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Engineering and Process Development in Support of the Removal of Residual Sodium Coolant from the Prototype Fast Reactor at Dounreay, Scotland

机译:工程和工艺开发,以支持从苏格兰Dounreay的原型快速反应器中去除残留的钠冷却剂

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As part ofthe United Kingdom nuclear power development programme, a sodium cooled fast breeder reactor was constructed at the United Kingdom Atomic Energy Authority (UKAEA) Dounreay site. The Prototype Fast Reactor (PFR) commenced operation in 1974, and supplied electricity to the national grid until the end of its design life in 1994. The facility is now being decommissioned, and the site environment restored. Decommissioning and dismantling operations require the chemotoxic hazard presented by the sodium to be considered, in addition to the radiological hazard inherent in the decommissioning of any nuclear facility.rnRemoval of sodium from the reactor vessel will be in two stages. Firstly, the bulk of the sodium will be pumped out to a dedicated treatment plant. This will leave sodium residues as films on all internal surfaces and as pools in areas of the vessel that will not drain. These residues will then be chemically reacted in-situ, prior to commencing dismantling operations.rnThe Water Vapour Nitrogen (WVN) process methodology has been selected by UKAEA as the preferred technology for the removal of sodium residues. To this end, a dedicated off-site test and development facility has been constructed to prove the WVN process for application to facilities on the Dounreay site. As part of the development, the highly vigorous sodium-water reaction has been captured on video, and pressure and temperature transients analysed to provide a better understanding of the reaction progress.rnThe WVN process has now been successfully used to clean sodium residues from ancillary plant including storage tanks, small plant items with complex geometries, and the secondary circuits. Residual sodium quantities of up to one tonne have been successfully treated. Lessons learned through these successes will be important in the design stage of the system to clean the reactor vessel, in order to ensure its safe, successful cleaning.
机译:作为英国核电发展计划的一部分,在英国原子能管理局(UKAEA)Dounreay厂址建造了钠冷却快中子增殖堆。原型快速反应堆(PFR)于1974年开始运行,并向国家电网供电,直到1994年设计寿命结束。该设施现已退役,现场环境得以恢复。退役和拆除操作除了要考虑到任何核设施退役所固有的放射性危害外,还需要考虑到钠带来的化学毒性危害。从反应堆容器中去除钠将分两个阶段进行。首先,大部分钠将被泵送到专门的处理厂。这将在所有内表面上留下钠残留物,形成薄膜状,并在不排水的容器区域中形成水池。然后,在开始拆卸操作之前,这些残留物将进行原位化学反应。英国航空航天局选择水蒸气氮(WVN)工艺方法作为去除钠残留物的首选技术。为此,已经建立了专用的场外测试和开发设施,以证明WVN流程适用于Dounreay站点上的设施。作为开发的一部分,已在视频上捕获了剧烈的钠水反应,并对压力和温度瞬态进行了分析,以更好地了解反应进程。rn WVN工艺现已成功用于清洁辅助设备中的钠残留物包括储罐,具有复杂几何形状的小型工厂物品和次级回路。已成功处理了高达一吨的钠残留量。从这些成功中学到的经验教训对于清洁反应堆容器的系统设计阶段非常重要,以确保其安全,成功地进行清洗。

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