CN108885911A - 核反应堆的泵/热交换器组件 - Google Patents

核反应堆的泵/热交换器组件 Download PDF

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CN108885911A
CN108885911A CN201780007377.1A CN201780007377A CN108885911A CN 108885911 A CN108885911 A CN 108885911A CN 201780007377 A CN201780007377 A CN 201780007377A CN 108885911 A CN108885911 A CN 108885911A
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heat exchanger
pump
axis
nuclear reactor
exchanger assemblies
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CN108885911B (zh
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L·奇诺蒂
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Water Conservancy Mining Nuclear Energy Co
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    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C15/00Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
    • G21C15/24Promoting flow of the coolant
    • G21C15/243Promoting flow of the coolant for liquids
    • G21C15/247Promoting flow of the coolant for liquids for liquid metals
    • FMECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
    • F04POSITIVE - DISPLACEMENT MACHINES FOR LIQUIDS; PUMPS FOR LIQUIDS OR ELASTIC FLUIDS
    • F04DNON-POSITIVE-DISPLACEMENT PUMPS
    • F04D29/00Details, component parts, or accessories
    • F04D29/04Shafts or bearings, or assemblies thereof
    • F04D29/043Shafts
    • FMECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
    • F04POSITIVE - DISPLACEMENT MACHINES FOR LIQUIDS; PUMPS FOR LIQUIDS OR ELASTIC FLUIDS
    • F04DNON-POSITIVE-DISPLACEMENT PUMPS
    • F04D29/00Details, component parts, or accessories
    • F04D29/58Cooling; Heating; Diminishing heat transfer
    • F04D29/586Cooling; Heating; Diminishing heat transfer specially adapted for liquid pumps
    • F04D29/5866Cooling at last part of the working fluid in a heat exchanger
    • FMECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
    • F04POSITIVE - DISPLACEMENT MACHINES FOR LIQUIDS; PUMPS FOR LIQUIDS OR ELASTIC FLUIDS
    • F04DNON-POSITIVE-DISPLACEMENT PUMPS
    • F04D7/00Pumps adapted for handling specific fluids, e.g. by selection of specific materials for pumps or pump parts
    • F04D7/02Pumps adapted for handling specific fluids, e.g. by selection of specific materials for pumps or pump parts of centrifugal type
    • F04D7/06Pumps adapted for handling specific fluids, e.g. by selection of specific materials for pumps or pump parts of centrifugal type the fluids being hot or corrosive, e.g. liquid metals
    • F04D7/065Pumps adapted for handling specific fluids, e.g. by selection of specific materials for pumps or pump parts of centrifugal type the fluids being hot or corrosive, e.g. liquid metals for liquid metal
    • FMECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
    • F04POSITIVE - DISPLACEMENT MACHINES FOR LIQUIDS; PUMPS FOR LIQUIDS OR ELASTIC FLUIDS
    • F04DNON-POSITIVE-DISPLACEMENT PUMPS
    • F04D7/00Pumps adapted for handling specific fluids, e.g. by selection of specific materials for pumps or pump parts
    • F04D7/02Pumps adapted for handling specific fluids, e.g. by selection of specific materials for pumps or pump parts of centrifugal type
    • F04D7/08Pumps adapted for handling specific fluids, e.g. by selection of specific materials for pumps or pump parts of centrifugal type the fluids being radioactive
    • FMECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
    • F22STEAM GENERATION
    • F22BMETHODS OF STEAM GENERATION; STEAM BOILERS
    • F22B1/00Methods of steam generation characterised by form of heating method
    • F22B1/02Methods of steam generation characterised by form of heating method by exploitation of the heat content of hot heat carriers
    • F22B1/06Methods of steam generation characterised by form of heating method by exploitation of the heat content of hot heat carriers the heat carrier being molten; Use of molten metal, e.g. zinc, as heat transfer medium
    • F22B1/063Methods of steam generation characterised by form of heating method by exploitation of the heat content of hot heat carriers the heat carrier being molten; Use of molten metal, e.g. zinc, as heat transfer medium for metal cooled nuclear reactors
    • FMECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
    • F22STEAM GENERATION
    • F22BMETHODS OF STEAM GENERATION; STEAM BOILERS
    • F22B37/00Component parts or details of steam boilers
    • F22B37/02Component parts or details of steam boilers applicable to more than one kind or type of steam boiler
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C15/00Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
    • G21C15/24Promoting flow of the coolant
    • G21C15/243Promoting flow of the coolant for liquids
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C1/00Reactor types
    • G21C1/02Fast fission reactors, i.e. reactors not using a moderator ; Metal cooled reactors; Fast breeders
    • G21C1/03Fast fission reactors, i.e. reactors not using a moderator ; Metal cooled reactors; Fast breeders cooled by a coolant not essentially pressurised, e.g. pool-type reactors
    • YGENERAL 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
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02BCLIMATE CHANGE MITIGATION TECHNOLOGIES RELATED TO BUILDINGS, e.g. HOUSING, HOUSE APPLIANCES OR RELATED END-USER APPLICATIONS
    • Y02B30/00Energy efficient heating, ventilation or air conditioning [HVAC]
    • Y02B30/52Heat recovery pumps, i.e. heat pump based systems or units able to transfer the thermal energy from one area of the premises or part of the facilities to a different one, improving the overall efficiency
    • YGENERAL 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
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear fission reactors

