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首页> 外文会议>Waste management 2004 symposium (WM'04): waste management, energy security and a clean environment >DECOMMISSIONING MODEL FOR THE BROOKHAVEN GRAPHITE RESEARCH REACTOR
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DECOMMISSIONING MODEL FOR THE BROOKHAVEN GRAPHITE RESEARCH REACTOR

机译：布鲁克哈芬石墨研究反应器的退役模型

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As part of its broad commitment to protecting public health and the environment,the U.S.Department of Energy (DOE)is decommissioning the Brookhaven Graphite Research Reactor(BGRR).The BGRR was an air-cooled graphite moderated reactor like many built in the U.S.and U.K.after World War II.The BGRR was the first reactor built for the sole purpose of providing neutrons for scientific research,and operated from 1950 to 1968. rnThe team of Burns and Roe Enterprises,Inc.(BREI),Babcock Services,Inc.(BSI),and WMG,Inc.(WMG)was commissioned by Brookhaven National Laboratory(BNL)to evaluate and analyze the stability,and progressive decommissioning and removal of BGRR components.This analysis took the form of several detailed decommissioning studies that range from disassembly and removal of the unit’s graphite pile to the complete environmental restoration of the reactor site. rnThe studies provide a decision-making tool for the final end state of the facility.To meet this need,key parameters are fully developed,and include removal methodologies(based on CERCLA criteria),waste streams and volumes, cost and schedule,and total man-rem exposure. rnWhile most of the facility’s decommissioning effort is conventional,the graphite pile and its biological shield present the greatest challenge.The studies develop a unique method of removing high-activity waste(primarily from fuel failures)trapped in the graphite joints by over-boring the fuel channels and collecting the debris.Once the high-activity waste is removed,the remainder of the pile lends itself to dismantlement by a compact,electrically powered demolition machine with standard end-effectors. rnThis methodology for graphite handling and disposal at the relatively small BGRR pile sets the stage for decommissioning of the larger U.K.reactors.With these reactors,special considerations such as Wigner energy and high-activity debris,necessitates a waiting period of up to one hundred years.The BGRR decommissioning model therefore would provide useful and early baseline data that can be applied directly and proactively to the planning and remediation of the U.K.reactors.
机译：作为对保护公众健康和环境的广泛承诺的一部分，美国能源部（DOE）正在使布鲁克黑文石墨研究反应堆（BGRR）退役。BGRR是一种空气冷却的石墨慢化反应堆，与许多美国和美国第二次世界大战之后的英国。BGRR是第一个专门为科学研究提供中子的目的而建造的反应堆，其运行时间为1950年至1968年。rn Burns and Roe Enterprises，Inc。（BREI），Babcock Services，Inc。的团队。 （BSI）和WMG，Inc.（WMG）受布鲁克黑文国家实验室（BNL）的委托来评估和分析BGRR组件的稳定性以及逐步退役和去除。该分析采取了一些详细的退役研究的形式，范围从拆卸并拆除装置的石墨堆，以完全恢复反应堆现场的环境。 rn这些研究为设施的最终状态提供了决策工具。为满足此需求，充分开发了关键参数，包括清除方法（基于CERCLA标准），废物流和量，成本和进度以及总计人雷姆曝光。 rn虽然大多数设施的退役工作是常规的，但石墨堆及其生物防护层却是最大的挑战。研究开发了一种独特的方法，可以通过过度钻孔来清除石墨接头中捕获的高活性废物（主要是由于燃料故障）燃料通道并收集碎屑。一旦去除了高活性废物，堆中的其余部分将通过带有标准末端执行器的紧凑型电动拆除机自行拆除。 rn这种在相对较小的BGRR堆中处理和处置石墨的方法为大型UK反应器的退役奠定了基础。有了这些反应器，诸如Wigner能量和高活性碎屑之类的特殊考虑因素需要长达一百年的等待期。因此，BGRR退役模型将提供有用的早期基准数据，这些数据可以直接，主动地应用于UKreactors的计划和修复。

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