紧凑、节能的中子源:钍育成器和加速器嬗变废物的使能技术

A. Hershcovitch, Thomas Roser
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摘要

背景 为满足对大通量中子源的需求,目前使用和/或提议的大通量中子源要么基于核反应堆,要么基于加速器。第一种方法的缺点是产生放射性废物,扩散风险高。基于加速器的溅射中子源复杂、昂贵且耗电量大。描述了一种新型中子源,该中子源由一束氘(能量约为 100 KeV)射入一个充满氚气和/或氚等离子体的管子中,产生 D-T 聚变反应,其产物为 14.06 MeV 中子和 3.52 MeV α粒子。在管子的另一端,回收了未发生相互作用的氘离子的能量。可利用适当厚度的铍壁吸收 14 MeV 中子并释放 2 - 3 个低能中子。每个离子源和离子管构成一个模块。使用多个单元可以形成更大的系统。结果 计算表明,这种方法是可行的,并具有多种优势。相关性:这一中子源概念的可能应用包括亚临界核增殖反应堆和放射性废物的嬗变。结论 由于其简单性,可以使用廉价的桌面实验来测试这一想法。
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Compact, energy efficient neutron source: Enabling Technology for Thorium Breeder and Accelerator Transmutation of Waste
Background To fulfill need for large flux neutron sources, presently utilized and/or proposed large flux neutron sources are either nuclear reactor based or accelerator based. First method has shortcomings: in radioactive waste generation high proliferation risk. Accelerator based spallation neutron sources are complex, expensive and use large amounts of power. Method A novel neutron source comprising of a deuterium beam (energy of about 100 KeV) injected into a tube filled with tritium gas and/or tritium plasma that generates D-T fusion reactions, whose products are 14.06 MeV neutrons and 3.52 MeV alpha particles, is described. At the opposite end of the tube, the energy of deuterium ions that did not interact was recovered. Beryllium walls of appropriate thickness can be utilized to absorb 14 MeV neutrons and release 2 – 3 low-energy neutrons. Each ion source and tube forms a module. Larger systems can be formed using multiple units. Results Calculations indicate that this method is feasible and has multiple advantages. Relevance: among the possible applications of this neutron source concept are subcritical nuclear breeder reactors and transmutation of radioactive waste. Conclusion Due to its simplicity the idea can be tested using an inexpensive tabletop experiment.
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