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Replacing a 252C/ Source with a Neutron Generator in a Shuffler - A Conceptual Design Performed with MCNPX

机译:用Shuffler用中子发生器替换252C /源 - 使用MCNPX进行的概念设计

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The 252C f shuffler has been widely used in nuclear safeguards and radioactive waste management to assay fissile isotopes, such as 235U or 239Pu, present in a variety of samples, ranging from small cans of uranium waste to metal samples weighing several kilograms. Like other non-destructive assay instruments, the shuffler uses an interrogating neutron source to induce fissions in the sample. Although shufflers with 252Cf sources have been reliably used for several decades, replacing this isotopic source with a neutron generator presents some distinct advantages. Neutron generators can be run in a continuous or pulsed mode, and may be turned off, eliminating the need for shielding and a shuffling mechanism in the shuffler. There is also essentially no dose to personnel during installation, and no reliance on the availability of 252Cf. Despite these advantages, the more energetic neutrons emitted from the neutron generator (14.1 MeV for D-T generators) present some challenges for certain material types. For example when the enrichment of a uranium sample is unknown, the fission of 238U is generally undesirable. Since measuring uranium is one of the main uses of a shuffler, reducing the delayed neutron contribution from 238U is desirable. Hence, the shuffler hardware must be modified to accommodate a moderator configuration near the source to tailor the interrogating spectrum in a manner which promotes sub-threshold fissions (below 1 MeV) but avoids the over-moderation of the interrogating neutrons so as to avoid self-shielding. In this study, where there are many material and geometry combinations, we use the Monte Carlo N-Particle extended (MCNPX)1 transport code to model, design, and optimize the moderator configuration within the shuffler geometry. We then use the code to evaluate and compare the assay performances of both the modified shuffler and the current 252C f shuffler designs for different test samples. We investigate and quantify the matrix effect and the non-uniformity of the interrogating flux in each case. The modified geometry we propose in this study can serve as a guide in retrofitting shufflers that are already in use.
机译:252C F Shuffler已广泛应用于核保护和放射性废物管理,以测定裂变同位素,如235U或239Pu,这些样品中存在于各种样品中,从小罐的铀废料到称重几千克的金属样品。与其他非破坏性测定仪器一样,Shuffler使用询问中子源来诱导样品中的裂口。虽然具有252cf源的吊索已经可靠地使用了几十年,但用中子发生器替换这种同位素源具有一些​​不同的优势。中子发生器可以在连续或脉冲模式下运行,并且可以关闭,消除了在混室中屏蔽的需要和遮挡机构。在安装过程中,人员也没有给人,并且没有依赖于252CF的可用性。尽管存在这些优点,但从中子发生器发出的更高的能量中子(14.1 MeV for D-T发电机)对某些材料类型产生了一些挑战。例如,当铀样品的富集未知时,238U的裂变通常是不希望的。由于测量铀是Shuffler的主要用途之一,因此需要238U的延迟中子贡献。因此,必须修改Shuffler硬件以在源附近的主持人配置以促进促进子阈值裂缝(低于1MeV)的方式定制询问光谱,但避免询问中子的过度调节,以避免自我 - 屏蔽。在这项研究中,在有许多材料和几何组合的情况下,我们使用蒙特卡罗n-taster扩展(MCNPX)1传输代码来模拟,设计和优化Shuffler几何体内的主持人配置。然后,我们使用代码来评估和比较修改的Shuffler和当前252C F混洗机设计的测定性能,用于不同的测试样本。我们在每种情况下调查和量化矩阵效应和询问通量的不均匀性。我们在本研究中提出的修改几何可以用作改装已经使用的乳房的引导件。

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