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PRELIMINARY NEUTRON SIMULATION OF CERAMIC FAST REACTOR

机译:陶瓷快速反应器的初步中子模拟

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In this paper, preliminary neutron physical properties of ceramic fast reactor (CFR) are simulated and analyzed. The CFR core consists of ceramic materials, including nuclear fuels, coolants, structural materials, reflective and absorption materials. These ceramics improve inherent safety levels substantially, increase breeding performance, and enhance the power-generation efficiency. The CFR has the potential to operate and breed more than 30 years. The performance of the CFR was simulated focusing on neutron-related effects. The parameters discussed contain fast neutron energy spectrum, the ideal effective multiplication-factor, nuclides mass changes, breeding performance, operation mode, etc. Furthermore, the strengths of the proposed reactor system are discussed. In the future nuclear energy system, CFR may be one of the existing alternative novel reactor type.
机译:本文对陶瓷快堆(CFR)的初步中子物理性质进行了模拟和分析。 CFR芯由陶瓷材料组成,包括核燃料,冷却剂,结构材料,反射和吸收材料。这些陶瓷大大提高了固有安全水平,提高了繁殖性能,并提高了发电效率。 CFR具有运行和繁殖超过30年的潜力。对CFR的性能进行了模拟,重点是中子相关效应。讨论的参数包括快速中子能谱,理想的有效倍增因子,核素质量变化,繁殖性能,运行模式等。此外,还讨论了拟议的反应堆系统的强度。在未来的核能系统中,CFR可能是现有替代新型反应堆类型之一。

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