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  • Engineering & Computer Science (AREA)
  • General Engineering & Computer Science (AREA)
  • Physics & Mathematics (AREA)
  • Mechanical Engineering (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Thermal Sciences (AREA)
  • Plasma & Fusion (AREA)
  • Life Sciences & Earth Sciences (AREA)
  • Sustainable Development (AREA)
  • Sustainable Energy (AREA)
  • Structures Of Non-Positive Displacement Pumps (AREA)

Abstract

本发明涉及一种核反应堆(1)的泵/热交换器组件(5),所述核反应堆(1)特别是液态金属冷却核反应堆,泵(6)的特征在于用于驱动叶轮(15)的轴(14)被***热交换器(8)内部的壳(9)中,并且在所述热交换器的管束的底部部分处具有较小的横截面,并且具有逐渐增加到所述热交换器(8)的管束的顶部部分处的最宽横截面的横截面。同时,所得到的叶轮轴的轴向轮廓被设计成使所述热交换器(8)的管束(20)内部的主流体的流量均匀地分布,并且为泵(6)提供高机械惯性。

Description

核反应堆的泵/热交换器组件
技术领域
本发明涉及核反应堆的泵/热交换器组件,所述核反应堆特别是液态金属冷却核反应堆。
特别地,本发明涉及泵/热交换器组件,所述泵/热交换器组件包括:主循环泵,即对反应堆的主冷却流体起作用;以及主热交换器,主流体在所述主热交换器中循环,并且在所述主热交换器内部容纳主流体的循环泵。
本发明还涉及核反应堆,特别是配备有所述泵/热交换器组件的液态金属冷却核反应堆,所述泵/热交换器组件对反应堆的主冷却流体起作用。
背景技术
意大利专利申请No.MI2007A001685(随后扩展到国际专利申请WO2009/024854)、No.MI2008A000766(国际专利申请WO2009/040644)以及GE2015A000036(国际专利申请WO2016/147139)示出了此类型的泵/热交换器组件,在所述泵/热交换器组件内部容纳轴和泵叶轮。
文件US4216821也示出了此类型的解决方案。
这样的解决方案是极其紧凑的,但并非没有缺点,特别是在主流量分布方面。由于管束供给是径向的,所以当主流体在热交换器的供给区域中自底向顶传递时,主流体的轴向速度下降。此轴向速度下降对应于较高的压力,因此对应于热交换器的上部部分相对于热交换器的下部部分中的超压力。
发明内容
本发明的一个目的是提供一种用于核反应堆的泵/热交换器组件,所述泵/热交换器组件允许克服已知解决方案的缺点且具有另一些安全优点。
因此,本发明涉及如所附权利要求1中限定的核反应堆的泵/热交换器组件,以及如所附权利要求6中限定的核反应堆。
本发明另一些特性被限定在从属权利要求中。
基本上,本发明的特征在于泵/热交换器组件的泵的叶轮轴的特定几何形状。事实上,根据本发明,叶轮轴具有优化的轴向轮廓,以便于克服现有技术的上述缺点。
附图说明
参考附图中的图,通过非限制性实施方案的方式描述本发明,在附图中:
图1是根据本发明的设置有至少一个具有叶轮轴的泵/热交换器组件的核反应堆的纵向截面的部分示意图;
图2是图1中的泵/热交换器组件的纵向截面和放大比例的示意图;
图3是图2中的泵/热交换器组件的细节的纵向截面的示意图,并且示出了泵的叶轮轴的一个不同实施方案;以及
图4是沿着图3中的平面A-A的横截面的示意图。
具体实施方式
参考图1-图2,核反应堆1包括由顶部3覆盖且包含堆芯4的主容器2。一个或多个泵/热交换器组件5被容纳在容器2的内部;每个泵/热交换器组件5包括用于使反应堆1的主冷却流体7循环的泵6和热交换器8。优选地,主流体7是液态重金属,例如铅。在容器2中的主流体7上方存在填充气体(blanket gas)。
热交换器8优选地是壳管式热交换器并且具有管束20,该管束20占据内壳9外部的环形区域,该内壳9设置有孔10并且限定内部体积,在该内部体积内容纳泵6的部件,并且特别是容纳圆柱形壳11和叶轮15的轴14,所述圆柱形壳11设置有孔12且充当泵6的扩散器13的支撑件。在圆柱形壳11的内部和轴14的外部之间存在供给管道16。泵16的马达17和机械地支撑轴14的机械轴承18被定位在反应堆的顶部3上方。
在反应堆1的正常操作条件下,离开堆芯4的主流体7在连接管道19内运送且由循环泵6的叶轮15推进,自底向上流过供给管道16,然后流经圆柱形结构11的孔12,流经壳9的孔10并且径向地流经管束20。
泵6的特征在于,叶轮15的轴14具有轴向可变横截面。轴14在热交换器8的管束20的底部部分处具有最小直径,并且具有在向上方向上直到管束20的顶部部分增加的直径,因此,供给管道16在主流体的流量较大的下部部分中具有较大的横截面,并且在流量较小的上部部分中具有较小的横截面。
除了热交换器8的管束20的实施方式和设计要求,泵6的轴14的轮廓将被成形为使管道16的截面(意为与轴14的旋转轴线正交的横截面)大致与管束20的上升部分的高度h成比例。例如,轴14的轮廓可以在管束20的底部水平下方和顶部水平上方是圆柱形的,并且在点B和点C之间是旋转抛物面,点B和点C分别对应于管束20的底部水平和顶部水平。
轴14可以完全由结构材料制成的实心件构成,如图1和图2中示出的,或者如图3和图4中详细示出的,泵6的轴14可以是中空的并且设置有内部纵向腔23。
在此情况下,中空的轴14在底部部分中轴向地装配有管道21,以允许主流体7还借助于其他管道22进入腔23内;在顶部部分中还装配管道24,以允许来自于反应堆1的顶部的气体流出且允许用主流体7填充到轮廓25,该轮廓25的形状还是叶轮15的旋转速度的函数。
提供了呈十字形布置且与轴14成整体的金属板26,以整体地夹带包含在轴内部的主流体进入旋转。
本发明的优点从以上描述中清楚地显现。
-泵/热交换器组件5构成一个紧凑单元。
-轴14的成形轮廓允许以可以均匀供给热交换器8的方式来校准主流体7在管道16中的轴向速度。特别地,可以使主流体7在向上供给管道16中的向上速度恒定,或可以根据热交换器8的设计的流量分布要求来调整向上速度。
-对壳11内部的空间的充分利用允许创建高机械刚度和惯性的轴14。高机械刚度使得能够避免使用浸没在主流体中的用于泵6的浮动轴承;叶轮15的轴14将仅由放置在反应堆的顶部3上方的机械轴承18支撑。在切断对泵6的电功率供应的情况下,高机械惯性对堆芯4从强制循环到自然循环的逐渐通过是必要的。轴14的高机械惯性避免了必须在反应堆1的顶部3(一个挤满了许多部件的区域)上添加飞轮。
-用主流体7填充的中空轴14对于用高密度主流体7(诸如,铅)冷却的反应堆是特别有利的,因为它同时提供了轻轴和比钢制实心轴更高的机械惯性。

