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On the Possibility of Achieving Optimal Operating Modes of Hyperspeed Model Gas Centrifuges: 3D Numerical Simulation 超高速模型气体离心机实现最佳运行模式的可能性:三维数值模拟
IF 1.2 3区 工程技术 Q2 Energy Pub Date : 2024-04-22 DOI: 10.1080/00295639.2024.2332021
S. V. Bogovalov, I. V. Tronin, A. V. Vasilyev
In this paper, numerical simulation methods are used to study issues related to the optimal operating modes of hyperspeed (rotor velocity 1000 m/s and above) model gas centrifuges (GCs) of various ...
本文采用数值模拟方法,研究了与各种型号气体离心机(GCs)的超高速(转子速度 1000 m/s 及以上)最佳运行模式有关的问题。
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引用次数: 0
Analysis of Fission Matrix Databases with Nonuniform Fuel Temperature Profiles for Static and Transient Calculations 用于静态和瞬态计算的非均匀燃料温度曲线裂变矩阵数据库分析
IF 1.2 3区 工程技术 Q2 Energy Pub Date : 2024-04-22 DOI: 10.1080/00295639.2024.2328944
Maximiliano Dalinger, William Walters
Monte Carlo codes are the most accurate way to solve the neutronics in a reactor core but can be computationally expensive, especially for when feedback effects are considered or for transient calc...
Monte Carlo 代码是求解反应堆堆芯中子学问题的最精确方法,但计算成本很高,特别是在考虑反馈效应或进行瞬态计算时。
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引用次数: 0
MaCaw: Domain-Decomposed Monte Carlo Neutral Particle Transport on Unstructured Mesh in MOOSE MaCaw:MOOSE 中非结构网格上的域分解蒙特卡洛中性粒子传输
IF 1.2 3区 工程技术 Q2 Energy Pub Date : 2024-04-17 DOI: 10.1080/00295639.2024.2332009
G. Giudicelli, R. Crowder, L. Harbour, D. Gaston
MaCaw is a Multiphysics Object-Oriented Simulation Environment (MOOSE)–based application that enables domain-decomposed neutral particle transport calculations in MOOSE. It leverages MOOSE’s ray-tr...
MaCaw 是一款基于多物理场面向对象仿真环境 (MOOSE) 的应用程序,可在 MOOSE 中进行域分解中性粒子输运计算。它利用 MOOSE 的射线追踪技术,可对中性粒子进行...
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引用次数: 0
Hot Hydrogen Testing of W-Coated UN Kernels in a Mo30W Matrix 在 Mo30W 基质中对 W 涂层 UN 内核进行热氢测试
IF 1.2 3区 工程技术 Q2 Energy Pub Date : 2024-04-15 DOI: 10.1080/00295639.2024.2332001
Arne Cröll, Jamelle K. P. Williams, Brian Taylor, Martin P. Volz, Christopher McKinney, Timothy Coons, Jhonathan Rosales
Ceramic uranium mononitride (UN) is being considered as a reactor fuel for nuclear thermal propulsion. To avoid or reduce the dissociation of UN at the high temperatures needed, embedding it in a m...
人们正在考虑将陶瓷单氮化铀(UN)作为核热推进反应堆燃料。为了避免或减少 UN 在所需的高温下发生解离,将其嵌入陶瓷材料中是一种有效的方法。
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引用次数: 0
A Multilevel Approach for Direct Core Calculation Schemes 直接核心计算方案的多层次方法
IF 1.2 3区 工程技术 Q2 Energy Pub Date : 2024-04-15 DOI: 10.1080/00295639.2024.2329838
Antonio Galia
A method of dynamic homogenization was recently proposed as an alternative technique for three-dimensional (3D) core calculations using a direct approach. This technique allows for producing homoge...
最近提出了一种动态均质化方法,作为使用直接方法进行三维(3D)核心计算的替代技术。这种技术可以产生同质化的结果。
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引用次数: 0
Convergence Study of 2D Transport Method for Multigroup k-Eigenvalue Problems with High-Order Scattering Source Using Fourier Analysis 利用傅立叶分析法对具有高阶散射源的多组 k 特征值问题的二维传输方法的收敛性研究
IF 1.2 3区 工程技术 Q2 Energy Pub Date : 2024-04-12 DOI: 10.1080/00295639.2024.2310391
Boran Kong, Longfei Xu, Baiwen Li
The convergence behavior of a two-dimensional (2D) transport method has been derived by Fourier analysis for single-group problems with isotropic sources. However, in real calculation, to pursue pr...
对于各向同性源的单组问题,二维(2D)传输方法的收敛行为是通过傅立叶分析得出的。然而,在实际计算中,为了追求...
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引用次数: 0
Comparing Coupled Multiphysics Simulations of Pump-Driven Transients for a Pressurized Heavy Water Reactor 比较压水重水反应堆的泵驱动瞬态耦合多物理场模拟
IF 1.2 3区 工程技术 Q2 Energy Pub Date : 2024-04-12 DOI: 10.1080/00295639.2024.2331906
Santiago Bazzana, Juan I. Beliera, Dumitru Serghiuta, Alexandre Trottier
Comparison of results for global responses predicted by different multiphysics simulations of benchmark problems may fail to reveal potentially significant local modeling issues. An examination of ...
比较基准问题的不同多物理场模拟所预测的全局响应结果可能无法揭示潜在的重大局部建模问题。对...
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引用次数: 0
Demonstrating a Quantitative and Systematic Approach to Reducing Excess Conservativism in Nuclear Criticality Safety Analyses 展示在核临界安全分析中减少过度保守的定量和系统方法
IF 1.2 3区 工程技术 Q2 Energy Pub Date : 2024-04-10 DOI: 10.1080/00295639.2024.2323866
Sharbrenai Anise Holyk, Robert B. Hayes
Although reducing conservatism would alleviate unnecessary constraints in processing, storage, transportation, and disposal of nuclear materials, excessively conservative approaches are still utili...
尽管减少保守主义会减轻核材料在加工、储存、运输和处置过程中不必要的限制,但过度保守的方法仍然有用。
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引用次数: 0
Predicting Model Biases of the APOLLO3 Neutronics Code Using Machine Learning: Toward a Multiscale and Multifidelity Approach 利用机器学习预测 APOLLO3 中子代码的模型偏差:采用多尺度和多保真度方法
IF 1.2 3区 工程技术 Q2 Energy Pub Date : 2024-04-10 DOI: 10.1080/00295639.2024.2329837
Claire Terrazzoni, Laurent Buiron, Jean-Marc Palau
As part of the verification, validation, and uncertainty quantification process applied to neutronics deterministic codes, there is a requirement to expand the validation domain, especially to acco...
作为适用于中子确定性代码的验证、确认和不确定性量化过程的一部分,有必要扩大验证领域,特别是要考虑到中子确定性代码的不确定性。
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引用次数: 0
A Diffusion Scale Approximation for Stochastic Fission Chains with State Feedback 具有状态反馈的随机裂变链的扩散尺度近似值
IF 1.2 3区 工程技术 Q2 Energy Pub Date : 2024-04-04 DOI: 10.1080/00295639.2024.2324532
Chen Dubi, Anil K. Prinja
Modeling and simulation of stochastic fission chains, often referred to as zero power reactor noise or stochastic transport, is a central topic in nuclear science and engineering, with important pr...
随机裂变链的建模与仿真通常被称为零功率反应堆噪声或随机传输,是核科学与工程领域的核心课题,具有重要的意义。
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引用次数: 0
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Nuclear Science and Engineering
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