CN1134024A - 原子核反应堆的永久性池腔密封装置 - Google Patents

原子核反应堆的永久性池腔密封装置 Download PDF

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CN1134024A
CN1134024A CN95115370A CN95115370A CN1134024A CN 1134024 A CN1134024 A CN 1134024A CN 95115370 A CN95115370 A CN 95115370A CN 95115370 A CN95115370 A CN 95115370A CN 1134024 A CN1134024 A CN 1134024A
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seal
seal pad
ring
refuel
seal plate
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CN1105390C (zh
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金仁容
李炆郁
李珪万
黄祯气
辛太明
金范植
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Korea Power Engineering Co., Inc.
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Korea Atomic Energy Research Institute KAERI
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    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C13/00—Pressure vessels; Containment vessels; Containment in general
    • G21C13/02—Details
    • G21C13/028—Seals, e.g. for pressure vessels or containment vessels
    • 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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  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Gasket Seals (AREA)

Abstract

一种原子核安全壳结构设有跨越反应堆容器和燃料更换池壁之间的环形空隙而延伸的永久性池腔密封装置，密封板有一支撑圈，其圆柱部分将外密封圈焊在埋置圈上，J形挠性圈联接在密封板上以允许热膨胀和收缩过程中容器的运动，密封板的内部悬伸于J形挠性圈之上，匹配的出入孔和出入孔盖形成通向池腔的入口，密封板下有多个支撑臂，每个支撑臂有校平螺旋以调整密封板的水平。这提供了一个允许燃料更换池的注满的永久性池腔密封装置，仅在需要时拆下出入孔盖。

Description

原子核反应堆的永久性池腔密封装置
本发明涉及一种用于原子核反应堆的永久性池腔密封装置。
增压轻水反应堆是一种通常具有高度可靠实现性的常规生产，在这个反应堆里，反应堆容器设置在燃料更换池壁内和由安全壳内的混凝土防护结构形成的燃料更换池腔壁中，燃料更换池腔内设置有用于监测反应度的仪器。燃料更换池和燃料更换池腔能适应生产过程中反应堆的热膨胀并提供一条空气从反应堆容器底部流动的通路，在给反应堆更换燃料之前，在拆下反应堆容器端部的同时向燃料更换池注满含硼酸水以形成中子屏蔽。为保护燃料更换池腔内的仪器，有必要在注水前在池腔上安装一个密封板。在反应堆的正常工作过程中，反应堆容器易发生径向和轴向的热膨胀，经常用于燃料更换操作的密封板在燃料更换后不能被留在反应堆容器和混凝土防护结构的燃料更换池底板的周围，因为它们不能适应反应堆容器的热膨胀。所以人们试图开发一种永久性池腔密封装置，使其在燃料更换完毕后无需拆下。
本发明提供一个原子核反应堆安全壳结构，其中，一个永久性池腔密封装置跨越位于一个有圆周壁与一个水平延伸凸缘的反应堆容器和安全壳内的混凝土防护结构构成的燃料更换池壁之间的环形空隙而延伸。密封板包括一个J形挠性圈和一个支撑圈，挠性圈内侧朝下而水平延伸的部分焊接到内密封圈上，该密封圈用密封装置栓固并焊到反应堆容器凸缘上，支撑圈外侧的朝下延伸的圆柱形部分焊接到外密封圈上，该密封圈用密封装置栓固并焊接到埋置在燃料更换池底板内的圈上。J形挠性圈允许了热膨胀和收缩过程中反应堆容器的运动。永久性池腔密封装置必须有强度和挠性，永久性池腔密封件必须在结构上有足够的强度以经受得住水的重量和可能由于疏忽掉落在其上的重物的碰撞，且确保不会发生防护水的完全或突然丧失，并且最好能牢固地保持密封的完整性。密封板的内部悬伸于J形挠性圈之上，使之不会遭到坠落物落在其上。永久性池腔密封装置也要在结构上有足够的挠性以适应在反应堆工作过程中相对于混凝土防护结构的反应堆容器的径向和轴向的热膨胀和收缩并牢固地保持密封的完整性。匹配的出入孔和密封装置上的出入孔盖形成通向燃料更换池腔的入口。密封板下面设置有多个支撑臂，每个支撑臂至少有一个校平螺旋调整密封板的水平。这就提供了一个允许为燃料更换而注满燃料更换池的永久性池腔密封装置，仅在需要时拆下普通反应堆工作所使用的出入孔盖。
结合附图对本发明进行详尽描述可以更好地理解本发明。
图1是本发明的正视图；
图2是本发明的平面图；
图3是沿图2的1-1线穿过出入孔盖截断的横截面图。
永久性池腔密封装置通常由密封板10，内密封圈13，外密封圈14，J形挠性圈11，支撑圈12，校平螺旋支撑臂15，校平螺旋16和用于覆盖和密封密封板10上的出入孔32的装置。
密封板10最好选用不锈钢制成，其厚度为1.5英寸，用以抵挡水的重量和燃料更换过程中燃料的碰撞。密封板10由多个弧形板组成，这些板在反应堆容器26周围彼此相邻设置组成密封板10，这些弧形板在它们分别焊接到支撑圈12和J形挠性圈11之前拼接焊在一起。围绕密封板10的周边上彼此留有一定间距地设有许多出入孔32，出入孔32形成通向设在反应堆容器26和混凝土防护结构35之间的燃料更换池腔下部的核反应仪器的出入口，并且允许了反应堆正常工作过程中反应堆容器26下方的空气循环。密封板10中的每个出入孔32设有带有O圈31的凹槽30以形成围绕其周边的密封，每个出入孔盖28有一个孔29和孔塞33，孔塞由螺栓34紧固并且设有在注满前检查密封情况的装置。密封板10带有支撑圈12和从那里轴向延伸的J形挠性圈11，支撑圈12最好选用与密封板10相同的材料制成。支撑圈10由多个弧形板组成，弧形板在燃料更换池底板23上彼此相邻设置而形成支撑圈10，弧形板在焊接到密封板10之前拼接焊在一起。J形挠性圈11必须在结构上有足够的挠性以适应反应堆容器26的径向和轴向的热膨胀和收缩，它最好用0.1到0.2英寸厚的不锈钢制成，J形挠性圈11由多个弧形板组成，这些弧形板在反应堆容器凸缘27上彼此相邻设置而形成J形挠性圈11，弧形板在其焊接到密封板10之前拼接焊在一起。密封板10在就位安装之前分别与支撑圈12和J形挠性圈11焊接。外密封圈14和内密封圈13最好用与密封板10相同的材料制成。外密封圈14和内密封圈13由多个弧形板组成，弧形板彼此相邻设置分别形成外密封圈14和内密封圈13，两组弧形板在分别用密封装置栓固并焊接到反应堆容器凸缘27和燃料更换池底板23内的埋置圈24上之前就拼接焊在一起。密封板10下方的多个支撑臂15用来支撑密封板10，每个从燃料更换池腔壁25向靠近J形挠性圈11的密封板10延伸的支撑臂15可以有至少一个校平螺旋16以调整密封板10的水平。

