CN106910537A - 一种用于保护堆外捕集器的保护装置 - Google Patents

一种用于保护堆外捕集器的保护装置 Download PDF

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CN106910537A
CN106910537A CN201710282466.9A CN201710282466A CN106910537A CN 106910537 A CN106910537 A CN 106910537A CN 201710282466 A CN201710282466 A CN 201710282466A CN 106910537 A CN106910537 A CN 106910537A
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pile
protection device
trap
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pile trap
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勾鸿量
杨勇
袁芳
黄小林
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Shanghai Nuclear Engineering Research and Design Institute Co Ltd
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    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C9/00Emergency protection arrangements structurally associated with the reactor, e.g. safety valves provided with pressure equalisation devices
    • G21C9/016Core catchers
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C9/00Emergency protection arrangements structurally associated with the reactor, e.g. safety valves provided with pressure equalisation devices
    • G21C9/001Emergency protection arrangements structurally associated with the reactor, e.g. safety valves provided with pressure equalisation devices against explosions, e.g. blast shields
    • 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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  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Structure Of Emergency Protection For Nuclear Reactors (AREA)

Abstract

本发明提供一种用于保护堆外捕集器的保护装置,其包括:隔热层、抵御蒸汽爆炸荷载的盖板和底部加强部件。本发明提供的用于保护堆外捕集器的保护装置,可以在堆外蒸汽爆炸荷载的作用下,保证堆外捕集器的结构完整性,使其继续发挥熔融物冷却和滞留的作用。解决了传统堆外捕集器只能用于干堆腔工况的问题,提高了堆外捕集器的适用范围,进一步保证了核电站在极端事故工况下的安全性。

