A Gamma-Compensated Helium-4 Ion Chamber for Spent Nuclear Fuel Monitoring.

O. Searfus, Jeremy M. Osborn, I. Jovanovic
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Abstract

Management of the spent nuclear fuel (SNF) is an intriguing problem from a safeguards instrumentation perspective: for safety reasons, it must be packed with a large amount of shielding to prevent radiation exposure to facility workers and the public, and with neutron-absorbing materials to prevent criticality. SNF is typically also at high temperature in dry storage and during transportation, precluding the use of many types of radiation sensors internal to a fuel cask. The radiation environment of SNF casks includes intense gamma radiation originating mostly from fission fragments, and a smaller but still sizable amount of fast neutron radiation, both from spontaneous fission of transuranic isotopes and (alpha,n) reactions with oxygen in the fuel matrix. Fast neutrons emitted by SNF are of particular interest for safeguards, as plutonium is the most significant contributor to the neutron source term. A gamma-“compensated” 4 He ion chamber would in some ways be an ideal instrument for use in SNF safeguards: 4 He has a high cross-section for fast neutron elastic scattering, it does not contain any materials that are consumed or transmuted, and it is a simple gas-based detector that is resilient to high temperature and radiation damage. The detector must be primarily sensitive to fast neutrons, as the thermal neutron population in a cask is depressed by neutron-absorbing materials. The gamma-ray contribution to the chamber current can be compensated by sheathing two identical tubes in different thicknesses of tungsten, a strong attenuator of gamma rays. In this way, the fractional difference in current between the two tubes is directly proportional to the fractional contribution of gamma rays to the signal in the thinner tube, which can then be subtracted to yield the fast neutron-only signal. In this work, Monte Carlo simulations are used to predict the performance of a 4 He-based detector system deployed at a realistic SNF cask. The sensitivity to a fuel diversion scenario is evaluated, and the gamma-compensation relationship is validated across the lifetime of a typical SNF cask.
用于乏核燃料监测的γ补偿氦-4离子室。
从安全保障仪器的角度来看,乏核燃料(SNF)的管理是一个有趣的问题:出于安全原因,它必须用大量的屏蔽物来防止辐射暴露给设施工作人员和公众,并用中子吸收材料来防止临界。SNF在干燥储存和运输过程中通常也处于高温状态,因此无法在燃料桶内部使用许多类型的辐射传感器。SNF桶的辐射环境包括主要来自裂变碎片的强烈伽马辐射,以及来自超铀同位素自发裂变和燃料基质中氧(α,n)反应的较小但仍相当数量的快中子辐射。SNF发射的快中子对保障特别有意义,因为钚是中子源项的最重要贡献者。在某些方面,伽马“补偿”的氦离子室将是用于SNF防护的理想仪器:氦具有高的快中子弹性散射截面,它不包含任何被消耗或变形的材料,它是一个简单的气体基探测器,对高温和辐射损伤具有弹性。探测器必须首先对快中子敏感,因为桶中的热中子数量受到中子吸收材料的抑制。伽马射线对腔室电流的贡献可以通过在不同厚度的钨中包裹两个相同的管来补偿,钨是伽马射线的强衰减器。这样,两管之间电流的分数差与较薄管中伽马射线对信号的分数贡献成正比,然后可以将其减去以产生仅快中子的信号。在这项工作中,蒙特卡罗模拟用于预测部署在现实SNF桶上的4he探测器系统的性能。对燃料导流情景的敏感性进行了评估,并在典型SNF桶的整个生命周期内验证了伽马补偿关系。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
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