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1. The Need for Further Development of CAD/MCNP Interface Codes 原文获取 
[中文会议论文]   作者:X.George Xu   作者单位:Nuclear Engineering and Engineering Physics   会议名称:第十二届反应堆数值计算与粒子输运学术会议
INTRODUCTION MCNP and MCNPX are multi-particle transport simulation programs widely used in reactor
2. State-of-the-art 3-D radiation transport methods for fusion energy systems 原文获取 
[中文会议论文]   作者:P.P.H.Wilson;R.Feder;U.Fischer;M.Loughlin;L.Petrizzi;M.Youssef   作者单位:U.Wisconsin-Madison;Princeton Plasma Physics Laboratory;Forschungszentrum Karlsruhe;Euratom/UKAEA Fusion Assoc.;ENEA-Frascati.via Enrico Fermi 45;U.California-Los Angeles.420 Westwood Plaza   会议名称:第十二届反应堆数值计算与粒子输运学术会议
Recent advances in radiation transport simulation tools enable an increased fidelity and accuracy in
3. The fusion-driven hybrid system and its material selection 原文获取 
[中文会议论文]   会议名称:第十二届反应堆数值计算与粒子输运学术会议
The fusion-driven multi-functional hybrid reactor system (FDS) is proposed as a middle step toward t
4. A Fusion Neutron Source Driven Sub-Critical Nuclear Energy System:A Way for Early Application of Fusion Technology 原文获取 
[中文会议论文]   作者:吴宜灿   作者单位:Institute of Plasma Physics Chinese Academy Sciences   会议名称:第十二届反应堆数值计算与粒子输运学术会议
This paper proposes a sub-critical nuclear energy system driven by fusion neutron source,FDS,which c
5. Progress in fusion-driven hybrid system studies in China 原文获取 
[中文会议论文]   会议名称:第十二届反应堆数值计算与粒子输运学术会议
The fusion-driven hybrid reactor studies have been performed for nearly 20 years in China to seek fo
6. Design analysis of the China dual-functional lithium lead (DFLL) test blanket module in ITER 原文获取 
[中文会议论文]   作者:the FDS Team   作者单位:Institute of Plasma Physics   会议名称:第十二届反应堆数值计算与粒子输运学术会议
The dual-functional lithium lead-test blanket module (DFLL-TBM) system,which is designated to check
7. Development of Accurate/Advanced Radiotherapy Treatment Planning and Quality Assurance System(ARTS) 原文获取 
[中文会议论文]   作者:吴宜灿;宋钢;曹瑞芬;吴爱东;程梦云;汤正道;李贵;景佳;刘慧;李佳;兰海洋;孟耀;郑华庆;金雏凤;曾勤;郑善良;黄群英;吴李君;李国丽;林辉;陶声祥;施常备   作者单位:Institute of Plasma Physics Chinese Academy Science   会议名称:第十二届反应堆数值计算与粒子输运学术会议
A prototype of accurate/advanced radiotherapy treatment planning and quality assurance system (ARTS)
8. Progress in Compatibility Experiments on Lithium-Lead with Candidate Structural Materials for Fusion in China 原文获取 
[中文会议论文]   作者:FDS Team   作者单位:Institute of Plasma Physics   会议名称:第十二届反应堆数值计算与粒子输运学术会议
Liquid LiPb eutectic is one of the promising candidates of tritium breeder materials for fusion reac
9. Status and Strategy of Fusion Materials Development in China 原文获取 
[中文会议论文]   会议名称:第十二届反应堆数值计算与粒子输运学术会议
The liquid metal and solid ceramic pebble breeder blankets have become the most promising blankets f
10. Design and testing of the Fusion Virtual Assembly System FVAS 1.0 原文获取 
[中文会议论文]   作者:the FDS Team   作者单位:Institute of Plasma Physics   会议名称:第十二届反应堆数值计算与粒子输运学术会议
This paper presents the Fusion Virtual Assembly System FVAS 1.0 which makes possible engineering app
11. Fusion-Based Hydrogen Production Reactor and Its Material Selection 原文获取 
[中文会议论文]   作者:FDS Team   作者单位:Institute of Plasma Physics   会议名称:第十二届反应堆数值计算与粒子输运学术会议
The fusion-based hydrogen production reactor (named FDS-Ⅲ),one of the series of fusion system design
12. Design status and development strategy of China liquid lithium-lead blankets and related material technology 原文获取 
[中文会议论文]   作者:FDS Team   作者单位:Institute of Plasma Physics   会议名称:第十二届反应堆数值计算与粒子输运学术会议
A series of fusion reactors (named FDS series) have been designed and assessed in China,with four ty
13. A feasibility study of sub-criticality monitoring for ADS via static flux distribution measurement 原文获取 
[中文会议论文]   会议名称:第十二届反应堆数值计算与粒子输运学术会议
Sub-criticality is a critical safety parameter for ADS,how to measure or monitor the sub-criticality
14. Conceptual design activities of FDS series fusion power plants in China 原文获取 
[中文会议论文]   作者:FDS Team   作者单位:Institute of Plasma Physics   会议名称:第十二届反应堆数值计算与粒子输运学术会议
A series of fusion power plants (named FDS series) have been designed and assessed for the examinati
15. Feasibility of embedding nodal homogenization in next generation methods for 3D pin-by-pin core simulation 原文获取 
[中文会议论文]   会议名称:第十二届反应堆数值计算与粒子输运学术会议
The current generation methods for LWR core design and analysis based on single assembly homogenizat
16. Benchmarking of MCAM 4.0 with the ITER 3D model 原文获取 
[中文会议论文]   会议名称:第十二届反应堆数值计算与粒子输运学术会议
Monte Carlo particle transport simulations are widely employed in fields such as nuclear engineering
17. Conceptual design of the fusion-driven subcritical system FDS-I 原文获取 
[中文会议论文]   作者:FDS Team   作者单位:Institute of Plasma Physics   会议名称:第十二届反应堆数值计算与粒子输运学术会议
The fusion-driven subcritical system (named FDS-I) was previously proposed as an intermediate step t
18. Conceptual Design of China Fusion Power Plant FDS-Ⅱ 原文获取 
[中文会议论文]   作者:FDS Team   作者单位:Institute of Plasma Physics   会议名称:第十二届反应堆数值计算与粒子输运学术会议
As one of the series of fusion system design concepts developed in China,the fusion power plant FDS-
19. Progress in development of China Low Activation Martensitic steel for fusion application 原文获取 
[中文会议论文]   会议名称:第十二届反应堆数值计算与粒子输运学术会议
A series of R&D activities on the structural material China Low Activation Martensitic steel (CLAM)
20. Benchmarking of SNAM with the ITER 3D model 原文获取 
[中文会议论文]   作者:FDS Team   作者单位:Institute of Plasma Physics   会议名称:第十二届反应堆数值计算与粒子输运学术会议
The discrete ordinates particle transport codes (SN codes) are widely used in reactor design,radiati
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