WO2017096614A1 - 核电站严重事故反应堆长期水源非能动pH值调节系统及方法 - Google Patents
核电站严重事故反应堆长期水源非能动pH值调节系统及方法 Download PDFInfo
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- G—PHYSICS
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- G21C9/00—Emergency protection arrangements structurally associated with the reactor, e.g. safety valves provided with pressure equalisation devices
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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
- G21C15/02—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices
- G21C15/08—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices from moderating material
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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
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- 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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- the invention belongs to the technical field of nuclear power, and more particularly to a long-term water source passive pH adjustment system and method for a serious accident reactor of a nuclear power plant.
- the safety injection pump of the safety injection system takes water from the displacement tank in the containment, and injects water into the reactor through a pipeline connected to the reactor.
- the reactor provides a cooling water source and operates for long periods of time to ensure the safety of the reactor.
- the safety injection system performs the functional phase, and needs to adjust the pH value of the water source in the displacement tank in the containment to prevent the radioactive iodine that has been trapped in the internal displacement tank from re-evaporating, and limit the water in the pool to the containment after the accident. Corrosion of equipment.
- the object of the present invention is to provide a long-term water source passive pH adjustment system and method for a serious accident reactor of a nuclear power plant, in order to adjust the water source by adding chemicals to the water source in the containment tank in a passive manner after a serious accident. pH value.
- the present invention provides a long-term water source passive pH adjustment system for a nuclear power plant severe accident reactor, which comprises:
- a reactor pressure vessel a debris interceptor, an internal displacement tank, disposed within the containment, and a water flow passage connecting the debris intercepting device and the inner displacement pool;
- the lowest position of the water flow channel is provided with a pH adjustment basket in which a chemical agent for adjusting the pH value is placed.
- the water flow channel comprising one or more return water pipes connected to the debris intercepting device and a room provided with an overflow port, the pH value
- the adjustment basket is set at the bottom of the room.
- the overflow port is disposed on the side wall of the room, and the overflow port is located above the pH adjustment basket.
- the reactor pressure vessel is connected to the inner displacement water tank through an injection water intake pipeline, an injection pump and an injection return water pipeline.
- the pH adjustment basket is set as a screen structure.
- the present invention also provides a long-term water source passive pH adjustment method for a nuclear power plant severe accident reactor, which comprises the following steps:
- the safety injection pump of the safety injection system takes water from the internal displacement tank and injects it into the reactor.
- the water flow channel comprising one or more return water pipes connected to the debris intercepting device and having an overflow In the mouth of the room, the pH adjustment basket is placed at the bottom of the room.
- the passive pH value of the long-term water source of the severe accident reactor of the nuclear power plant of the present invention As an improvement of the method for adjusting the passive pH value of the long-term water source of the severe accident reactor of the nuclear power plant of the present invention, after the water level rises to a certain height, the water is returned to the inner displacement tank through the overflow port on the side wall of the room, and the pH is adjusted to dissolve. The solvent of the value of the chemical enters the inner displacement tank.
- the overflow port is disposed on the side wall of the room, and the overflow port is located above the pH adjusting basket.
- the reactor pressure vessel is connected to the inner displacement water tank through an injection water intake pipeline, an injection pump and an injection return water pipeline.
- the pH adjustment basket is set as a screen structure.
- the long-term water source passive pH adjustment system and method for the severe accident reactor of the nuclear power plant of the invention has the following advantages:
- the safe injection system is used to circulate the water source formed by the water injection cooling of the reactor, so that the water flows through the specially designed flow channel, and the chemical source is added to the water source in the passive displacement tank to adjust the pH value of the water source in a passive manner. Keep it alkaline, prevent the radioactive iodine that has been trapped in the inner displacement tank from re-evaporating, and limit the corrosion of the water in the tank to the equipment inside the containment after the accident. It does not require any external power supply, nor does it require equipment such as safety-grade batteries in nuclear power plants. The structure is simple and reliable.
- FIG. 1 is a schematic structural view of a long-term water source passive pH adjustment system for a nuclear power plant severe accident reactor.
- the long-term water source passive pH adjustment system for the serious accident reactor of the nuclear power plant of the present invention comprises: a safety shell 60; a reactor pressure vessel 10 disposed in the containment vessel 60, a debris intercepting device 20, and an internal displacement material pool 50, And a water flow passage connecting the debris intercepting device 20 and the inner displacement pool 50, wherein the pH adjustment basket 402 is disposed at a lowest position of the water flow passage.
- the debris intercepting device 20 is used for filtering debris and falling off in the leaked water in the reactor to ensure the smooth flow of the water flow passage.
- the water flow passage includes one or more return water conduits 30 and a room 40 disposed below the debris intercepting device 20 for leaking water from the reactor filtered by the debris intercepting device 20. Import into room 40.
