聚变驱动次临界堆概念设计研究
Conceptual design study on the fusion-driven sub-critical system
查看参考文献17篇
文摘
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在深入分析相关领域研究发展状况的基础上,提出一个可实现核废料嬗变、可裂变重金属核燃料和氚核燃料增殖、产能等多种功能的次临界反应堆概念.概念有托卡马克实验装置参数适量外推的等离子体物理和技术水平的聚变堆芯、高压He气/液态LiPb双冷却系统嬗变包层.介绍了系统基本概况和参考结构形式,阐述了系统聚变等离子体物理学、包层中子物理学和包层热工水力学设计的基本原则和主要工程约束限制条件,指出系统相关的安全和潜在环境影响问题,给出典型的参考设计参数. |
其他语种文摘
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A conceptual design of the Fusion-Driven Sub-critical System (FDS) is presented, which consists of the fusion neutron driver with feasible plasma parameters and the multifunctional blanket (DWTB) used to transmute long-lived nuclear wastes, to breed nuclear fuels such as tritium and plutonium and to generate energy. The overview of the current status and main reference parameters of the FDS design is given including the design principles and engineering constraints of core plasma physics, blanket neutronics, blanket thermal-hydraulics and safety & environmental impact etc. |
来源
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核科学与工程
,2004,24(1):72-80 【核心库】
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关键词
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聚变
;
次临界堆
;
概念设计
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地址
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中国科学院等离子体物理研究所, 安徽, 合肥, 230031
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语种
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中文 |
文献类型
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研究性论文 |
ISSN
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0258-0918 |
学科
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原子能技术 |
基金
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国家自然科学基金资助项目
;
中国科学院知识创新工程项目
;
"百人计划"项目资助
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文献收藏号
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CSCD:1913584
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参考文献 共
17
共1页
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1.
吴宜灿. 聚变中子源驱动的次临界清洁核能系统──聚变能技术的早期应用途径.
核技术,2000,23(8):519-525
|
被引
10
次
|
|
|
|
2.
Wu Y C. The Fusion-Driven Hybrid System and its Material Selection[J].
Journal of Nuclear Materials,2002,307/311:1629-1636
|
被引
36
次
|
|
|
|
3.
WU Yican. Progress in Fusion-Driven Hybrid System Studies in China[J].
Fusion Eng. Design,2002,63/64:73-78
|
被引
19
次
|
|
|
|
4.
Wu Y C. Neutronics Analysis of Dual-cooled Waste Transmutation Blanket for the FDS[J].
Fusion Eng. Design,2002,63/64:133-138
|
被引
7
次
|
|
|
|
5.
Ke Y. Thermal-hydraulic Analysis of the Dual-cooled Waste Transmutation Blanket for the FDS[J].
Fusion Eng. Design,2002,61/62:455-459
|
被引
3
次
|
|
|
|
6.
Wang Hong-yan. Preliminary Analysis of Liquid Metal MHD Pressure Drop in the Blanket for the FDS[J].
Plasma Physics and Technology,2002,4(5)
|
被引
2
次
|
|
|
|
7.
Zheng Shan-liang. Neutronics Optimization of LiPb-He Dual-cooled Fuel Breeding Blanket for the FDS[J].
Plasma Physics and Technology,2002,4(4)
|
被引
3
次
|
|
|
|
8.
Zheng Shan-liang. Neutronics Optimization of Tritium Breeding Blanket for the FDS[J].
Plasma Physics and Technology,2002,4(2)
|
被引
3
次
|
|
|
|
9.
Wang Weihua. Analysis on Stress Field of the Dual-cooled Waste Transmutation Blanket for the FDS[J].
Fusion Engineering and Design,2003,69:297-301
|
被引
1
次
|
|
|
|
10.
Ke Y. MHD Simulation of the Liquid Metal/Helium Gas Dual-cooled Waste Transmutation Blanket for FDS[J].
Fusion Engineering and Design,2003,69:431-435
|
被引
2
次
|
|
|
|
11.
ITER. Study of Options for the Reduced Technical Objectives/Reduced Cost (RTO/RC) ITER.
Study of Options for the Reduced Technical Objectives/Reduced Cost (RTO/RC) ITER. ITER-FEAT Outline Design Report,2000
|
被引
1
次
|
|
|
|
12.
Wan Yuanxi. Overview of steady state operation of HT-7 and present status of the HT-7U project[J].
Nuclear Fusion,40(6)
|
被引
1
次
|
|
|
|
13.
Lee G S. An advanced steady state superconducting tokamak experiment[J].
Nuclear Fusion,40(3Y)
|
被引
1
次
|
|
|
|
14.
储德林. 聚变驱动次临界堆聚变堆芯物理设计与分析[J].
核科学与工程,2004,24(1)
|
被引
1
次
|
|
|
|
15.
黄群英. 聚变堆低活化马氏体钢发展综述[J].
核科学与工程,2004,24(1)
|
被引
6
次
|
|
|
|
16.
柯严. 聚变驱动次临界堆双冷嬗变包层结构设计与分析[J].
核科学与工程,2004,24(1)
|
被引
2
次
|
|
|
|
17.
汪卫华. 聚变驱动次临界堆双冷嬗变包层热工水力学参数设计与分析[J].
核科学与工程,2004,24(1)
|
被引
3
次
|
|
|
|
|