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ORCA: A Tool for Radiological Consequences for Accidental Releases ORCA:意外释放辐射后果工具
IF 1.2 3区 工程技术 Q3 NUCLEAR SCIENCE & TECHNOLOGY Pub Date : 2024-03-04 DOI: 10.1080/00295639.2024.2315905
P. Maka, E. Van Heerden, M. Rezaee
Evaluating atmospheric dispersion and radiological doses in the vicinity of buildings is required for small modular reactors (SMRs) because of the reduced size of their exclusion area boundary. The...
由于小型模块化反应堆(SMR)的禁区边界尺寸较小,因此需要对建筑物附近的大气扩散和辐射剂量进行评估。这...
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引用次数: 0
New RMC Energy Deposition Treatment and its Application in Multi-Physics Simulation 新型 RMC 能量沉积处理及其在多物理场仿真中的应用
IF 1.2 3区 工程技术 Q3 NUCLEAR SCIENCE & TECHNOLOGY Pub Date : 2024-03-01 DOI: 10.1080/00295639.2024.2316955
Hao Luo, Kaiwen Li, Nan An, Shanfang Huang, Kan Wang
Accurate estimation of energy deposition is important in core physics and severe accident analyses for design optimizations. In this study, a new energy deposition treatment is implemented in the R...
精确估算能量沉积对于核心物理和严重事故分析中的设计优化非常重要。在这项研究中,R...
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引用次数: 0
On the Use of the Jacobian-Free Newton Krylov Method to Generate One-Group Discontinuity and Super Homogenization Factors for Full-Core Neutron Diffusion Simulations 论使用无雅各布牛顿克雷洛夫方法为全中子扩散模拟生成单组不连续和超均质化因子
IF 1.2 3区 工程技术 Q3 NUCLEAR SCIENCE & TECHNOLOGY Pub Date : 2024-03-01 DOI: 10.1080/00295639.2024.2303548
Bailey Painter, Dan Kotlyar
Coupled Monte Carlo (MC) and thermal-hydraulic analysis is valuable as a design or reference tool but can be slow, especially when implemented in a Picard iteration. Previous work has developed a n...
蒙特卡洛(MC)和热流体力学耦合分析作为一种设计或参考工具非常有价值,但速度较慢,尤其是在皮卡迭代中实施时。以前的工作已经开发了一种新的方法,它可以通过...
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引用次数: 0
Examining the Contributions of Various Source Layers and Transport Pathways to Dose Rates Exterior to a Low- and Intermediate-Level Radioactive Waste Storage Facility Using ADVANTG/MCNP 利用 ADVANTG/MCNP 研究各种源层和传输途径对中低放射性废物贮存设施外部剂量率的影响
IF 1.2 3区 工程技术 Q3 NUCLEAR SCIENCE & TECHNOLOGY Pub Date : 2024-02-29 DOI: 10.1080/00295639.2024.2318834
Bo-Lun Lai, Szu-Li Chang, Rong-Jiun Sheu
An in-depth shielding analysis of a large indoor facility designed for storing low- and intermediate-level radioactive waste generated from nuclear power plant decommissioning was performed. The fa...
我们对一个大型室内设施进行了深入的屏蔽分析,该设施是为储存核电站退役产生的中低放射性废物而设计的。分析结果表明...
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引用次数: 0
A Review of Neutron–Gamma-Ray Discrimination Methods Using Organic Scintillators 使用有机闪烁体的中子-伽马射线辨别方法综述
IF 1.2 3区 工程技术 Q3 NUCLEAR SCIENCE & TECHNOLOGY Pub Date : 2024-02-29 DOI: 10.1080/00295639.2024.2316946
Imane Ahnouz, Hanan Arahmane, Rajaa Sebihi
Neutron detection is increasingly vital in various fields such as homeland security, medical sciences, and high-energy physics. However, interference from accompanying gamma rays poses a critical c...
