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首页> 外文会议>Proceedings of the international topical meeting on advanced reactors safety >Upgrading of Operating NPP Units Equipped with V-179 and V-230 Reactors to Enhance Safety in Case of Severe Accidents Followed by Reactor Core and Reactor Vessel Destruction
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Upgrading of Operating NPP Units Equipped with V-179 and V-230 Reactors to Enhance Safety in Case of Severe Accidents Followed by Reactor Core and Reactor Vessel Destruction

机译：升级严重配备V-179和V-230反应堆的核电厂运行装置，以提高安全性，以防在发生严重事故后反应堆堆芯和反应堆容器毁坏

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摘要

The course of a severs accident is accompanies with different failures or periodic actions of safety and normal operation systems not envisaged in the design. As a result of failures or conditions of these systems operation not envisaged in the design by the moment of corium release into the concrete pit it can contain any quantity of coolant (by the level) The concrete pit can be: 1) completely flooded with water, internal space between the bottom and the thermal protection of reactor vessel lower part filled up; 2) not completely flooded with water, the level of which can be situated between reactor vessel bottom head and the floor of sub-reactor space; 3) be flooded with water under reactor vessel lower part thermal shielding only; 4) not to be flooded with water (water can be found in the well only).rnThe most important peculiarities of the concrete pits of the operating reactor plants equipped with VVER-440 of V-230 type and their qualitative characteristics: 1) air is supplied to cool the concrete via the channels coming from the lateral surface of the concrete pit; 2) air is supplied respectively to thermal shielding of reactor vessel lower part from aside.rnThe aim of the proposed design is to create the system of containment protection for a water cooledrnand water moderated reactor plant at the operating NPP units equipped with VVER-440 reactor, that provides enhancing the reliability of corium retention in reactor pit inside the containment in case of an accident of core destruction and corium release from reactor vessel.rnThe paper covers the main approaches to concrete pits upgrading at the operating reactor plants with the aim to enhance the safety of NPPs equipped with VVER-440 of V-230 type reactors.
机译：服务器事故的过程伴随着设计中未设想的安全和正常操作系统的不同故障或周期性动作。由于这些系统的故障或状况，是在设计中未设想到的，因为当水泥释放到水泥坑中时，它可能含有任何数量的冷却剂（按液位计）。混凝土坑可能是：1）完全被水淹没底部与反应堆容器下部热保护之间的内部空间已填满； 2）未完全充满水，其水位可位于反应堆容器底部与副反应器空间底部之间； 3）仅在反应堆容器下部隔热板上注水； 4）不要被水淹没（只能在井中找到水）。rn配备V-230型VVER-440的在运反应堆工厂混凝土坑的最重要特征及其质量特征：1）空气通过来自混凝土坑侧面的通道供应冷却混凝土。 2）分别从侧面将空气供应到反应堆容器下部的隔热层。拟议设计的目的是在配备VVER-440反应堆的运行核电厂装置上为水冷和水缓和的反应堆装置建立安全壳保护系统如果发生堆芯破坏和反应堆容器中的钙释放事故，可以提高安全壳内反应堆坑中的钙保留的可靠性。rn本文涵盖了正在运行的反应堆工厂进行混凝土坑改造的主要方法，目的是提高装有V-230型反应堆的VVER-440的核电厂的安全性。

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  • 会议地点 Orlando FL(US)
  • 作者

    B.I.Nigmatulin; V.G.Fedorov; A.S.Sidorov; G.E.Nosenko;

  • 作者单位

    Electrogorsk Research Engineering Centre of Nuclear Plants Safety street Bezymyannaya, 6 Electrogorsk, Moscow district, Russia, 142530;

    Experimental Design Organization 'GIDROPRESS' street Ordzhonikidze, 21 Podolsk, Moscow district, Russia, 142103;

    Experimental Design Organization 'GIDROPRESS' street Ordzhonikidze, 21 Podolsk, Moscow district, Russia, 142103;

    Experimental Design Organization 'GIDROPRESS' street Ordzhonikidze, 21 Podolsk, Moscow district, Russia, 142103;

  • 会议组织
  • 原文格式 PDF
  • 正文语种 eng
  • 中图分类 反应堆安全与控制;
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