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Nuclear Science and Engineering 封面图

Nuclear Science and Engineering

IF1.3
论文数223
被引数3546
期刊论文 223
发表时间
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Hybrid SN-Diffusion Neutronics Method for Control Rod Modeling in Molten Salt Reactors熔盐反应堆控制棒建模的混合SN-扩散中子学方法
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IF1.3
delete2026-05-01
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PREAI
deletePark, Sun Myung; Huff, Kathryn D.; Munk, Madicken
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Adjoint-Based Surrogate Modeling of Detector Responses for Repositioned Volumetric Sources基于伴随的探测器响应的替代建模，用于重新定位的体积源
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IF1.3
delete2026-05-01
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PREAI
deleteRodriguez, Jason; Ragusa, Jean C.
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Surrogate Modeling for Neutron Transport: A Neural Operator Approach中子输运的代理建模：一种神经算子方法
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IF1.3
delete2026-05-01
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PREAI
deleteSahadath, Md Hossain; Cheng, Qiyun; Pan, Shaowu; Ji, Wei
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A Systematic Review of Physical Security Assessment Approaches for Nuclear Facilities核设施物理安全评估方法的系统综述
deleteNuclear Science and Engineering
IF1.3
delete2026-05-01
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PREAI
deleteLigam, Alfred Sanggau; Abdul Rahman, Irman; Idris, Mohd Idzat; Abdul Karim, Julia; Dunstan Mandau, Loviana Lenyu
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Adaptation and Extension of a Margin-Based Approach for System-Level Health Assessment and Decision-Making基于裕度的方法在系统级健康评估和决策制定中的适应与扩展
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IF1.3
delete2026-05-01
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deleteZanotelli, Mattia; Ifeanyi, Ark; Mandelli, Diego; Coble, Jamie
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Computational Verification and Experimental Validation of BSOLVE - A New Multi-Group Burnup, Depletion, and Decay Computer Code for Advanced Nuclear Power SystemsBSOLVE - 一种用于先进核动力系统的多群燃耗、亏损和衰变计算机代码的计算验证和实验验证
deleteNuclear Science and Engineering
IF1.3
delete2026-05-01
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deleteWang, Meng-Jen; Sjoden, Glenn E.; Kimball, Taylor; Hines, Corey
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Group Constants Generation and SPH Correction Applied to the Westinghouse LFR Design群常数生成及SPH修正在西屋公司LFR设计中的应用
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IF1.3
delete2026-05-01
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PREAI
deleteVita, Christian; Abrate, Nicolo'; Dulla, Sandra; Franceschini, Fausto
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Special Issue Featuring Selected Papers from the 28th International Conference on Transport Theory (ICTT28)第28届输运理论国际会议（ICTT28）精选论文专刊
deleteNuclear Science and Engineering
IF1.3
delete2026-04-03
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PREAI
deleteMcClarren, Ryan; Ganapol, Barry
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Analysis of a Heat Balance Experiment in the TREAT Reactor with SPARTA and OpenMC使用SPARTA和OpenMC对TREAT反应堆的热平衡实验进行分析
deleteNuclear Science and Engineering
IF1.3
delete2026-04-01
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deleteFerney, Paul A.; DeHart, Mark D.
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1D Monoenergetic Discrete Ordinates Transport with Faux Quadrature and Nascent Delta Function Source一维单能离散纵标输运与伪求积和初生δ函数源
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IF1.3
delete2026-04-01
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PREAI
deleteGanapol, B. D.
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Development of Delayed Photon Group Parameters for Estimating Delayed Photoneutron Kinetics Parameters开发用于估计延迟光中子动力学参数的延迟光子组参数
deleteNuclear Science and Engineering
IF1.3
delete2026-04-01
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PREAI
deleteKim, Young In
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DNBR Box: Enhancing the Thermal-Hydraulic Design of the Pressurized Water Reactor Protection and Surveillance Systems Using Machine Learning and Uncertainty QuantificationDNBR Box：利用机器学习和不确定性量化方法提升压水堆保护与监测系统的热工水力设计
deleteNuclear Science and Engineering
IF1.3
delete2026-04-01
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PREAI
deleteSegond, M.; Lefebvre, L.; Mestrot, G.; Haouaneb, H.; Allory, M.
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High-Fidelity Multiphysics Modeling of the SNAP 10/A Space Reactor Using Cardinal基于Cardinal的高保真度SNAP 10/A空间反应堆多物理场建模
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IF1.3
delete2026-04-01
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deleteDalinger, Maximiliano; Merzari, Elia; Nguyen, Tri; Martineau, Richard
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Ameliorating Xe-Induced Power Oscillations in FHR Monte Carlo Depletion Simulations缓解FHR蒙特卡罗燃耗模拟中Xe诱导的功率振荡
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IF1.3
delete2026-04-01
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PREAI
deleteFaulkner, Jonathon; Petrovic, Bojan
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Application of Fuel Depletion Chain Simplification to Experiment Analysis in the Advanced Test Reactor先进试验反应堆中燃料燃耗链简化的实验分析应用
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IF1.3
delete2026-04-01
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PREAI
deleteLabossiere-Hickman, Travis J.; Calvin, Olin W.
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Nuclear Data Impact Assessment for the HTR-10 Pebble-Bed Reactor Using SCALE使用SCALE对HTR-10球床反应堆进行核数据影响评估
deleteNuclear Science and Engineering
IF1.3
delete2026-04-01
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PREAI
deleteElzohery, Rabab; Bostelmann, Friederike; Procop, Germina
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Addressing Geometrical Perturbations by Applying Generalized Polynomial Chaos to Virtual Density in Continuous-Energy Monte Carlo Power Iteration通过将广义多项式混沌应用于连续能量蒙特卡罗功率迭代中的虚拟密度来处理几何扰动
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IF1.3
delete2026-04-01
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PREAI
deleteBonnet, Theophile; Dubey, Anuj; Shwageraus, Eugene
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Study on the Automated Welding Process Parameters of the Maintenance Robot for Sheath of Electric Heating Tubes in Pressurizers of Nuclear Power Plant压水堆核电站加热器套管维护机器人的自动化焊接工艺参数研究
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IF1.3
delete2026-04-01
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deleteHan, Feng; Li, Chenghao; Guo, Liwei; Huang, Junfen; Xue, Long; Wang, Caimei
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Evaluation of Radiation Transport Through a Nuclear-Grade Sandwich Composite核级三明治复合材料的辐射输运评估
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IF1.3
delete2026-04-01
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deleteStewart, Ryan H.; Bays, Samuel E.; Ougouag, Abderrafi M.
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Barry and Symbolic Computing巴里与符号计算
deleteNuclear Science and Engineering
IF1.3
delete2026-03-01
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PREAI
deletePazsit, Imre
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