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Reactor Physics Monitoring of a Source-Driven Subcritical System in Stationary State by Deterministic and Probabilistic Deep Neural Networks 利用确定性和概率性深度神经网络监测静态源驱动亚临界系统的反应堆物理特性
IF 1.2 3区 工程技术 Q3 NUCLEAR SCIENCE & TECHNOLOGY Pub Date : 2024-04-01 DOI: 10.1080/00295639.2024.2328957
Ronald Daryll E. Gatchalian, Pavel V. Tsvetkov
Reactivity measurement methods, like the Amplified Source Method (ASM), link observable quantities to integral physics parameters characterizing subcritical assemblies (SCAs). These methods were mo...
反应性测量方法,如放大源方法(ASM),将可观测量与表征亚临界组件(SCA)的整体物理参数联系起来。这些方法都是在......
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引用次数: 0
Experimental Covariance Determination for Critical Integral Experiments 临界积分实验的实验协方差确定
IF 1.2 3区 工程技术 Q3 NUCLEAR SCIENCE & TECHNOLOGY Pub Date : 2024-04-01 DOI: 10.1080/00295639.2024.2328452
Eric Aboud, Jesse Norris, Daniel Siefman
Integral benchmarks for criticality safety and nuclear data validation require expensive uncertainty quantification studies. In general, uncertainty quantification techniques ignore correlations be...
临界安全和核数据验证的整体基准需要昂贵的不确定性量化研究。一般来说,不确定性量化技术会忽略与核反应堆的相关性。
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引用次数: 0
Coupled Neutronics-Thermal-Hydraulic Modeling of a Molten Salt Reactor: The Aircraft Reactor Experiment 熔盐反应堆的中子-热-水耦合建模:飞机反应堆实验
IF 1.2 3区 工程技术 Q3 NUCLEAR SCIENCE & TECHNOLOGY Pub Date : 2024-04-01 DOI: 10.1080/00295639.2024.2328964
François Martin, André Bergeron, Guillaume Campioni, Yannick Gorsse, Nathan Greiner, Elsa Merle
The CEA multiphysics tool combining the deterministic neutronics code APOLLO3® and the computational fluid dynamics (CFD) platform TRUST/TrioCFD is used to model the first-ever-built molten salt nu...
CEA的多物理场工具结合了确定性中子学代码APOLLO3®和计算流体动力学(CFD)平台TRUST/TrioCFD,用于对有史以来首次建造的熔盐核电站进行建模。
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引用次数: 0
On the Assumptions Behind Statistical Sampling: A 235U Fission Yield Uncertainty Propagation Case Study 关于统计取样背后的假设:235U 裂变当量不确定性传播案例研究
IF 1.2 3区 工程技术 Q3 NUCLEAR SCIENCE & TECHNOLOGY Pub Date : 2024-03-19 DOI: 10.1080/00295639.2024.2323217
Enrica Belfiore, Federico Grimaldi, Luca Fiorito, Pablo Romojaro, Gašper Žerovnik, Pierre-Etienne Labeau, Sandra Dulla
Monte Carlo sampling is frequently employed for uncertainty quantification in depletion calculations. Several assumptions are needed to perform this analysis. In this work, an assessment of these a...
Monte Carlo 取样经常被用于损耗计算中的不确定性量化。进行这种分析需要几个假设。在这项工作中,对这些假设进行了评估。
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引用次数: 0
Three-Dimensional Full-Core BEAVRS Using OpenMOC with Transport Equivalence 使用具有传输等效性的 OpenMOC 的三维全核心 BEAVRS
IF 1.2 3区 工程技术 Q3 NUCLEAR SCIENCE & TECHNOLOGY Pub Date : 2024-03-19 DOI: 10.1080/00295639.2024.2321661
G. Giudicelli, B. Forget, K. Smith
Using an optimized implementation of the three-dimensional (3D) method of characteristics for neutron transport, along with a novel equivalence method for transport calculations that was designed t...
