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A New Concept of Decommissioning Planning for Nuclear Research Reactor as Part of Life Cycle Management

机译:生命周期管理的核研究堆退役计划新概念

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摘要

This work will analyze the possibility to reutilize the RR structures, systems and components (SSCs) after decontamination and partial dismantling. In the RR will be developed a cleanup plan as part of decommissioning plan and release of site from initial destination to a new destination. Dose limits for release of site are in the range of 10 Sv/a~(-1) -mSv/a except the Reactor Block, basement of Reactor Block and Hot Cells, where the dose limit for the workers in the newly authorized practice will be of max. 20 mSv/a.rnWe propose the utilization of the reactor block as wet storage for Co-60 sources (30 kCi) recycled from decommissioning of medical installations. This storrage space is highly needed as currently there are in storage in IFIN-HH and the Research Nuclear Centre in Pitesti aprox. 18 kCi. In the technological spaces of the actual primary circuit will be placed the conveyor-transport system for varrious materials radiation processing. Hot cells, nuclear chemistry laboratories, workshop for depleted uranium, cranes, and sanitary ventilation could all be used after decontamination. Other items, like stack, technological ventilation, cooling pond for SNF, electrical and automatization systems will be removed by dismantling. In conclusion, RR as nuclear facility will be released from regulatory control as terminated practice and in the same sitting will be placed an irradiation facility with Co-60 source and electron accelerator (max. 10 MeV) for radiation processing and technologies as well as research in material sciences.rnAs a result, after 40 years (1947-1997) of functioning, 10 years (1997-2007) in transitional phase, 5 years (2008-2013) in D&D phase, there will be other 50 years of utilisation with the new destination, also closely related with the nuclear field.rnThis concept is based on lessons learned and experienced during the commissioning of the irradiation facility with Co-60 (15 kCi) placed in the basement of Subcritical Assembly HELEN in IFIN-HH.
机译:这项工作将分析去污和部分拆除后重新利用RR结构,系统和组件(SSC)的可能性。在RR中将制定清理计划,作为退役计划的一部分,并将站点从初始目标释放到新目标。除反应器座,反应器座地下室和热室外,释放场所的剂量限制在10 Sv / a〜(-1)-mSv / a范围内,在此范围内,新授权操作人员的剂量限制将在最多20 mSv / a.rn我们建议利用反应堆作为湿储存,用于从医疗设施退役中回收的Co-60来源(30 kCi)。由于IFIN-HH和Pitesti aprox的研究核中心目前正在存储该存储空间,因此非常需要。 18 kCi。在实际的主回路的技术空间中,将放置用于各种材料辐射处理的输送机-运输系统。净化后,可使用热室,核化学实验室,贫铀车间,起重机和卫生通风设备。其他物品,如烟囱,技术通风,SNF的冷却池,电气和自动化系统,将通过拆除来拆除。总之,作为核设施的RR将按照终止的惯例从监管控制中释放出来,并将在同一地点放置一个带有Co-60源和电子加速器(最大10 MeV)的辐照设施,用于辐射处理和技术以及研究。因此,经过40年(1947-1997)的运作,10年(1997-2007)的过渡阶段,5年(2008-2013)的D&D阶段的使用,将有50年的使用年限。这个概念是基于在IFIN-HH的亚临界组件HELEN地下室放置的Co-60(15 kCi)辐照设施投入运行期间汲取的经验教训。

著录项

  • 来源
  • 会议地点 Denver CO(US)
  • 作者

    Mitica Dragusin;

  • 作者单位

    'Horia Hulubei' National Institute for Physics and Nuclear Engineering IFIN-HH Bucharest St. Atomistilor 407, Com.Magurele, jud.Ilfov, P. O.B. MG-6, 76900 Romania tel. +(4021) 404.23.00, fax +(4021) 457.44.40/ 404.23.25 drasusin@ifin.nipne.ro;

  • 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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