| 核聚变实验装置HT-7U一维及二维辐射防护设计研究 |
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| 引用本文： | 黄群英,陈朝斌,吴宜灿. 核聚变实验装置HT-7U一维及二维辐射防护设计研究[J]. 核科学与工程, 2001, 21(1): 79-85 |
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| 作者姓名： | 黄群英 陈朝斌 吴宜灿 |
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| 作者单位： | 中国科学院等离子体所, |
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| 摘 要： | 主要介绍一维、二维中子输运程序ANISN，DOT3.5在核聚变实验装置HT-7U辐射屏蔽物理设计中的应用。计算和分析了该装置实验大厅内外中子注量/能谱、γ注量/能谱、中子剂量率、γ剂量率的空间分布，对屏蔽材料的选取及屏蔽层厚度进行了优化设计，为HT-7U装置的辐射屏蔽物理设计提供了建议性意见及理论依据。
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| 关 键 词： | HT-7U装置； 核聚变； 辐射屏蔽； 剂量率 |
| 修稿时间： | 2000-03-06 |
Shielding Design of HT-7U Nuclear Fusion Experimental Device |
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| HUANG Qunying,CHEN Chaobin,WU Yican. Shielding Design of HT-7U Nuclear Fusion Experimental Device[J]. Chinese Journal of Nuclear Science and Engineering, 2001, 21(1): 79-85 |
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| Authors: | HUANG Qunying CHEN Chaobin WU Yican |
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| Abstract: | Calculation and analysis on radiation field around HT 7U tokamak device under the condition of D D discharge have been performed with the one dimensional and two dimensional discrete ordinates transport calculation codes ANISN and DOT3.5.The effects of concrete wall and borated water with different thicknesses of the shield have been analyzed and optimized.The neutron spectrum,induced photon spectrum and dose rates equivalent are presented as a reference to the radiation protection design of HT 7U device. |
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| Keywords: | HT-7U device nuclear fusion radiation shield dose rate |
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