为四个,设置在空气夹层2内且位于圆筒形波动孔4与连接体3之间,如图3所示,该邻近圆筒形波动孔4的环向加劲板6厚度约40mm,其余环向加劲板6厚度约为20mm。 In this embodiment, the number of the hoop stiffeners 6 is four, which are arranged in the air interlayer 2 and between the cylindrical undulating hole 4 and the connecting body 3. As shown in FIG. 3 , the adjacent cylindrical undulating The thickness of the hoop stiffening plate 6 of the hole 4 is about 40 mm, and the thickness of the other hoop stiffening plates 6 is about 20 mm.
所述径向加劲板5的数量为八个,均匀分布在隔热板本体1上,该径向加劲板5的一端与邻近圆筒形波动孔4的环向加劲板6连接,另一端则延伸到连接体3位置处,如图2和图3所示。该径向加劲板5的厚度约为20mm。 The number of said radial stiffeners 5 is eight, which are evenly distributed on the heat insulation board body 1. One end of the radial stiffeners 5 is connected to the annular stiffener 6 adjacent to the cylindrical wave hole 4, and the other end is Extend to the position of connector 3, as shown in Figure 2 and Figure 3. The radial stiffener 5 has a thickness of about 20 mm.
通过上述径向加劲板5和环向加劲板6的共同作用,有效将空气夹层2分隔成33个空腔,进一步阻隔空气流动,降低热传导效率;同时该设置能够承受反应堆内高达21MPa的高压环境,有效增强耐压程度。 Through the joint action of the above-mentioned radial stiffening plate 5 and circumferential stiffening plate 6, the air interlayer 2 is effectively divided into 33 cavities, which further blocks air flow and reduces heat transfer efficiency; at the same time, this setting can withstand a high-pressure environment up to 21MPa in the reactor , effectively enhance the degree of pressure resistance.
为了能更好地隔绝热量传递,即,为了能有效降低辐照导致的热传递,所述空腔内水平叠放有波纹状镜面不锈钢箔片构成的金属反射层7,如图1所示,该金属反射层7的厚度约为0.1mm。 In order to better insulate heat transfer, that is, in order to effectively reduce the heat transfer caused by radiation, a metal reflective layer 7 made of corrugated mirror stainless steel foil is stacked horizontally in the cavity, as shown in Figure 1, The thickness of the metal reflective layer 7 is about 0.1mm.
实施例3 Example 3
本实施例与实施例1和实施例2的区别在于:本实施例将实施例1或2中的压水堆内置蒸汽稳压器隔热板应用到压水堆中,公开了一种利用实施例1或2中的隔热板构成一体化压水堆的结构,其具体结构如下: The difference between this embodiment and Embodiment 1 and Embodiment 2 is that this embodiment applies the built-in steam pressurizer heat shield of the pressurized water reactor in Embodiment 1 or 2 to the pressurized water reactor, and discloses a method for implementing The heat shield in Example 1 or 2 constitutes the structure of an integrated pressurized water reactor, and its specific structure is as follows:
一体化压水堆,包括具有顶盖封头11的反应堆压力容器8,位于反应堆压力容器8内的反应堆冷却剂过冷水9,位于反应堆冷却剂过冷水9上方的内置稳压器饱和水10,以及焊接在顶盖封头11内用于分隔反应堆冷却剂过冷水9和内置稳压器饱和水10的隔热板。 An integrated pressurized water reactor, comprising a reactor pressure vessel 8 with a top cover head 11, a reactor coolant supercooled water 9 located in the reactor pressure vessel 8, a built-in pressurizer saturated water 10 located above the reactor coolant supercooled water 9, And welded in the top cover head 11 is used to separate the reactor coolant supercooled water 9 and the built-in pressurizer saturated water 10 of the heat shield.
上述隔热板即为实施例1或实施例2中所述的压水堆内置蒸汽稳压器隔热板。 The above heat insulation board is the heat insulation board of the built-in steam pressurizer of the PWR described in Embodiment 1 or Embodiment 2.
上述实施例仅为本实用新型的优选实施例,并非对本实用新型保护范围的限制,但凡采用本实用新型的设计原理,以及在此基础上进行非创造性劳动而作出的变化,均应属于本实用新型的保护范围之内。 The foregoing embodiments are only preferred embodiments of the present utility model, and are not limitations of the protection scope of the present utility model, but all the design principles of the present utility model, and the changes made by non-creative work on this basis, all should belong to the present utility model. within the scope of the new protection.
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Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN104464841A (en) * | 2014-12-16 | 2015-03-25 | 中国核动力研究设计院 | Thermal insulation plate for built-in steam pressurizer of pressurized water reactor and integrated pressurized water reactor formed by thermal insulation plate |
| CN116110623A (en) * | 2022-12-16 | 2023-05-12 | 国科中子能(青岛)研究院有限公司 | Ultra-compact reactor system |
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Cited By (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN104464841A (en) * | 2014-12-16 | 2015-03-25 | 中国核动力研究设计院 | Thermal insulation plate for built-in steam pressurizer of pressurized water reactor and integrated pressurized water reactor formed by thermal insulation plate |
| CN116110623A (en) * | 2022-12-16 | 2023-05-12 | 国科中子能(青岛)研究院有限公司 | Ultra-compact reactor system |
| CN116110623B (en) * | 2022-12-16 | 2024-01-26 | 国科中子能(青岛)研究院有限公司 | Ultra-compact reactor system |
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