首页> 外文会议>International conference on nuclear engineering;ICONE5 >UPGRADING OF OPERATING NPP UNITS EQUIPPED WITH V-213 (THE CONCRETE VAULT TYPE 2) 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-213 (THE CONCRETE VAULT TYPE 2) REACTORS TO ENHANCE SAFETY IN CASE OF SEVERE ACCIDENTS FOLLOWED BY REACTOR CORE AND REACTOR VESSEL DESTRUCTION

机译:升级装有V-213(混凝土vault型2)反应器的NPP装置,以提高反应堆核心和反应器容器毁坏后发生事故的安全性

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According to their functional destination thernsystems participating in managing the accidents with severerncore damage can be conventionally divided into tworngroups. Group 1 involves the systems that perform thernfunctions of reactor core cooling with the purpose ofrndecreasing the degree of core damage and limiting thernsource term. With this aim in view no special systems ofrnbeyond-design accidents managing are envisaged in therndesigns of NPPs equipped with VVER-type reactors. Thernabove functions are carried out by the systems of normalrnoperation. A number of systems and devices of beyonddesignrnaccidents managing (Group 2) is envisaged in thernprojects of NPPs equipped with VVER-type reactors withrnthe purpose to decrease the probability of protectivernbarriers system damaging. They involve: system of coriumrnretention inside reactor vessel and system of coriumrnretention inside reactor concrete pit.rnThe system of corium retention inside reactorrnvessel comprises interrelated channels that provide thernconditions of heat removal from reactor vessel due torncoolant natural circulation between the concrete pit andrnemergency pond. The system must provide retaining thernentire damaged core and all the internals inside the vessel with coolant available in the concrete pit and the minimumrnwater level in the emergency pond.rnThe system of corium retention inside reactorrnconcrete pit comprises the corium retention equipment andrncooling channels that connect the equipment and thernemergency pond. The system shall limit the generation ofrnexplosible corium-to-coolant interaction above thernspecified limits and to provide retaining the splintered fuelrnwith coolant available and no significant corium-to-pitrnconcrete interactionrnAlong with the systems and devices of beyond-designrnaccidents managing the paper covers the main approachesrnto concrete pits upgrading at the operating reactor plantsrnwith the aim to enhance the safety of NPPs equipped withrnVVER-type reactors.
机译:根据其功能目标,参与管理具有严重核心损害的事故的系统通常可以分为两个组。第1组涉及执行反应堆堆芯冷却功能的系统,目的是减少堆芯损坏的程度并限制源项。出于这个目的,在配备VVER型反应堆的核电厂的设计中未设想超出设计事故管理的特殊系统。上述功能由正常运行系统执行。在配备VVER型反应堆的核电厂项目中,设想了许多非设计事故管理系统和设备(第2组),其目的是减少保护性屏障系统损坏的可能性。它们涉及:反应堆容器内的ium留系统和反应堆混凝土坑内的ium留系统。反应堆容器内的retention留系统包括相互关联的通道,这些通道提供了由于混凝土坑和紧急池之间的冷却剂自然循环而从反应堆容器中除热的条件。该系统必须在混凝土坑内提供冷却剂并在应急池中提供最低的水位,以保留损坏的铁心和容器内部的所有内部零件。反应堆内部的钙保留系统-混凝土坑包括钙保留设备和连接设备的冷却通道和紧急池塘。该系统应将爆炸性的皮质与冷却剂之间的相互作用限制在规定的极限之上,并提供分裂的燃料并保留可用的冷却剂,并且皮质与沥青之间不存在明显的相互作用。正在运行的反应堆工厂对混凝土坑进行升级,目的是提高装有VVER型反应堆的核电厂的安全性。

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