摘要: The primary function of beryllium in a fusion reactor blanket is neutron multiplication to enhance tritium breeding. However, because heat, tritium and helium will be generated in and/or transported through beryllium and because t... 展开
作者 | Billone, M. C. | ||
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原报告号 | DE95 004637 | 总页数 | 32 |
主办者 | Department of Energy, Washington, DC. | ||
报告分类号 | [77A - Thermonuclear Fusion Devices, 71N - Nonferrous Metals & Alloys] | ||
报告类别/文献类型 | DE / NTIS科技报告 | ||
关键词 | Beryllium Breeding Blankets Breeding Ratio Design Information Systems Interstitial Helium Generation Materials Mechanical Properties Performance Physical Properties Physical Radiation Effects Tritium Tritium Recovery Thermonuclear reactors |