- the room 40 is for collecting water flowing in through one or more of the return water pipes 30, and a pH adjustment basket 402 is provided at the lowest position at the bottom.
- the pH adjustment basket 402 is a mesh structure in which a pH-adjusting chemical is placed.
- the water flooding the pH adjustment basket 402 can pass through the screen into the pH adjustment basket 402 and dissolve the pH adjusted chemical placed in the pH adjustment basket 402.
- An overflow port 404 is provided on the side wall of the room 40, and when the water level in the room 40 reaches a predetermined position, it flows into the inner displacement pool 50 through the overflow port 404. In the illustrated embodiment, the overflow port 404 is located above the pH adjustment basket 402.
- the pH adjustment basket 402 is disposed at the bottom of the room 40 in this specification, it will be understood by those skilled in the art that the pH adjustment basket 402 may be disposed at other locations of the water flow channel ( For example, the lowest point position of the return water pipe 30 can be ensured that the water in the water flow passage can sufficiently immerse and dissolve the chemical agent for adjusting the pH value in the pH adjusting basket 402.
- the internal displacement tank 50 provides a water source for the safety injection system.
- the reactor is connected to the internal displacement tank 50 through an injection water intake line 502, an injection pump 504, and an inlet return water line 506, and water is taken from the internal displacement tank 50 into the reactor. .
- the safety injection system amp pump 504 takes water from the internal displacement tank 50 and injects it into the reactor via an injection water line 502 and an inlet return line 506.
- the pH of the water source in the internal displacement tank 50 is adjusted to be alkaline by the cycle of steps 1) to 4).
- the long-term water source passive pH adjustment system and method for the severe accident reactor of the nuclear power plant of the invention has the following advantages:
- the safe injection system is used to circulate the water source formed by the reactor, so that the water flows through the specially designed flow channel, and the chemical source is added to the water source in the passive displacement tank in a passive manner to adjust the pH value of the water source. Maintaining alkalinity prevents the radioactive iodine that has been trapped in the internal displacement tank from re-evaporating, limiting the stress corrosion of the water in the pool after the accident. It does not require any external power supply, nor does it require equipment such as safety-grade batteries in nuclear power plants. The structure is simple and reliable.
