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Journal of Fusion Energy最新文献

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Retraction Note: Effects of Hot Limiter Biasing on Tokamak Runaway Discharges 撤回说明：热限制器偏置对托卡马克失控放电的影响
IF 1.9 4区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Journal of Fusion Energy
Pub Date : 2024-10-09 DOI: 10.1007/s10894-024-00464-1
A. Salar Elahi, M. Ghoranneviss, M. R. Ghanbari
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引用次数: 0
Retraction Note: Feedback System Design for Plasma Horizontal Position Control in IR-T1 Tokamak 撤回说明：IR-T1 托卡马克中等离子体水平位置控制的反馈系统设计
IF 1.9 4区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Journal of Fusion Energy
Pub Date : 2024-10-09 DOI: 10.1007/s10894-024-00463-2
A. Naghidokht, R. Khodabakhsh, M. Ghoranneviss, A. Salar Elahi
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引用次数: 0
Artificial Neural Network-Based Tomography Reconstruction of Plasma Radiation Distribution at GOLEM Tokamak 基于人工神经网络的 GOLEM 托卡马克等离子体辐射分布断层扫描重建技术
IF 1.9 4区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Journal of Fusion Energy
Pub Date : 2024-09-04 DOI: 10.1007/s10894-024-00458-z
S. Abbasi, J. Mlynar, J. Chlum, O. Ficker, V. Svoboda, J. Brotankova

The paper presents an artificial neural network-based model for tomography reconstruction of visible plasma radiation distribution at the GOLEM tokamak. The model was trained using a dataset from emissivity phantoms and associated synthetic measurements from a poloidal cross-section of the GOLEM tokamak. The model validation was performed on the prediction of various unseen phantom samples with shapes similar to those in the training dataset. The backfit of line-integrated measurements indicates the considerable potential of the proposed model for reconstructing the position, size, shape and intensity of the radiation function of one cross section. Additionally, the neural network-based model offers a significantly shorter prediction time compared to traditional tomography methods, providing a substantial advantage.

本文介绍了一个基于人工神经网络的模型，用于对 GOLEM 托卡马克可见等离子体辐射分布进行断层扫描重建。该模型是利用来自发射率模型的数据集和来自 GOLEM 托卡马克极坐标截面的相关合成测量数据进行训练的。模型验证是通过预测与训练数据集形状相似的各种未见模型样本进行的。线积分测量的反拟合结果表明，所提出的模型在重建一个截面的辐射函数的位置、大小、形状和强度方面具有相当大的潜力。此外，与传统的层析成像方法相比，基于神经网络的模型可大大缩短预测时间，具有很大的优势。
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引用次数: 0
Retraction Note: Comparison between Discrete Magnetic Coils and Multipole Coils for Measurement of Plasma Displacement in IR-T1 Tokamak 撤回说明：用于测量 IR-T1 托卡马克中等离子体位移的分立磁线圈与多极线圈之间的比较
IF 1.9 4区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Journal of Fusion Energy
Pub Date : 2024-08-29 DOI: 10.1007/s10894-024-00459-y
Ahmad Rahimirad, M. Emami, M. Ghoranneviss, A. Salar Elahi
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引用次数: 0
Comparative Study on the Reduction of Tritium Breeding Ratio Caused by Inventory Changes of a Solid-State Tritium Breeding Blanket in a Fusion Demonstration Reactor Using MCNP and FISPACT-II 利用 MCNP 和 FISPACT-II 对聚变示范反应堆中固态氚孕育毯库存变化导致的氚孕育率降低进行比较研究
IF 1.9 4区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Journal of Fusion Energy
Pub Date : 2024-08-08 DOI: 10.1007/s10894-024-00455-2
Byung Chul Kim

