首页> 外文会议>American Nuclear Society 9th topical meeting and exhibition on robotics and remote systems >AMERICAN NUCLEAR SOCIETY NINTH INTERNATIONALTOPICAL MEETING ON ROBOTICS AND REMOTE SYSTEMS
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AMERICAN NUCLEAR SOCIETY NINTH INTERNATIONALTOPICAL MEETING ON ROBOTICS AND REMOTE SYSTEMS

机译:美国核学会第九届国际机器人与远程系统会议

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The US Department of Energy (DOE) is currently evaluating the Yucca Mountain Nevada site forrnsuitability as a Monitored Geologic Repository (MGR) for underground disposal of 70,000 metric ton ofrnthe nation’s high-level waste. This paper reviews the remote handling, engineering, safety, and economicrntrade-off studies leading to the development, conceptual design, viability assessment, and siternrecommendation decisions for the repository. Trade-off considerations studied include a number ofrnremote handling and high-level radioactive waste packaging facility design alternatives such as truckrnversus rail transport, wet versus dry handling, contact versus remote operation, methods to stage fuelrnassemblies and canisters, manual versus remote maintenance, and modular versus integrated buildingrnconstruction. These trade-off studies have led to design of seven primary waste handling systems tornaccomplish the repository mission of safe handling, reliable remote equipment, cost-effective operations,rnhigh throughput rates, and a minimum of facility outages. Those trade-off decisions that are beingrnreconsidered or reevaluated for the license application phase of the design are also discussed.rnThe results from trade-off studies conducted to date are summarized and the design concepts developedrnfor the repository site recommendation are presented. Waste shipments arrive at the security station nearrnthe North Portal to the underground MGR. After receipt inspections and checks, truck or rail cask carriersrnare staged in a controlled area surrounding the MGR nuclear facilities. The cask personnel barriers andrnimpact-limiters are removed in a Carrier Preparation Building prior to transporting the cask and carrier tornthe Waste Handling Building (WHB). Remote handling and packaging operations are performed in thernWHB. Casks are unloaded from their carriers in a large carrier bay. Commercial spent nuclear fuel casksrnare transferred to an Assembly Transfer System where they are placed in unloading pools for remoternunderwater fuel handling. The spent fuel assemblies are staged in connected pools until they arernremotely transferred to hot cells for loading into a disposal container. DOE-owned spent fuel and highlevelrnwaste canisters and casks are transferred to a Canister Transfer System where the casks arernopened, transported into hot cells, and the canisters are transferred remotely to a staging area or arndisposal container. Once a disposal container is loaded, it is transferred to a Disposal ContainerrnHandling System where disposal container lids are welded, annealed and/or inspected remotely in a largernhot cell. The sealed waste package is then staged and loaded, remotely and horizontally, into a shieldedrnwaste package transporter for underground MGR waste emplacement operations.
机译:美国能源部(DOE)目前正在评估尤卡山内华达州场址是否适合作为监测性地质处置库(MGR)用于地下处置70,000吨美国高放废物。本文回顾了导致存储库开发,概念设计,可行性评估和站点推荐决策的远程处理,工程,安全和经济权衡研究。折衷考虑的因素包括许多远程处理和高级放射性废物包装设施的设计替代方案,例如卡车与铁路运输,湿式与干式处理,接触式与远程操作,分装燃料组件和罐的方法,手动与远程维护以及模块化与综合建筑施工。这些权衡研究已经导致设计了七个主要的废物处理系统,以完成安全处理,可靠的远程设备,具有成本效益的操作,高生产率,以及最少的设备中断的存储库任务。还讨论了在设计的许可证申请阶段正在重新考虑或重新评估的那些权衡决定。总结了迄今为止进行的权衡研究的结果,并介绍了针对存储库站点推荐而开发的设计概念。废物运抵北入口,靠近地下MGR。在收到检查和检查后,卡车或铁路桶运输车在MGR核设施周围的受控区域上演。在将桶和运输工具运送到废物处理大楼(WHB)之前,先在运输者准备大楼中移除桶的人员障碍和限制器。在WHB中执行远程处理和包装操作。桶是从一个大型承运人托架中从承运人卸下的。将商用乏核燃料桶转移到装配转移系统中,然后将其放置在卸货池中,以进行远程水下燃料处理。用过的燃料组件在相连的池中分段放置,直到将它们远程转移到热室中以便装入处置容器中为止。能源部拥有的乏燃料,高废物罐和罐被转移到罐转移系统,在罐转移系统中将罐打开,运输到热室中,然后将罐远程转移到集结区或垃圾处理容器。装载处理容器后,将其转移到处理容器处理系统,在其中将处理容器盖在较大的热室中进行焊接,退火和/或远程检查。然后将密封的废物包装从远处和水平分段放置并装入屏蔽的废物包装运输机中,以进行地下MGR废物安置作业。

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