Description

一种用于保护堆外捕集器的保护装置
技术领域
本发明涉及一种核电领域的抵御极限爆炸荷载作用的结构,具体涉及一种在堆腔内部用于堆外捕集器的保护装置。
背景技术
在严重事故的堆芯熔化过程中,堆芯熔融物会坍塌、掉落到压力容器下腔室,并加热压力容器下封头,从而产生非常严重的后果。为了冷却堆腔内的堆芯熔融物,消除安全壳超压和底板熔穿对安全壳完整性的威胁,国际上已经提出了许多熔融物堆外滞留(EVR)策略和堆外冷却措施。目前,应用最为广泛的EVR策略是设置堆外捕集器。针对堆外捕集器,国际上已做了大量的试验进行有效性论证,并在电厂设计中进行了实际应用。
然而,目前已有的核电厂EVR方案设计中,基本都是针对干堆腔工况,如果考虑湿堆腔状态,就不可避免地引入堆外蒸汽爆炸这一事故工况,这将直接影响堆外捕集器的安全性和工作性。所以,非常有必要设计一种能够抵御极限爆炸荷载作用下的核电特种结构,保护堆外捕集器在事故工况下能够正常运行。采用带有保护装置的改进堆外捕集器系统,能够有效抵御堆外熔融物对于系统的破坏作用,更好地保障核电站在极端事故工况下的安全。
传统的堆外捕集器并没有设置任何的保护装置,在堆外蒸汽爆炸作用下,很难继续发挥其作用,一旦堆外捕集器失效,后续的熔融物冷却和滞留就无法实现,这是目前堆外捕集器设计中最致命的缺点,也是业界亟待解决的问题。通过设置堆外捕集器保护装置,可以抵御堆外蒸汽爆炸的压力冲击,保护堆外捕集器的结构完整性;并且可以在反应堆正常运行条件下,作为保温层流道进水组件的支撑,并防止堆芯中子等对堆外捕集器产生影响。同时,在核电厂停堆大修期间,也可作为检修人员的操作平台。
根据发明人进行的查新结果,还未出现能达到在上述蒸汽爆炸荷载作用下保护堆外捕集器的相关装置。
发明内容
本发明针对现有技术的不足,提出一种用于保护堆外捕集器的保护装置。
用于保护堆外捕集器的保护装置包括:隔热层、抵御蒸汽爆炸荷载的盖板和底部加强部件。
优选地,所述隔热层由耐高温材料组成,直接安装在所述盖板的表面。
优选地,所述盖板由高强材料制成。
优选地,所述盖板由SA-508(3级2类)材料制成。
优选地,所述底板加强部件由高强材料制成
优选地,所述底板加强部件由SA-508(3级2类)材料制成。
优选地,所述底板加强部件分为横向加强部件和纵向加强部件,所述横向加强部件和所述纵向加强部件通过铆钉进行连接。
与现有技术相比,本发明具有以下有益效果:
本发明提供的用于保护堆外捕集器的保护装置,可以在堆外蒸汽爆炸荷载的作用下,保证堆外捕集器的结构完整性,使其继续发挥熔融物冷却和滞留的作用。解决了传统堆外捕集器只能用于干堆腔工况的问题,提高了堆外捕集器的适用范围,进一步保证了核电站在极端事故工况下的安全性:
(1)通过设置堆外捕集器保护装置,可以抵御堆外蒸汽爆炸的压力冲击,确保堆外捕集器的结构完整性;
(2)通过设置保护装置,打破了传统堆外捕集器只能用于干堆腔的限制,在保证安全的前提下,扩大了适用范围。
(3)在反应堆正常运行条件下,堆外捕集器保护装置可以作为保温层流道进水组件的支撑,并防止堆芯中子等对堆外捕集器产生影响;
(4)在核电厂停堆大修期间,保护装置也可作为检修人员的操作平台,方便操作。
(5)经保护装置的力学分析和完整性评估,保护装置的最大等效应变约为10.8%,小于材料的失效应变,可以有效保护堆外捕集器。
附图说明
图1为符合本发明实施例的用于保护堆外捕集器的保护装置的结构示意图。
图2为符合本发明实施例的用于保护堆外捕集器的保护装置的另一角度结构示意图。
图3为堆外捕集器保护装置实际布置图
具体实施方式
为使本发明的上述目的、特征和优点能够更加明显易懂,下面结合附图和具体实施方式对本发明作进一步详细的说明。
如图1、2所示,堆外捕集器包括隔热层1、抵御蒸汽爆炸荷载的盖板2和底部加强部件3&4。抵御蒸汽爆炸荷载的盖板所用材料为高强材料,如SA-508(3级2类),厚度较厚,如厚度为400mm。隔热层由耐高温材料构成,厚度如为50mm。底板加强部件亦由高强材料制成,如SA-508(3级2类)材料制成,等间距布置,如间隔为1900mm,分为横向加强部件和纵向加强部件,横向加强部件和纵向加强部件通过铆钉进行连接。
当极端事故发生时,由于堆外捕集器的设置,可以有效抵御堆外爆炸荷载的作用,保护装置的最大等效应变小于材料的限值。该保护装置适用于干、湿堆腔工况,极大地扩展了堆外捕集器的适用范围和安全性,并能够作为保温层流道进水组件的支撑以及大修期间的检修平台。
本发明实施例具有以下有益效果:
本发明实施例提供的用于保护堆外捕集器的保护装置,可以在堆外蒸汽爆炸荷载的作用下,保证堆外捕集器的结构完整性,使其继续发挥熔融物冷却和滞留的作用。解决了传统堆外捕集器只能用于干堆腔工况的问题,提高了堆外捕集器的适用范围,进一步保证了核电站在极端事故工况下的安全性:
(1)通过设置堆外捕集器保护装置,可以抵御堆外蒸汽爆炸的压力冲击,确保堆外捕集器的结构完整性;
(2)通过设置保护装置,打破了传统堆外捕集器只能用于干堆腔的限制,在保证安全的前提下,扩大了适用范围。
(3)在反应堆正常运行条件下,堆外捕集器保护装置可以作为保温层流道进水组件的支撑,并防止堆芯中子等对堆外捕集器产生影响;
(4)在核电厂停堆大修期间,保护装置也可作为检修人员的操作平台,方便操作。
(5)经保护装置的力学分析和完整性评估,保护装置的最大等效应变约为10.8%,小于材料的失效应变,可以有效保护堆外捕集器。
本说明书中各个实施例采用递进的方式描述,每个实施例重点说明的都是与其他实施例的不同之处,各个实施例之间相同相似部分互相参见即可。对于实施例公开的系统而言,由于与实施例公开的方法相对应,所以描述的比较简单,相关之处参见方法部分说明即可。
本领域技术人员可以对每个特定的应用来使用不同方法来实现所描述的功能,但是这种实现不应认为超出本发明的范围。
显然,本领域的技术人员可以对发明进行各种改动和变型而不脱离本发明的精神和范围。这样,倘若本发明的这些修改和变型属于本发明权利要求及其等同技术的范围之内,则本发明也意图包括这些改动和变型在内。

Claims (7)

1.一种用于保护堆外捕集器的保护装置,其特征在于,包括:隔热层、抵御蒸汽爆炸荷载的盖板和底部加强部件。隔热层布置在盖板上方,与盖板采用密封胶粘连接;底部加强部件位于盖板底部,与盖板采用焊接连接。
2.如权利要求1所述的用于保护堆外捕集器的保护装置,其特征在于,所述隔热层由耐高温材料组成,直接安装在所述盖板的表面。
3.如权利要求1所述的用于保护堆外捕集器的保护装置,其特征在于,所述盖板由高强材料制成。
4.如权利要求3所述的用于保护堆外捕集器的保护装置,其特征在于,所述盖板由SA-508(3级2类)材料制成。
5.如权利要求1所述的用于保护堆外捕集器的保护装置,其特征在于,所述底板加强部件由高强材料制成。
6.如权利要求5所述的用于保护堆外捕集器的保护装置,其特征在于,所述底板加强部件由SA-508(3级2类)材料制成。
7.如权利要求1所述的用于保护堆外捕集器的保护装置,其特征在于,所述底板加强部件分为横向加强部件和纵向加强部件,所述横向加强部件和所述纵向加强部件通过铆钉进行连接。横向和纵向加强部件皆位于盖板底部,与盖板采用焊接连接;横向与纵向加强部件之间通过铆钉进行连接。
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