首页> 美国政府科技报告 >Proceedings of the ANS/ASME/NRC International Topical Meeting on Nuclear Reactor Thermal-Hydraulics Held at Saratoga Springs, New York on October 5-8, 1980. Volume 3. LMFBR and HTGR Advanced Reactor Concepts and Analysis Methods
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Proceedings of the ANS/ASME/NRC International Topical Meeting on Nuclear Reactor Thermal-Hydraulics Held at Saratoga Springs, New York on October 5-8, 1980. Volume 3. LMFBR and HTGR Advanced Reactor Concepts and Analysis Methods

机译:aNs / asmE / NRC国际核反应堆热工水力专题会议论文集于1980年10月5日至8日在纽约萨拉托加斯普林斯举行。第3卷.LmFBR和HTGR先进反应堆概念和分析方法

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Technical papers and invited lectures presented at the 1980 International Topical Meeting on Nuclear Reactor Thermal-Hydraulics are presented. The thermal-hydraulics of pressurized water reactors, boiling water reactors, liquid metal cooled fast breeder reactors, and high temperature gas cooled reactors including pebble bed reactors are covered. There are sessions on reactor blowdown and refill, reactor containment technology and reactor-plant components. Basic mechanisms of two-phase flow are presented in sessions on critical flow, instrumentation, critical heat flux and reflood, entrainment and droplet deposition. There is also a special session on mathematical methods.

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