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ASNC upgrade for nuclear material accountancy of ACPF

机译:对ACPF的核材料会计进行ASNC升级

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摘要

A safeguards neutron coincidence counter for nuclear material accountancy of the Advanced spent-fuel Conditioning Process Facility (ACPF), known as the ACP Safeguards Neutron Counter (ASNC), was upgraded to improve its remote-handling and maintenance capabilities. Based on the results of the previous design study, the neutron counter was completely rebuilt, and various detector parameters for neutron coincidence counting (i.e., high-voltage plateau, efficiency profile, dead time, die-away time, gate length, doubles gate fraction, and stability) were experimentally determined. The measurement data showed good agreement with the MCNP simulation results. To the best of the authors' knowledge, the ASNC is the only safeguards neutron coincidence counter in the world that is installed and operated in a hot-cell. The final goals to be achieved were (1) to evaluate the uncertainty level of the ASNC in nuclear material accountancy of the process materials of the oxide-reduction process for spent fuels and (2) to evaluate the applicability of the neutron coincidence counting technique within a strong radiation field (e.g., in a hot-cell environment).
机译:升级了先进乏燃料调节过程设施(ACPF)的核材料衡算保障中子符合计数器,称为ACP保障中子计数器(ASNC),以提高其远程处理和维护能力。根据先前设计研究的结果,中子计数器被完全重建,并且用于中子重合计数的各种检测器参数(即高压平稳段,效率曲线,停滞时间,消亡时间,门长度,门倍数翻倍)和稳定性)是通过实验确定的。测量数据与MCNP模拟结果吻合良好。据作者所知,ASNC是世界上唯一在热室中安装和运行的保障中子符合计数器。要实现的最终目标是(1)评估ASNC在乏燃料氧化物还原过程的过程材料的核材料核算中的不确定性水平,以及(2)评估中子符合计数技术在核燃料核算中的适用性强辐射场(例如,在热室环境中)。

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