Coupled neutronics, thermochemistry, corrosion modeling and sensitivity analyses for isotopic evolution in molten salt reactors

IF 3.3 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Mauricio E. Tano, Samuel A. Walker, Abdalla Abou-Jaoude, Robin Roper, Toni Karlsson, Mikael C.F. Karlsson, Parikshit Bajpai, Rodrigo de Oliveira, Ramiro Freile, Vasileios Kyriakopoulos, Mustafa K. Jaradat, Piyush Sabharwall
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Abstract

This study presents a computational methodology for analyzing isotopic evolution and associated uncertainties in molten salt reactors (MSRs), focusing on both fluoride- and chloride-based fuel salts. The primary goal is to enhance the understanding of isotopic behavior in MSRs and provide data to support future experimental efforts. The methodology integrates transport-coupled depletion calculations using OpenMC, equilibrium thermodynamics modeling with Thermochimica, and a corrosion model. Sensitivity analyses are performed to evaluate the impact of power density, air ingress, and humidity content on isotopic evolution in MSR concepts. This study examines representative F- and Cl-based MSR designs, highlighting the dominant influence of power density on isotopic composition, which significantly affects isotope production and depletion rates, accounting for approximately 76% of the observed variance in element concentration. Air ingress and humidity content also affect the redox potential, solubility of heavier elements, and corrosion rates, thereby altering the expected isotopic evolution in the reactor. On average, air ingress accounts for around 17% of the variance in element concentrations, while humidity explains the remaining 7%. These variances differ significantly from element to element, depending on the element’s role in depletion, redox potential evolution, and galvanic corrosion. The findings indicate that power density, air ingress, and humidity content are all critical factors for optimizing reactor design and operational strategies. Furthermore, the study provides expected ranges for key impurities in the fuel salt, which are crucial for guiding future experimental studies and refining MSR designs. Finally, this study demonstrates the importance of modeling depletion coupled with the evolution of redox potential and chemical interactions in MSR fuel salts.

Abstract Image

熔盐反应堆同位素演变的耦合中子、热化学、腐蚀建模和敏感性分析
本研究介绍了一种用于分析熔盐反应堆(MSR)中同位素演变和相关不确定性的计算方法,重点关注氟化盐和氯化物燃料盐。主要目标是加深对 MSR 中同位素行为的理解,并为未来的实验工作提供数据支持。该方法整合了使用 OpenMC 进行的输运耦合损耗计算、使用 Thermochimica 进行的平衡热力学建模以及腐蚀模型。进行了敏感性分析,以评估功率密度、空气进入和湿度含量对 MSR 概念中同位素演变的影响。这项研究考察了具有代表性的以 F 和 Cl 为基础的 MSR 设计,突出显示了功率密度对同位素组成的主要影响,它显著影响了同位素的产生和损耗率,约占观察到的元素浓度差异的 76%。进气和湿度也会影响氧化还原电位、较重元素的溶解度和腐蚀速率,从而改变反应堆中预期的同位素演变。平均而言,空气进入约占元素浓度差异的 17%,而湿度则占其余的 7%。不同元素之间的差异很大,这取决于元素在耗竭、氧化还原电位演变和电化学腐蚀中的作用。研究结果表明,功率密度、空气进入量和湿度含量都是优化反应堆设计和运行策略的关键因素。此外,研究还提供了燃料盐中关键杂质的预期范围,这对于指导未来的实验研究和完善 MSR 设计至关重要。最后,这项研究证明了对耗竭以及 MSR 燃料盐中氧化还原电位和化学相互作用的演变进行建模的重要性。
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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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