Claims (4)

1.在原子核安全壳结构中，燃料更换池腔设置在原子核容器凸缘和燃料更换池底板之间，一种永久性池腔密封装置包括：
a.一个由多个弧形板组成的密封板，在密封板上围绕其周边按照一定间距设有多个出入孔；
b.由多个弧形板组成的支撑圈和J形挠性圈；
c.由多个弧形板组成的内密封圈和外密封圈；
d.用密封装置联接并焊接到反应堆容器的凸缘上的内密封圈；
e.用密封装置联接并焊接到燃料更换池底板内的埋置圈上的外密封圈；
f.一个出入孔盖可拆卸地联接到密封板的每一个覆盖的和密封的出入孔上。
2.根据权利要求1所述的密封板，其特征在于密封板的一部分悬伸于J形挠性圈之外，使其不会遭受坠落物落在上面。
3.根据权利要求1所述的原子核反应堆安全壳结构，其特征在于：在密封板的下方有多个支撑臂从燃料更换池腔壁向密封板的内径方向延伸来支撑密封板。
4.根据权利要求3所述的原子核反应堆安全壳结构，其特征在于：每一个支撑臂有至少一个校平螺旋来调整密封板的水平。
CN95115370A 1995-04-21 1995-08-09 原子核反应堆的永久性池腔密封装置 Expired - Lifetime CN1105390C (zh)

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CN105321584A (zh) * 2014-07-17 2016-02-10 尼古拉斯·M·博诺姆 用于水冷却慢化核反应堆的安全壳
CN112037942A (zh) * 2020-09-08 2020-12-04 中国原子能科学研究院 盖板装置及具有其的池式反应堆

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CN112037942A (zh) * 2020-09-08 2020-12-04 中国原子能科学研究院 盖板装置及具有其的池式反应堆

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CN1105390C (zh) 2003-04-09
US5633901A (en) 1997-05-27
KR960039017A (ko) 1996-11-21
KR0150110B1 (ko) 1998-12-15

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