The self-sufficient supply of tritium in the deuterium-tritium nuclear fusion demonstration reactor (DEMO) is a fundamental design requirement. But, it is hindered by depletion of tritium breeding materials resulting in reduction of tritium breeding ratio (TBR) less than the initial design value especially in the solid-state tritium breeding blanket (TBB) of the DEMO. Unlike the liquid tritium breeding blanket of DEMO, compensation measures of the depleted breeding material in the solid-state TBB will be its substitution depending on the reduction rate of TBR. To estimate the replacement period of the solid-state TBB, it is required to estimate the reduction rate of TBR according to the operation conditions of the DEMO and the physical configuration of a solid-state TBB. In this study, the representative simulation codes, MCNP and FISPACT-II, are used for assessment of the reduction rate of TBR with the benchmarking model which is modified from the one poloidal segment of the TBB in the Korean-DEMO. After 3 full power-year operations with the neutron irradiation with the benchmarking model, the TBR simulated by MCNP is reduced to 96.84% of the initially calculated TBR, but the TBR calculated by FISPACT-II is reduced to 90.57% of the initially calculated TBR.

氘氚核聚变示范反应堆（DEMO）中氚的自给自足是一项基本设计要求。但是，由于氚孕育材料的耗竭，导致氚孕育率（TBR）低于初始设计值，特别是在 DEMO 的固态氚孕育毯（TBB）中，氚孕育率的降低阻碍了氚的自给自足。与 DEMO 的液态氚孕育毯不同，固态氚孕育毯中贫化孕育材料的补偿措施是根据氚孕育率的降低率进行替代。为了估算固态 TBB 的替换周期，需要根据 DEMO 的运行条件和固态 TBB 的物理结构估算 TBR 的减少率。本研究使用 MCNP 和 FISPACT-II 这两个具有代表性的仿真代码来评估 TBR 的减少率。在基准模型的中子辐照下，经过 3 个全功率年运行后，MCNP 模拟的 TBR 降至最初计算 TBR 的 96.84%，而 FISPACT-II 计算的 TBR 降至最初计算 TBR 的 90.57%。
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引用次数: 0
Retraction Note: Relations between the Plasma Diamagnetic Effect and Plasma Basic Parameters in IR-T1 Tokamak 撤稿说明：IR-T1 托卡马克中等离子体二磁效应与等离子体基本参数的关系
IF 1.9 4区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Journal of Fusion Energy
Pub Date : 2024-08-06 DOI: 10.1007/s10894-024-00456-1
Ahmad Salar Elahi, Mahmood Ghoranneviss
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引用次数: 0
Retraction Note: Measurement of Plasma Poloidal Beta in Presence of Resonant Helical Field in IR-T1 Tokamak 撤回说明：IR-T1 托卡马克中存在共振螺旋场时的等离子体极坐标β测量结果
IF 1.9 4区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Journal of Fusion Energy
Pub Date : 2024-08-03 DOI: 10.1007/s10894-024-00457-0
Ahmad Salar Elahi, Mahmood Ghoranneviss
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引用次数: 0
Retraction Note: Study of Effects of the Effective Edge Safety Factor on the Energy Confinement Time in IR-T1 Tokamak 撤回声明：IR-T1 托卡马克中有效边缘安全系数对能量囚禁时间影响的研究
IF 1.9 4区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Journal of Fusion Energy
Pub Date : 2024-07-25 DOI: 10.1007/s10894-024-00454-3
A. Salar Elahi, M. Ghoranneviss
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引用次数: 0
Retraction Note: Plasma Magnetic Fluctuations Measurement on the Outer Surface of IR-T1 Tokamak 撤回说明：IR-T1 托卡马克外表面等离子体磁波动测量
IF 1.9 4区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Journal of Fusion Energy
Pub Date : 2024-07-23 DOI: 10.1007/s10894-024-00452-5
A. Salar Elahi, M. Ghoranneviss
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引用次数: 0
Retraction Note: Experimental Study of Effects of the Internal Inductance on the Energy Confinement Time in IR-T1 Tokamak 撤回声明：IR-T1 托卡马克中内部电感对能量囚禁时间影响的实验研究
IF 1.9 4区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Journal of Fusion Energy
Pub Date : 2024-07-20 DOI: 10.1007/s10894-024-00453-4
A. Salar Elahi, M. Ghoranneviss
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引用次数: 0
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