CN116134550A - 核反应堆非能动反应度控制系统 - Google Patents
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Abstract
公开了一种非能动核反应堆控制装置。所述非能动核反应堆控制装置包括：密封的室，所述密封的室包括储蓄器和与所述储蓄器流体连通的管。熔盐在所述密封的室内，所述熔盐是一价金属卤化物与一种或多种镧系元素的氟化物或氯化物和/或铪的氟化物或氯化物的低共熔混合物。气体在所述密封的室内，并且所述气体不与所述熔盐反应。
Description
技术领域
本发明涉及核反应堆的控制装置。
背景技术
核裂变反应堆依赖于具有在正常运行下精确为1的核反应度(k有效)。即使稍微高于1的反应度也导致来自裂变的能量生成指数增加，而低于1的反应度导致能量生成指数下降到零。
对反应度的这种非常精确的控制通常通过无需人工或自动控制的非能动系统与能动系统的组合来实现。最重要的非能动系统是反应堆必须具有负的反应性温度系数，使得如果功率增大，则温度升高并且反应度下降。另一种非能动系统是将“可燃的”中子吸收物(中子吸收剂)掺入到反应堆堆芯中，这一开始抑制反应度，但是，随着它们被中子吸收所毁坏，渐减地抑制反应度。
能动系统典型地是机械控制棒，其将中子吸收材料插入到反应堆堆芯中，或者取出中子吸收材料。
对于这些能动系统的依赖是安全危害的主要来源，因为任何机械系统都可能出故障或被不恰当地使用。导致控制棒系统的不正确使用的人为错误最终触发了切尔诺贝利灾难。
因此，代替或补足控制棒的非能动操作系统多年来一直是核工业的目标。IAEA文件NR-T-1.16“用于快中子反应堆的非能动关闭系统(Passive Shutdown Systems forFast neutron reactors)”中提供了对这类非能动系统的现状的出色概括。
所描述的在机械上最简单的系统是：熔融的锂金属在加热时膨胀并受迫沿着管向下进入反应堆堆芯中。这是一种具有极高可靠性的精妙系统，并且是可逆的，使得其可以用于连续控制反应堆的功率来将输出冷却剂温度保持在限定范围内。
遗憾地，这种基于锂的装置具有以下缺点：当Li-6吸收中子时，其发射氚和氦原子。这相当快速地使系统加压，而更关键地，氚是高度放射性的且移动性非常强的气体，因此它的产生造成了另外的安全危害。
迄今为止的大部分研究都是关于在轻水反应堆或熔融金属冷却的快中子反应堆中的非能动反应度控制装置。近年来，对其中燃料或冷却剂是熔盐的熔盐反应堆的关注大量增加。这些反应堆远远优于其他反应堆，部分因为熔盐燃料的膨胀造成异常强的负反应度系数，这使反应度强烈地自稳定。然而，对于基于锂的非能动反应度控制系统的使用，熔盐带来问题，因为所产生的氚在熔盐中是高移动性的，并且实际上会扩散通过金属壁，使得对它的安全密封是极具挑战性的。
因此，仍需要一种在基于熔盐的反应堆中简单、有效、可靠的非能动反应度控制系统，其不造成氚管理问题。
发明内容
根据第一方面，提供了一种非能动核反应堆控制装置。所述非能动核反应堆控制装置包括：密封的室，所述密封的室包括储蓄器和与所述储蓄器流体连通的管。熔盐在所述密封的室内，所述熔盐是一价金属卤化物与一种或多种镧系元素的氟化物或氯化物和/或铪的氟化物或氯化物的低共熔混合物。气体在所述密封的室内，并且所述气体不与所述熔盐反应。
根据第二方面，提供了一种核反应堆，所述核反应堆包括反应堆堆芯和根据第一方面所述的非能动核反应堆控制装置，其中至少所述密封的室的所述管延伸到所述反应堆堆芯中。
附图说明
图1是一种反应堆堆芯的示意图；
图2是一种非能动核反应堆控制装置在三种温度下的示意图；
图3是一种备选的反应堆堆芯的示意图。
具体实施方式
非能动反应度控制装置包括：熔盐的储蓄器，所述熔盐含有与一价盐混合以形成低熔点的低共熔混合物的来自镧系元素家族或铪的氟化物或氯化物盐形式的强中子吸收物。
镧系元素在辐射下不生成显著的氚或氦。不过，它们是高熔点金属，因此不能在反应度控制装置中简单地代替为人熟知的锂。转化为氟化物或氯化物盐并且与一价金属卤化物形成低共熔盐混合物将熔点降低至可用的水平。
该装置类似于水银温度计。储蓄器或温度计球状增大部分位于热的出口冷却剂(或与燃料组合的冷却剂)盐中，并且窄的管或温度计主干进入到反应堆堆芯中。主干含有惰性气体(即不与熔盐明显反应的气体)，所述惰性气体在中子吸收盐沿着主干向下膨胀时被压缩，并且在储蓄器冷却时，该气体的压力使中子吸收盐返回到球状增大部分。对于在热谱反应堆中的使用来说特别有用的镧系元素是钆、铕、钐，它们各自具有几千靶恩的中子吸收截面。然而，也可以使用其他吸收性没那么强的镧系元素比如镝、铒或者铪，并且也可以使用多种镧系元素的混合物，在需要降低盐的中子吸收以使得其对于中子来说是“灰色”而不是“黑色”的情况下，这可以是有利的。
