用机器学习确定压水反应堆VVER-1000的暂态电平

IF 2.3 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Ceyhun Yavuz, Senem Şentürk Lüle
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引用次数: 0

摘要

核反应堆在发生事故时具有严重后果的重大风险。因此,确保其安全运行的必要性是至关重要的。在瞬态条件下,关键参数时间序列可能以不立即可见的方式波动。因此,检测这些瞬变对于预防措施和保护行动至关重要。本文的工作重点是确定53种瞬态子情景,这些情景来自于通过抽棒插入反应性、稳压器蒸汽泄漏、流量损失和冷却剂损失事故,这些事故同时影响VVER型反应堆的热腿和冷腿主瞬态。已经处理了91个特征,以465,465个数据点进行模型评估。k -最近邻、决策树分类器、随机森林分类器、梯度增强、逻辑回归、支持向量机、Naïve贝叶斯和多层感知器方法分别用于三种不同的方法。对于识别子场景,考虑了一步、两步和分组一步方法。在一步法中,确定了精确的子方案(例如,抽油杆回撤量为25%)。在两步方法中,首先确定主要瞬态(例如抽油杆撤回),然后确定子情景(例如抽油杆撤回25%)。在分组一步法中,将子情景分组(例如,抽油杆拔出20%至30%)以提高预测的准确性。一步法的最高准确率为74.66%,两步法的主瞬态识别准确率为99.51%,总准确率为86.44%。子场景分组的精度较低,但精度较高,准确率为92.33%。总之,采用两步法实现了VVER型反应器的快速瞬态辨识。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Transient level determination with machine learning for pressurized water reactor VVER-1000
Nuclear reactors carry significant risks of severe consequences in the event of accidents. Therefore, the imperative of ensuring their safe operation is paramount. During transient conditions, key parameter time series may fluctuate in ways that are not immediately visible. Therefore, the detection of these transients is essential for preventive measures and protective actions. This work focuses on identification of 53 transient sub-scenarios derived from reactivity insertion via rod withdrawal, steam leak from pressurizer, loss of flow and loss of coolant accidents affecting both hot and cold legs main transient for VVER type reactor. 91 features have been handled for model assessment with 465,465 data points. K-Nearest Neighbor, Decision Tree Classifier, Random Forest Classifier, Gradient Boosting, Logistic Regression, Support Vector Machine, Naïve Bayes and Multilayer Perceptron methods were applied for three different approaches. A one-step, two-steps, and grouped one-step approaches were considered for identification sub-scenarios. In the one-step approach, the exact sub-scenario (e.g. 25% rod withdrawal) was identified. In the two steps approach, the main transients (e.g. rod withdrawal) were identified first and then the sub-scenario (e.g. 25% rod withdrawal) were identified. In the grouped one-step approach, sub-scenarios were grouped (e.g. 20 to 30% rod withdrawal) to increase the accuracy of predictions. While the highest accuracy in one-step approach was 74.66%, two-steps approach had 99.51% main transient identification but 86.44% total accuracy. The grouping of sub-scenarios achieved a less precise but more accurate result with 92.33% accuracy. In conclusion, fast transient identification for VVER type reactors was achieved with two-steps approach.
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来源期刊
Annals of Nuclear Energy
Annals of Nuclear Energy 工程技术-核科学技术
CiteScore
4.30
自引率
21.10%
发文量
632
审稿时长
7.3 months
期刊介绍: Annals of Nuclear Energy provides an international medium for the communication of original research, ideas and developments in all areas of the field of nuclear energy science and technology. Its scope embraces nuclear fuel reserves, fuel cycles and cost, materials, processing, system and component technology (fission only), design and optimization, direct conversion of nuclear energy sources, environmental control, reactor physics, heat transfer and fluid dynamics, structural analysis, fuel management, future developments, nuclear fuel and safety, nuclear aerosol, neutron physics, computer technology (both software and hardware), risk assessment, radioactive waste disposal and reactor thermal hydraulics. Papers submitted to Annals need to demonstrate a clear link to nuclear power generation/nuclear engineering. Papers which deal with pure nuclear physics, pure health physics, imaging, or attenuation and shielding properties of concretes and various geological materials are not within the scope of the journal. Also, papers that deal with policy or economics are not within the scope of the journal.
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