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Qualification and Implementation of the Canberra Box Counter NDA System

机译:堪培拉箱柜台柜台柜台系统的资格和实施

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The Canberra Box Counter Nondestructive Assay (NDA) System consists of two mobile subsystems: a Box Segmented Gamma Scanner (BSGS) and a separate Box Neutron Assay System (BNAS). The counter is to be used to assay transuranic (TRU) waste packaged in large containers for shipment to the Waste Isolation Pilot Plant (WIPP). The system was designed and fabricated by Canberra Industries, Inc. under a research and development contract with the US Department of Energy. Plutonium and other radionuclides of importance to the TRU waste disposal program at WIPP will be quantified by the counter. The BSGS is suitable for quantification of ~ 241Am, ~ 238Pu, ~ 239Pu, ~ 240Pu, ~ 241Pu, ~ 233U, ~ 235U, ~ 238U, ~ 137Cs, and other radionuclides using either a multi-density efficiencycorrected method or a transmission-corrected approach to account for matrix attenuation. Spectra from the BSGS are also used to determine relative plutonium and uranium isotopic ratios. The BNAS directly measures the time-correlated neutron signal from spontaneously fissioning isotopes (generally ~ 238Pu, ~ 240Pu, and ~ 242Pu) using both coincidence and multiplicity counting methods. Canberra’s Genie 2000 and NDA 2000 software packages automate control of the acquisition and motion elements of the two components, manage data collection and storage, analyze the collected data, integrate the results from the two subsystems as needed, and identify problems with the assay data. Combined results from the BSGS and BNAS are used to determine the total alpha activity, fissile gram equivalent, decay heat, and other properties of the radioactive waste. Unique to the box counter is its capability to accurately characterize the radioactive contents of Contact-Handled TRU waste packaged in a wide variety of containers. These range in size from 208-liter (55-gallon) drums to 5.5’ x 5.5’ x 8.5’ boxes. Factory calibration of the system was performed for a broad assortment of simulated waste matrices contained in 208-liter drums, Standard Waste Boxes (SWB), the Standard Large Box - 2 (SLB-2), and Ten Drum Overpacks (TDOP). The larger containers are to be used to ship multiple drum assemblies or large volume waste without resizing and/or repackaging. Upon completion of the design and fabrication of the system, the two box counter subsystems were calibrated and tested at the Canberra facility in Meriden, CT. They were then shipped to the Solid Waste Management Facility at the Savannah River Site (SRS) where acceptance testing was performed.
机译:堪培拉盒计数器无损检定(NDA)系统由两个移动子系统组成:一个盒分段伽玛扫描仪(BSGS)和一个单独的盒子中子测定系统(BNAS)。计数器是用于测定超铀(TRU),废包装在运往废物隔离试验厂(WIPP)大容器。该系统的设计,并根据与美国能源署的研究和开发合同堪培拉工业公司制造。钚和重要性在WIPP TRU的垃圾处理方案的其他放射性核素由计数器进行量化。所述BSGS适合于使用一个多密度efficiencycorrected方法或〜241Am的,〜钚238,〜239Pu,〜240Pu,〜241Pu的,〜233U,〜235U,〜238U,〜铯-137,和其它放射性核素的定量的传输校正方法占矩阵衰减。从BSGS光谱也被用来确定相对钚和铀同位素比率。所述BNAS直接测量从同时使用重合和多重计数方法自发裂变同位素(通常〜钚238,〜240Pu,和〜242Pu)的时间相关的中子的信号。堪培拉的精灵2000和NDA 2000软件包的两个组件的采集和运动元素的自动化控制,管理数据的采集和存储,分析收集到的数据,整合根据需要从两个子系统的结果,并确定与试验数据的问题。从BSGS和BNAS组合的结果被用来确定总α活性,裂变克当量,衰变热,和放射性废物的其它性质。独有的盒子计数器是它能够精确地表征联系柄TRU的放射性废物的内容包装在各种容器的能力。这些从208升(55加仑)的范围在大小鼓至5.5’ ×5.5’ ×8.5’ 盒。包含在208升桶废模拟矩阵的广泛分类进行了系统的工厂校准,标准废物箱(SWB),标准大箱子 - 2(SLB-2),和十鼓外包装(TDOP)。在较大的容器将被用于装运多个鼓组件或大体积的废物不调整和/或重新打包。一旦设计和系统的制造完成时,两个框计数器子系统进行校准,并在梅里登,CT堪培拉设施进行测试。然后,他们被运到在萨凡纳河站点固体废物管理设施进行(SRS),其中验收测试。

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