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Abstract
一种核电站严重事故反应堆长期水源非能动pH值调节系统及方法,该pH值调节系统包括:安全壳(60);设置于安全壳(60)内的反应堆压力容器(10)、碎片拦截装置(20)、回水管道(30)、侧壁设有溢流口(404)且底部设有pH值调节篮(402)的房间(40),以及与房间(40)通过溢流口(404)连通的内置换料水池(50)。在严重事故后,该pH值调节系统利用安全注入系统对反应堆注水冷却形成的水循环流动,以非能动的方式向内置换料水池内的水源添加化学药剂以调节水源的pH值,不需要外部电源或核电站中的安全级蓄电池等设备,结构简单可靠。
Description
本发明属于核电技术领域,更具体地说,本发明涉及一种核电站严重事故反应堆长期水源非能动pH值调节系统及方法。
在具有安全壳内置换料水池的核电站中,当反应堆发生失水事故后,安全注入系统的安注泵从安全壳内置换料水池中取水,通过与反应堆相连的管线将水注入反应堆中,为反应堆提供冷却水源并长期运行以保证反应堆的安全。
安全注入系统执行功能阶段,需要调节安全壳内置换料水池内水源的pH值,以阻止已被捕集到内置换料水池中的放射性碘再次挥发,限制事故后水池中的水对安全壳内设备的腐蚀。
有鉴于此,确有必要提供一种核电站严重事故反应堆长期水源非能动pH值调节系统及方法,以在严重事故后以非能动的方式向安全壳内置换料水池内水源添加化学物以调节水源的pH值。
发明内容
本发明的目的在于:提供一种核电站严重事故反应堆长期水源非能动pH值调节系统及方法,以在严重事故后以非能动的方式向安全壳内置换料水池内水源添加化学物以调节水源的pH值。
为了实现上述发明目的,本发明提供了一种核电站严重事故反应堆长期水源非能动pH值调节系统,其包括:
安全壳;
设置于安全壳内的反应堆压力容器、碎片拦截装置、内置换料水池,以及
连通碎片拦截装置和内置换料水池的水流通道;
其中,水流通道的最低位置处设有放置有调节pH值的化学药剂的pH值调节篮。
作为本发明核电站严重事故反应堆长期水源非能动pH值调节系统的一种改进,所述水流通道包括连接碎片拦截装置的一条或多条回水管道和设有溢流口的房间,所述pH值调节篮设置在房间的底部。
作为本发明核电站严重事故反应堆长期水源非能动pH值调节系统的一种改进,所述溢流口设置于房间的侧壁上,且溢流口位于pH值调节篮的上方。
作为本发明核电站严重事故反应堆长期水源非能动pH值调节系统的一种改进,所述反应堆压力容器通过安注取水管线、安注泵和安注回水管线与内置换料水池相连。
作为本发明核电站严重事故反应堆长期水源非能动pH值调节系统的一种改进,所述pH值调节篮设置为筛网结构。
为了实现上述发明目的,本发明还提供了一种核电站严重事故反应堆长期水源非能动pH值调节方法,其包括以下步骤:
1)在安全壳内设置反应堆压力容器、碎片拦截装置、内置换料水池,以及连接碎片拦截装置和内置换料水池的水流通道,其中,水流通道的最低位置处设有放置有调节pH值的化学药剂的pH值调节篮;
2)当反应堆发生失水事故后,从反应堆压力容器中泄露的水通过碎片拦截装置流入水流通道并溶解pH值调节篮中调节pH值的化学药剂;
3)水流通道中的水位升高至一定高度后,流入与水流通道连通的内置换料水池,溶解有调节pH值的化学药剂的溶剂进入内置换料水池;以及
4)安全注入系统的安注泵从内置换料水池中取水,注入反应堆。
作为本发明核电站严重事故反应堆长期水源非能动pH值调节方法的一种改进,所述水流通道包括连接碎片拦截装置的一条或多条回水管道和设有溢流
口的房间,所述pH值调节篮设置在房间的底部。
作为本发明核电站严重事故反应堆长期水源非能动pH值调节方法的一种改进,水位升高至一定高度后,通过所述房间的侧壁上的溢流口返回内置换料水池,溶解有调节pH值的化学药剂的溶剂进入内置换料水池。
作为本发明核电站严重事故反应堆长期水源非能动pH值调节方法的一种改进,所述溢流口设置于房间的侧壁上,且溢流口位于pH值调节篮的上方。
作为本发明核电站严重事故反应堆长期水源非能动pH值调节方法的一种改进,所述反应堆压力容器通过安注取水管线、安注泵和安注回水管线与内置换料水池相连。
作为本发明核电站严重事故反应堆长期水源非能动pH值调节方法的一种改进,所述pH值调节篮设置为筛网结构。
相对于现有技术,本发明核电站严重事故反应堆长期水源非能动pH值调节系统及方法具有以下优点:
在严重事故后,利用安全注入系统对反应堆注水冷却形成的水源循环流动,使水流经特殊设计的流道,以非能动的形式向内置换料水池内水源添加化学物以调节水源的pH值,使其保持碱性,阻止已被捕集到内置换料水池中的放射性碘再次挥发,限制事故后水池中的水对安全壳内设备的腐蚀。不需要任何外部电源,也不需要核电站中的安全级蓄电池等设备,结构简单可靠。
下面结合附图和具体实施方式,对本发明核电站严重事故反应堆长期水源非能动pH值调节系统及方法进行详细说明,其中:
图1为本发明核电站严重事故反应堆长期水源非能动pH值调节系统的结构示意图。
为了使本发明的发明目的、技术方案及其技术效果更加清晰,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。
