中温热管反应堆燃料优化与瞬态分析

IF 3.2 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Zenghao Liu , Laishun Wang , Chen Hu , Binhuo Yan
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引用次数: 0

摘要

微型反应堆,特别是热管冷却反应堆(hpr),由于其固有的安全性、紧凑的尺寸和可运输性,已被公认为分散电力市场的主要候选者。然而,传统的hpr在高温下运行,带来了与材料腐蚀、热应力和启动失败相关的挑战。为了解决这些问题,已经提出了在350°C下运行的中温热管冷却反应堆(MTRs)。在这项工作中,系统地评估了三种具有代表性的燃料:铀-锆氢化(U-ZrH1.6),二氧化铀(UO2)和铀-硅化化合物(U3Si2-Al)。稳态计算表明,这三种燃料都适合MTR的正常运行。通过瞬态模拟来评估燃料在单热管和多热管失效情况下的性能。结果表明,虽然所有燃料的中心线温度都低于其各自的熔点,但U3Si2-Al燃料的最高温度超过了推荐的安全阈值。尽管认为U-ZrH1.6燃料的中子经济性略好于UO2,但确定其安全裕度明显低于UO2。综上所述,UO2被确定为MTR的首选候选燃料。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Fuel optimization and transient analysis of a medium temperature heat pipe reactor
Micro reactors, particularly Heat Pipe cooled Reactors (HPRs), have been recognized as leading candidates for decentralized electricity markets due to their inherent safety, compact size, and transportability. However, conventional HPRs are operated at high temperatures, posing challenges related to material corrosion, thermal stresses, and startup failures. To address these issues, Medium Temperature Heat Pipe cooled Reactors (MTRs) operating at 350 °C have been proposed. In this work, three representative fuels are systematically evaluated: uranium-zirconium hydride (U-ZrH1.6), uranium dioxide (UO2), and uranium-silicide composite (U3Si2-Al). All three fuels are indicated by steady-state calculations to be suitable for normal operation of MTR. Transient simulations are conducted to assess the behavior of fuels under single and multiple heat pipe failure situations. Results are shown to indicate that while the centerline temperatures of all fuels remain below their respective melting points, the maximum temperature of U3Si2-Al fuel is found to exceed the recommended safety threshold. Although the U-ZrH1.6 fuel is considered to exhibit slightly better neutron economic performance than UO2, its safety margin is determined to be significantly lower than that of UO2. In conclusion, UO2 is identified as the preferred fuel candidate for MTR.
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来源期刊
Progress in Nuclear Energy
Progress in Nuclear Energy 工程技术-核科学技术
CiteScore
5.30
自引率
14.80%
发文量
331
审稿时长
3.5 months
期刊介绍: Progress in Nuclear Energy is an international review journal covering all aspects of nuclear science and engineering. In keeping with the maturity of nuclear power, articles on safety, siting and environmental problems are encouraged, as are those associated with economics and fuel management. However, basic physics and engineering will remain an important aspect of the editorial policy. Articles published are either of a review nature or present new material in more depth. They are aimed at researchers and technically-oriented managers working in the nuclear energy field. Please note the following: 1) PNE seeks high quality research papers which are medium to long in length. Short research papers should be submitted to the journal Annals in Nuclear Energy. 2) PNE reserves the right to reject papers which are based solely on routine application of computer codes used to produce reactor designs or explain existing reactor phenomena. Such papers, although worthy, are best left as laboratory reports whereas Progress in Nuclear Energy seeks papers of originality, which are archival in nature, in the fields of mathematical and experimental nuclear technology, including fission, fusion (blanket physics, radiation damage), safety, materials aspects, economics, etc. 3) Review papers, which may occasionally be invited, are particularly sought by the journal in these fields.
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