中子探测在国土安全、医学科学和高能物理等各个领域越来越重要。然而,伴随而来的伽马射线的干扰是一个关键问题。
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引用次数: 0
Analytic Error Analysis of the Partial Derivatives Cross-Section Model—II: Numerical Results 部分衍生截面模型的误差分析-II:数值结果
IF 1.2 3区 工程技术 Q3 NUCLEAR SCIENCE & TECHNOLOGY Pub Date : 2024-02-29 DOI: 10.1080/00295639.2024.2303544
Thomas Folk, Siddhartha Srivastava, Dean Price, Krishna Garikipati, Brendan Kochunas
Accurately predicting errors incurred in a cross-section model for two-step reactor analysis enables the development of optimal case matrices and more efficient cross-section models. In a companion...
准确预测用于两步反应器分析的横截面模型所产生的误差,有助于开发最佳情况矩阵和更高效的横截面模型。在配套的...
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引用次数: 0
The Effect of Branchless Collisions and Population Control on Correlations in Monte Carlo Power Iteration 无分支碰撞和种群控制对蒙特卡罗幂迭代中相关性的影响
IF 1.2 3区 工程技术 Q3 NUCLEAR SCIENCE & TECHNOLOGY Pub Date : 2024-02-28 DOI: 10.1080/00295639.2023.2288328
Theophile Bonnet, Hunter Belanger, Davide Mancusi, Andrea Zoia
The investigation of correlations in Monte Carlo power iteration has long been dominated by the question of generational correlations and their effects on the estimation of statistical uncertaintie...
长期以来,对蒙特卡罗幂迭代中相关性的研究主要集中在代际相关性问题及其对统计不确定性估计的影响上。
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引用次数: 0
Pre-Experimental Assessment of Uranyl Nitrate Solution Irradiation in Kartini Reactor Facilities 硝酸铀溶液辐照卡蒂尼反应堆设施的实验前评估
IF 1.2 3区 工程技术 Q3 NUCLEAR SCIENCE & TECHNOLOGY Pub Date : 2024-02-28 DOI: 10.1080/00295639.2024.2306103
Feryantama Putra, Syarip, Sihana
Medical radioisotope production using neutron irradiation via fission reaction requires a sufficient neutron source. The Kartini reactor has been proposed and studied to become a neutron source for...
利用中子辐照通过裂变反应生产医用放射性同位素需要足够的中子源。Kartini 反应堆已被提议并研究成为用于医用放射性同位素生产的中子源。
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引用次数: 0
Resonance Calculation of FCM Fuel Based on the Global-Local Method 基于全局-局部法的 FCM 燃料共振计算
IF 1.2 3区 工程技术 Q3 NUCLEAR SCIENCE & TECHNOLOGY Pub Date : 2024-02-27 DOI: 10.1080/00295639.2023.2296239
Siyu Yi, Zhouyu Liu, Kunpeng Wang, Wei Shen, Tiejun Zu, Liangzhi Cao, Hongchun Wu
Fully ceramic microencapsulated fuels is a promising potential fuel for pressurized water reactors because of its inherent safety, but double heterogeneity (DH) brings challenges to the neutronic c...
全陶瓷微囊燃料因其固有的安全性而成为压水反应堆的一种前景广阔的潜在燃料,但双重异质性(DH)给中子反应堆带来了挑战。
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引用次数: 0
Recovering From Structural Instability in Nuclear Power Design Optimization 从核电设计优化中的结构不稳定性中恢复过来
IF 1.2 3区 工程技术 Q3 NUCLEAR SCIENCE & TECHNOLOGY Pub Date : 2024-02-27 DOI: 10.1080/00295639.2024.2306707
Dominic J. Brennan, Geoffrey T. Parks
The Scientific Method—parsing a problem into isolated subproblems—is often necessarily employed in optimization efforts to reduce large and complex problems into more tractable parcels. However, ad...
科学方法--将问题解析为孤立的子问题--经常被用于优化工作中,以将复杂的大问题简化为更容易解决的问题。然而,科学方法并不能解决所有问题。
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引用次数: 0
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Nuclear Science and Engineering
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