请参阅图1所示,本发明核电站严重事故反应堆长期水源非能动pH值调节系统包括:安全壳60;设置于安全壳60内的反应堆压力容器10、碎片拦截装置20、内置换料水池50,以及连通碎片拦截装置20和内置换料水池50的水流通道,其中,水流通道的最低位置处设有pH值调节篮402。
碎片拦截装置20用于过滤反应堆中泄露的水中的碎片、脱落物,确保水流通道的通畅。
在图示实施方式中,水流通道包括一条或多条回水管道30和房间40,回水管道30设置于碎片拦截装置20的下方,用于将经碎片拦截装置20过滤的反应堆中泄露的水导入房间40中。
房间40用于收集经一条或多条回水管道30流入的水,其底部最低位置处设有pH值调节篮402。pH值调节篮402为筛网性结构,其中放置有调节pH值的化学药剂。淹没pH值调节篮402的水可以通过筛网进入pH值调节篮402,并溶解放置于在pH值调节篮402中的调节pH值的化学药剂。房间40的侧壁上设有溢流口404,当房间40中的水位达到预定位置时,会经溢流口404流入内置换料水池50。在图示实施方式中,溢流口404位于pH值调节篮402的上方。
可以理解的是,虽然在本说明书中pH值调节篮402设置在房间40的底部,但是,本领域的技术人员可以理解的是,pH值调节篮402也可以设置在水流通道的其他位置处(例如回水管道30的最低点位置),只要能保证水流通道中的水能充分浸没和溶解pH值调节篮402中调节pH值的化学药剂即可。
内置换料水池50为安全注入系统提供水源,反应堆通过安注取水管线502、安注泵504和安注回水管线506与内置换料水池50相连,并从内置换料水池50中取水注入反应堆。
以下结合附图详细说明本发明核电站严重事故反应堆长期水源非能动pH值调节系统的工作原理:
1)当反应堆发生失水事故后,从反应堆压力容器10中泄露的水通过碎片拦截装置20、回水管道30返回设有pH值调节篮402和溢流口404的房间40;
2)随着设有pH值调节篮402的房间40内的水位逐渐升高,pH值调节篮402逐渐被淹没,水通过筛网进入pH值调节篮402并溶解pH值调节篮402中调节pH值的化学药剂;
3)设有pH值调节篮402的房间40内的水位升高至一定高度后,通过房间40侧壁上的溢流口404返回内置换料水池50,溶解有调节pH值的化学药剂的溶剂进入内置换料水池50;
4)安全注入系统的安注泵504从内置换料水池50中取水,并经安注取水管线502和安注回水管线506注入反应堆。
通过步骤1)至步骤4)的循环,以非能动的方式将内置换料水池50中水源的pH值调节至碱性。
相对于现有技术,本发明核电站严重事故反应堆长期水源非能动pH值调节系统及方法具有以下优点:
在严重事故后,利用安全注入系统对反应堆形成的水源循环流动,使水流经特殊设计的流道,以非能动的形式向内置换料水池内水源添加化学物以调节水源的pH值,使其保持碱性,阻止已被捕集到内置换料水池中的放射性碘再次挥发,限制事故后水池中的水对安全壳内设备的应力腐蚀。不需要任何外部电源,也不需要核电站中的安全级蓄电池等设备,结构简单可靠。
根据上述原理,本发明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。
Claims (11)
- 一种核电站严重事故反应堆长期水源非能动pH值调节系统,其特征在于,包括:安全壳;设置于安全壳内的反应堆压力容器、碎片拦截装置、内置换料水池,以及连通碎片拦截装置和内置换料水池的水流通道;其中,水流通道的最低位置处设有放置有调节pH值的化学药剂的pH值调节篮。
- 根据权利要求1所述的核电站严重事故反应堆长期水源非能动pH值调节系统,其特征在于,所述水流通道包括连接碎片拦截装置的一条或多条回水管道和设有溢流口的房间,所述pH值调节篮设置在房间的底部。
- 根据权利要求2所述的核电站严重事故反应堆长期水源非能动pH值调节系统,其特征在于,所述溢流口设置于房间的侧壁上,且溢流口位于pH值调节篮的上方。
- 根据权利要求1至3中任一项所述的核电站严重事故反应堆长期水源非能动pH值调节系统,其特征在于,所述反应堆压力容器通过安注取水管线、安注泵和安注回水管线与内置换料水池相连。
- 根据权利要求1所述的核电站严重事故反应堆长期水源非能动pH值调节系统,其特征在于,所述pH值调节篮设置为筛网结构。
- 一种核电站严重事故反应堆长期水源非能动pH值调节方法,其特征在于,包括以下步骤:1)在安全壳内设置反应堆压力容器、碎片拦截装置、内置换料水池,以及连接碎片拦截装置和内置换料水池的水流通道,其中,水流通道的最低位置处设有放置有调节pH值的化学药剂的pH值调节篮;2)当反应堆发生失水事故后,从反应堆压力容器中泄露的水通过碎片拦截装置流入水流通道并溶解pH值调节篮中调节pH值的化学药剂;3)水流通道中的水位升高至一定高度后,流入与水流通道连通的内置换料水池,溶解有调节pH值的化学药剂的溶剂进入内置换料水池;以及4)安全注入系统的安注泵从内置换料水池中取水,注入反应堆。
- 根据权利要求6所述的核电站严重事故反应堆长期水源非能动pH值调节方法,其特征在于,所述水流通道包括连接碎片拦截装置的一条或多条回水管道和设有溢流口的房间,所述pH值调节篮设置在房间的底部。
- 根据权利要求7所述的核电站严重事故反应堆长期水源非能动pH值调节方法,其特征在于,水位升高至一定高度后,通过房间侧壁上的溢流口返回内置换料水池,溶解有调节pH值的化学药剂的溶剂进入内置换料水池。
- 根据权利要求7所述的核电站严重事故反应堆长期水源非能动pH值调节方法,其特征在于,所述溢流口设置于房间的侧壁上,且溢流口位于pH值调节篮的上方。
- 根据权利要求7所述的核电站严重事故反应堆长期水源非能动pH值调节方法,其特征在于,所述反应堆压力容器通过安注取水管线、安注泵和安注回水管线与内置换料水池相连。
- 根据权利要求6-10中任一项所述的核电站严重事故反应堆长期水源非能动pH值调节方法,其特征在于,所述pH值调节篮设置为筛网结构。
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