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Reactor and fuel cycle performance of light water reactor fuel with ~(235)U enrichments above 5%

机译:〜(235)U浓缩度高于5%的轻水堆燃料的反应堆和燃料循环性能

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Recent advances in nuclear fuel materials research, particularly on the topic of accident-tolerant fuels, have brought up potential opportunities for expanding the operating envelope of existing light water reactors. As many of the performance improvements offered by these technologies may be most fully realized by increasing fuel enrichment beyond the standard 5% limit, this paper examines the potential reactor performance and fuel cycle performance of low-enriched uranium oxide fueled light water reactors by generically considering pressurized water reactors with U-235 enrichment from 5 to 7%. Advanced cladding, including accident-tolerant cladding, has the potential to increase fuel burnup limits related to hydrogen in the cladding that coincide with those limits associated with end-of-life reactivity. Therefore, higher enrichment will be necessary in order to realize the higher fuel burnups. This work includes evaluation of the fuel cycle length, discharge burnup, reactivity coefficients, and fuel cycle performance, including radioactive waste and environmental impact metrics per unit energy generated. The analysis was performed using the evaluation metrics from the US Department of Energy Office of Nuclear Energy Fuel Cycle Evaluation and Screening Study.The reactor performance and safety analysis show that enrichments between 5 and 7% would have similar fuel temperature and moderator temperature coefficients. However, the soluble boron coefficient would decrease in magnitude, requiring more corrosive boric acid in the coolant or other methods of reactivity control during the fuel cycle. At these higher enrichments the maximum burnup at the rim of the fuel pellet would increase by almost a factor of two, which is expected to impact the formation of high-burnup structure in the fuel and the corresponding thermo-mechanical fuel properties.The fuel cycle performance assessment shows that increasing enrichment reduces the quantity of highlevel waste disposed per unit energy generated, but it increases the natural resource requirements normalized to a gigawatt-electricity-per-year basis. Another impact is the slightly higher discharge burnup, resulting in somewhat different activity levels of the spent nuclear fuel and high-level waste radioactivity at 100 and 100,000 years after fuel discharge. The environmental impacts-including land use, water use, carbon emission, and radiological exposure-are of the same magnitude per unit energy generated. However, the impacts are distributed differently. Less than 5% enrichment has marginally more impact on the back-end of the fuel cycle, and greater than 5% enrichment has marginally more impact on the front-end of the fuel cycle. Ultimately, no neutronic or reactor safety hindrances to employing light water reactor fuel with enrichments greater than 5% are identified; given the achievable reactor performance benefits with advanced fuels, further practical exploration of increased enrichment fuel is recommended. (C) 2020 Elsevier Ltd. All rights reserved.
机译:核燃料材料研究的最新进展,特别是在事故容忍燃料方面的研究,为扩大现有轻水反应堆的运行范围提供了潜在机会。由于这些技术提供的许多性能改进可以通过将燃料浓缩度提高到超过标准5%的限值来最充分地实现,因此,本文通篇考虑了低浓缩铀氧化物燃料燃料轻水反应堆的潜在反应堆性能和燃料循环性能U-235浓缩度从5到7%的压水反应堆。先进的熔覆层(包括耐事故熔覆层)有可能增加与熔覆层中氢有关的燃料燃耗极限,该极限与寿命终止反应性相关。因此,为了实现更高的燃耗,将需要更高的浓缩度。这项工作包括评估燃料循环长度,放电燃耗,反应系数和燃料循环性能,包括每单位产生的能量的放射性废物和环境影响指标。该分析是使用美国能源部核能燃料循环评估与筛选研究办公室的评估指标进行的。反应堆性能和安全性分析表明,浓缩度在5%至7%之间的燃料温度和调节剂温度系数相似。然而,可溶硼系数将减小幅度,在燃料循环期间需要冷却剂中具有更多腐蚀性的硼酸或其他反应性控制方法。在这些较高的浓度下,燃料芯块边缘的最大燃尽将增加几乎两倍,这预计会影响燃料中燃点高燃点结构的形成以及相应的热机械燃料特性。绩效评估显示,增加的浓缩减少了单位能源产生的高放废物的处置量,但是却增加了以每年千兆瓦电为基础的自然资源需求。另一个影响是放电燃耗稍高,导致乏核燃料的活动水平有所不同,并且在燃料放电后100年和100,000年时,高放射性废物的放射性较高。每产生的单位能量对环境的影响(包括土地使用,水使用,碳排放和辐射暴露)具有相同的程度。但是,影响的分布方式不同。小于5%的浓缩度对燃料循环的后端影响较大,而大于5%的浓缩度对燃料循环的前端影响较大。最终,没有发现使用浓缩度大于5%的轻水反应堆燃料的中子学或反应堆安全障碍;鉴于先进燃料可实现的反应堆性能优势,建议对增加的浓缩燃料进行进一步的实际探索。 (C)2020 Elsevier Ltd.保留所有权利。

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