利用中子输运三维(3D)特性法的优化实施,以及设计用于输运计算的新颖等效方法,该方法可用于中子输运计算。
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引用次数: 0
Multiscale Modeling of Flow in Rod Bundles: From Direct Numerical Simulation and Subchannel to Coarse-Mesh CFD 杆束流动的多尺度建模:从直接数值模拟和子通道到粗网格 CFD
IF 1.2 3区 工程技术 Q3 NUCLEAR SCIENCE & TECHNOLOGY Pub Date : 2024-03-14 DOI: 10.1080/00295639.2024.2318837
Adam R. Kraus, Elia Merzari
Fast and accurate evaluation of flow and heat transfer phenomena in rod bundles is a problem of long-standing interest in nuclear engineering. Computational fluid dynamics (CFD) can provide accurat...
快速准确地评估棒束中的流动和传热现象是核工程领域长期关注的问题。计算流体动力学(CFD)可提供精确的流体动力学参数,并能对棒束中的流动和传热现象进行评估。
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引用次数: 0
Improved Collision Probability Analysis of the Double-Heterogeneity Problem Based on Matrix Chord Length Correction 基于矩阵弦长校正的双异质问题碰撞概率分析改进
IF 1.2 3区 工程技术 Q3 NUCLEAR SCIENCE & TECHNOLOGY Pub Date : 2024-03-14 DOI: 10.1080/00295639.2024.2311595
Zhaoyu Liang, Ding She, Yutong Wen, Lei Shi, Zuoyi Zhang
Dispersion fuel exhibits excellent safety performance and effectively reduces the risk of radioactive leakage, making it widely applied in high-temperature gas-cooled reactors (HTGRs) and other adv...
分散燃料具有优异的安全性能,可有效降低放射性泄漏的风险,因此被广泛应用于高温气冷堆(HTGR)和其他先进反应堆。
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引用次数: 0
A Consequence-Informed Licensing Path Selection for the Design of Physical Protection Systems at Commercial Nuclear Power Facilities 商用核电设施实物保护系统设计的后果知情许可路径选择
IF 1.2 3区 工程技术 Q3 NUCLEAR SCIENCE & TECHNOLOGY Pub Date : 2024-03-12 DOI: 10.1080/00295639.2024.2316930
Thomas Freyman, Karen Vierow Kirkland
The survivability of the domestic nuclear power industry depends on the cost-competitiveness of safe and secure nuclear power generation. Advanced reactor design concepts aim to have increased safe...
国内核电工业的生存能力取决于安全可靠的核能发电的成本竞争力。先进的反应堆设计理念旨在提高核电厂的安全...
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引用次数: 0
Analytic Error Analysis of the Partial Derivatives Cross-Section Model—I: Derivation 部分衍生物横截面模型的误差分析-I:推导
IF 1.2 3区 工程技术 Q3 NUCLEAR SCIENCE & TECHNOLOGY Pub Date : 2024-03-05 DOI: 10.1080/00295639.2023.2288308
Thomas Folk, Siddhartha Srivastava, Dean Price, Krishna Garikipati, Brendan Kochunas
Accurate assessment of uncertainties in cross-section data is crucial for reliable nuclear reactor simulations and safety analyses. In this study, we focus on the interpolation procedure of the par...
准确评估横截面数据的不确定性对于可靠的核反应堆模拟和安全分析至关重要。在这项研究中,我们重点讨论了截面数据的插值程序。
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引用次数: 0
User Impressions and Gait Analysis of Exoskeleton Device Usage in Generalized Tank Farm Activities 外骨骼设备在普通油罐区活动中的用户印象和步态分析
IF 1.2 3区 工程技术 Q3 NUCLEAR SCIENCE & TECHNOLOGY Pub Date : 2024-03-05 DOI: 10.1080/00295639.2024.2316948
Janelle Bottom, David Wood, Tamzidul Mina, Savannah Bradley, Michal Rittikaidachar, Alexandria Miera, Jason Wheeler
Tank farm workers involved in nuclear cleanup activities perform physically demanding tasks, typically while wearing heavy personal protective equipment (PPE). Exoskeleton devices have the potentia...
参与核清理活动的油罐区工人通常在穿着厚重的个人防护设备 (PPE) 的情况下执行体力要求很高的任务。外骨骼设备有可能...
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引用次数: 0
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Nuclear Science and Engineering
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