首页> 外文会议>The transition to closure and legacy management >Sample-taking to Characterize Organic Solvent Contained in a Tank in a Shielded Room Involving 3D Modeling of the Room and the Equipment Present, Followed by the Development of Special Tools
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Sample-taking to Characterize Organic Solvent Contained in a Tank in a Shielded Room Involving 3D Modeling of the Room and the Equipment Present, Followed by the Development of Special Tools

机译:进行取样,以表征包含在房间和设备中的3D建模的屏蔽室的储罐中包含的有机溶剂,然后开发专用工具

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摘要

Licensed Nuclear Facility 57 consists of three buildings: Building 18 (hot lab), Building 91 (chemicalrnengineering hall) and Building 54 (equipment store). This facility has been under decommissioning since 1st July 1995.rnBuilding 18, formerly a radiochemistry laboratory, used for chemical research relating to the reprocessing of spent fuel andrnother issues as well as to the production of transuranic radionuclides, is undergoing clean-up prior to dismantling. In arnlaboratory of this type, the clean-up operations include reduction of radioactivity levels and chemical hazards associatedrn-with the equipment. This process notably includes draining and treatment of contents of process and effluent tanks.rnThe research and production work was performed in a facility comprising a shielded production line and a shielded roomrncontaining two effluent tanks and three process tanks, the production line and the tank room being linked by a plant duct.rnIn 1974, use of the tank in the room was abandoned as a result of a breach in a high-level effluent tank After management ofrnthe incident (recovery of the liquid contained in the catchment basement), process Tanks A and C containing aqueous liquorsrnwere drained in the early eighties by pumping through the production line. The contents of Tank B could not, at the time, berntransferred to the production line workstations via the existing systems.rnAs the drawings of the room were not reliable, an initial video inspection was made in 1995 via bore holes made in thernceiling. In 1997, it was planned to drain the contents of the tank using a tank level measuring pipe. This proved to bernimpracticable. It was then decided to take, from outside, a sample of the contents of the tank from the former control roomrnlocated above the tank room. An initial set of equipment was installed in the room with the collaboration of the DDCO/SDSPrnteams on the basis of the results of the 1995 video inspection and the drawings available. A 3D model was then created andrncorrected by video inspection and the use of environment reconstruction software developed by DTSI/SRSI. The 3D modelrnobtained enabled 3D simulation of the special tools and protocols necessary for the operation, including core drilling forrnaccess (size and position). The construction of a full-scale model, on the DDCO/SDSP test platform, enabled a protocol to bernestablished and the operators to be trained.rnOnce the necessary authorizations were obtained for core drilling the ceiling above the tank as required for sample-taking, the operations carried out in June 2004, samples were then taken which made it possible to establish the radiological,rnphysical and chemical properties of the solvent and to confirm the feasibility of decontamination. At the same time, studies were carried out in liaison with DRCP/SCPS of the possible ways of dissolving any solid deposits.
机译:获得许可的核设施57由三座建筑物组成:18号建筑物(热实验室),91号建筑物(化学工程大厅)和54号建筑物(设备商店)。该设施自1995年7月1日起停运。rn大楼18,以前是一个放射化学实验室,用于与乏燃料的再处理和其他问题以及超铀放射性核素的生产有关的化学研究,正在拆除之前进行清理。 。在这种类型的实验室中,清理操作包括降低放射性水平和与设备相关的化学危害。该过程主要包括对工艺池和污水池的内容物进行排放和处理。研究和生产工作是在包括屏蔽生产线和屏蔽室的设施中进行的,其中包含两个污水池和三个工艺池,生产线和池室为1974年,由于高位污水箱的泄漏而放弃了使用该房间的水箱。对事故进行处理(回收集水室地下室中的液体)后,处理水箱A八十年代初期,通过泵送流经生产线的方式来排放含碳的水溶液和含碳液体。当时无法通过现有系统将储罐B的内容传送到生产线工作站。由于房间的图纸不可靠,1995年通过在the孔上打孔对视频进行了初步检查。 1997年,计划使用储罐液位测量管排放储罐中的内容物。事实证明这是不切实际的。然后决定从外面从位于储藏室上方的前控制室中提取储藏室的样品。根据1995年视频检查的结果和可用的图纸,在DDCO / SDSPrnteams的协作下,在房间中安装了一套初始设备。然后创建3D模型,并通过视频检查和DTSI / SRSI开发的环境重建软件对其进行校正。 3D模型实现了操作所需的特殊工具和协议的3D仿真,包括岩心钻探通道(尺寸和位置)。在DDCO / SDSP测试平台上构建的全尺寸模型可以制定协议并培训操作员。一旦获得了必要的授权,可以根据取样要求在储罐上方的顶棚上进行岩心钻孔,在2004年6月进行的操作中,然后取样,从而可以确定溶剂的放射,物理和化学性质,并确认去污的可行性。同时,与DRCP / SCPS进行了研究,研究了解决任何固体沉积物的可能方法。

著录项

  • 来源
  • 会议地点 Denver CO(US)
  • 作者单位

    CEA/DEN-SAC/DRSN/SAFAR :Commissariat à l’Energie Atomique/Direction de l’Energie Nucléaire-Saclay/Département des Réacteurs et des Services Nucléaires/Service d’Assainissement de Fontenay aux Roses Centre de Fontenay aux Roses BP 6 92265 Fontenay aux Roses Cedex (France), michel.jeanjacques@cea.fr;

    rnCEA/DEN-SAC/DRSN/SAFAR :Commissariat à l’Energie Atomique/Direction de l’Energie Nucléaire-Saclay/Département des Réacteurs et des Services Nucléaires/Service d’Assainissement de Fontenay aux Roses Centre de Fontenay aux Roses BP 6 92265 Fontenay aux Roses Cedex (France), valerie.toulemonde@cea.fr;

    rnCEA/DEN-VRH/DDCO/SDSP : Commissariat à l’Energie Atomique/Direction de l’Energie Nucléaire-Vallée du Rh?ne/Département Démantèlement et Conduite d’Opérations/Service de Démantèlement et de Soutie;

  • 会议组织
  • 原文格式 PDF
  • 正文语种 eng
  • 中图分类 放射性废物管理及综合利用;
  • 关键词

  • 入库时间 2022-08-26 14:25:56

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