首页> 外文期刊>Nuclear Instruments & Methods in Physics Research. Section A, Accelerators, Spectrometers, Detectors and Associated Equipment >Design of MICADO advanced passive and active neutron measurement system for radioactive waste drums
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Design of MICADO advanced passive and active neutron measurement system for radioactive waste drums

机译:放射性废话鼓云母先进被动和活性中子测量系统的设计

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In the frame of the MICADO H2020 project, a passive and active neutron measurement system is being developed to estimate the nuclear material mass inside legacy waste drums of low and intermediate radioactivity levels. Monte-Carlo simulations have been performed to design a new modular and transportable neutron system, with the main objective to reach a good tradeoff between the performances in passive mode, i.e. neutron coincidence counting, and in active interrogation mode with the Differential Die-away Technique. Different designs are compared, which mainly differ in their moderation materials, graphite and polyethylene. This parametric study allowed us to define a prototype taking into account practical constraints in view of its final implementation in a wide range of in-situ locations and nuclear facilities. The total neutron detection efficiency of the prototype is 6.75%, as calculated for an empty drum, i.e. without waste matrix. The detection limit in terms of nuclear material equivalent mass have also been estimated based on assumptions for a homogeneous distribution of nuclear materials inside the drum, filled with four types of matrices covering the range of nuclear waste drums defined in the frame of the project. The most favorable matrix is made of stainless steel in passive mode and of polyethylene in active mode, with an apparent density of 0.7 g cm~(-3) and 0.1 g cm~(-3), respectively. The calculated mass detection limits are respectively 68 mg of ~(240)Pu, 62 mg of ~(235)U and 39 mg of ~(239)Pu. The most penalizing matrix is made of polyethylene with an apparent density of 0.7 g cm~(-3), which leads to a mass detection limit of 519 mg of ~(240)Pu in passive mode, and 564 mg of ~(235)U or 349 mg of ~(239)Pu in active mode. Measurement time is 30 min for both passive and active modes. Next steps will be a complete investigation of matrix effects based on intensive Monte-Carlo calculations and an experimental design to figure out the appropriate corrections. Experiments will also be conducted at CEA Cadarache Nuclear Measurement Laboratory with the construction and the assembly of the neutron system prototype, and the measurement of mock-up drums filled with different matrices.
机译:在MICADO H2020项目的框架中,正在开发一种被动和活性的中子测量系统,以估计遗留遗留废物鼓的核材料质量和中间放射性水平的核材料质量。已经进行了Monte-Carlo模拟,设计了一种新的模块化和可移动中子系统,主要目的是在无源模式下的性能之间达到良好的权衡,即中子符合计数,以及具有差分灭绝技术的主动询问模式。比较不同的设计,主要在其温和材料,石墨和聚乙烯中不同。考虑到其在广泛的原位地点和核设施中,这项参数研究允许我们定义了考虑到实际限制的原型。原型的总中子检测效率为6.75%,如空滚筒计算,即没有废矩阵。还基于滚筒内核材料的均匀分布的假设估计了核材料等同物的检测限估计,填充有四种类型的基质,覆盖项目框架中定义的核废料鼓的范围。最有利的基质是由无源模式和活性模式中的聚乙烯在无源模式和聚乙烯中制成的,表观密度分别为0.7g cm〜(-3)和0.1g cm〜(-3)。计算出的质量检测限度分别为68mg〜(240)PU,62mg〜(235)U和39mg〜(239)PU。最惩罚基质由聚乙烯制成,表观密度为0.7g cm〜(-3),其导致无源模式下519mg〜(240)PU的质量检测限,564毫克〜(235)在活动模式下,U或349毫克〜(239)PU。对于无源模式,测量时间为30分钟。下一步将是基于密集的蒙特卡罗计算和实验设计来完整的矩阵效应的调查,以确定适当的校正。在CEA Cadarache核测量实验室中还将进行实验,以及中子系统原型的组装,以及填充不同矩阵的模型鼓的测量。

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