对于快中子反应堆来说，最有效的镧系元素是铕和铪，但是同样地，吸收性没那么强的镧系元素的混合物可以具有实用性。
存在两种可行的避免熔盐流体柱在膨胀和收缩期间中断的方法。在第一种方法中，储蓄器位于管下方，并且管大致朝上取向(即，使得柱将由重力保持，并且熔盐向上膨胀)。在第二种方法中，管足够窄以使熔盐流体柱在倒置时保持完整——所需的半径将取决于熔盐流体与管的内表面之间的接触角。在第一种情况下，管可以具有任何所需宽度。在第二种情况下，管可以具有任何所需取向。
在任一种情况下，对于熔盐流体柱在膨胀和收缩期间保持完整来说需要的是，含有该熔盐流体柱的主干的表面与熔盐流体具有大的接触角，并且尤其，该表面不被流体润湿。在金属表面的润湿是个问题的情况下，这可以通过将熔盐与之具有高接触角的涂料沉积在材料的润湿表面上来改善。热解碳是一种这样的合适涂料。
实施例1
由含有氟化铀和氟化钠的混合物的一系列钼管形成核反应堆堆芯。铀富含U235同位素。这些管位于石墨块中的通道中，并且冷却剂液体向上通过在石墨和管之间的通道。
图1示出了在石墨减速的以液体熔盐为燃料的反应堆堆芯中的非能动反应度装置100的阵列。
如图1所示，非能动反应度装置的储蓄器101位于管中的燃料盐110的液面上方。装置的主干102向下突出穿过在石墨120和管之间的环形空间，并且终止于燃料管的底部。图2示出了在不同冷却剂输出温度T1＜T2＜T3下中子吸收流体103在球状增大部分101和主干102中的位置。每个非能动反应度装置的其余部分都含有不与中子吸收流体反应的气体104。左侧是在低于正常反应堆工作温度的温度下的装置，中间是在正常工作温度下的装置，并且右侧是高于正常工作温度。
实施例2
由含有氟化铀和氟化钠的混合物的一系列钼管形成核反应堆堆芯。铀富含U235同位素。这些管位于石墨块中的通道中，并且冷却剂液体向下通过在石墨和管之间的通道。
图3示出了一种布置方式，其中非能动反应堆控制装置的球状增大部分301位于燃料管下方(即燃料盐310)下方，并且主干302在石墨减速剂320和燃料盐310之间向上延伸。
Claims (7)
1.一种非能动核反应堆控制装置，所述非能动核反应堆控制装置包括：
密封的室，所述密封的室包括：
储蓄器；
与所述储蓄器流体连通的管；
在所述密封的室内的熔盐，所述熔盐是以下各项的低共熔混合物：
一价金属卤化物，和
以下的氟化物或氯化物：
一种或多种镧系元素；和/或
铪；
在所述密封的室内的不与所述熔盐反应的气体。
2.根据权利要求1所述的非能动核反应堆控制装置，其中所述密封的室的内表面是不可被所述熔盐润湿的。
3.根据权利要求2所述的非能动核反应堆控制装置，其中所述密封的室的内表面涂覆有热解碳。
4.根据任一项前述权利要求所述的非能动核反应堆控制装置，其中所述熔盐包含钆、铕、钐或铪中的任何一种或多种的氟化物或氯化物。
5.一种核反应堆，所述核反应堆包括反应堆堆芯和根据任一项前述权利要求所述的非能动核反应堆控制装置，其中至少所述密封的室的所述管延伸到所述反应堆堆芯中。
6.根据权利要求5所述的核反应堆，其中所述密封的室的所述储蓄器被定位为使得冷却剂从所述反应堆堆芯流动到所述密封的室的所述储蓄器。
7.根据权利要求5或6所述的核反应堆，其中所述反应堆堆芯包括一个或多个石墨块和在所述一个或多个石墨块内的多个通道，每个通道都包含含有可裂变材料的燃料管，并且所述多个通道的至少一个子集包含根据权利要求1至4中任一项所述的非能动核反应堆控制装置的管。
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| US20230260668A1 (en) | 2023-08-17 |
| KR20230065327A (ko) | 2023-05-11 |
| GB202014182D0 (en) | 2020-10-21 |
| CA3192273A1 (en) | 2022-03-17 |
| JP2023540604A (ja) | 2023-09-25 |
| CN116134550B (zh) | 2024-04-12 |
| EP4211704A1 (en) | 2023-07-19 |
| US11862354B2 (en) | 2024-01-02 |
| WO2022053374A1 (en) | 2022-03-17 |
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