Claims (6)

1.一种核反应堆(1)的泵/热交换器组件(5),所述核反应堆(1)特别是液态金属冷却核反应堆,所述泵/热交换器组件(5)包括一个泵(6)和一个热交换器(8),所述泵(6)具有一个叶轮(15)和一个用于驱动所述叶轮(15)的轴(14),并且所述轴(14)被***所述热交换器(8)内部的内壳(9)中;所述泵/热交换器组件(5)的特征在于,所述叶轮(15)的轴(14)在所述热交换器(8)的管束(20)的底部部分处具有较小的横截面并且具有逐渐增加到所述热交换器(8)的管束(20)的顶部部分处的最宽横截面的横截面。
2.根据权利要求1所述的泵/热交换器组件,其中所述轴(14)具有被成形为类似面向所述热交换器(8)的管束(20)的旋转抛物面的轴向轮廓。
3.根据权利要求1或2所述的泵/热交换器组件,其中所述轴(14)是实心的并且完全由结构材料制成。
4.根据权利要求1或2所述的泵/热交换器组件,其中所述轴(14)是中空的,且在所述轴(14)自身的旋转轴线上轴向地设置有位于下部部分中的第一管道(21)和位于上部部分中的第二管道(24),以在使用中将腔(23)与所述上部部分中所述反应堆(1)的填充气体和所述下部部分中的主冷却剂(7)液压连通。
5.根据权利要求4所述的泵/热交换器组件,其中所述轴(14)具有内腔(23),所述内腔(23)设置有与所述轴(14)成整体的十字形布置的金属板(26)。
6.一种核反应堆(1),所述核反应堆(1)特别是液态金属冷却核反应堆,其特征在于,所述核反应堆(1)包括至少一个根据前述权利要求之一所述的泵/热交换器组件(5)。
CN201780007377.1A 2016-01-19 2017-01-19 核反应堆的泵和热交换器组件 Active CN108885911B (zh)

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PCT/IB2017/050287 WO2017125874A1 (en) 2016-01-19 2017-01-19 Nuclear reactor pump/heat exchanger assembly

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WO2009024854A2 (en) * 2007-08-22 2009-02-26 Del Nova Vis S.R.L. Nuclear reactor with compact primary heat exchanger

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US20190252084A1 (en) 2019-08-15
PL3405959T3 (pl) 2020-06-15
US11387009B2 (en) 2022-07-12
EP3405959A1 (en) 2018-11-28
EP3405959B1 (en) 2019-11-27
ITUB20160544A1 (it) 2017-07-19
WO2017125874A1 (en) 2017-07-27
HUE048420T2 (hu) 2020-07-28
CN108885911B (zh) 2022-09-02

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