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Theoretical Study of Transient Sodium Boiling in Reactor Coolant Channels Utilizing a Compressible Flow Model.

机译：利用可压缩流动模型研究反应堆冷却剂通道中瞬态沸腾的理论研究。

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For abstract,see NSA 26 01,number 00254.

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作者
siegmann,eric r.;
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年度 1979
页码 1-167
总页数 167
原文格式 PDF
正文语种 eng
中图分类工业技术;
关键词
computer programs; reactors/liquid metal-cooled; sodiumanl-7842;

机译：计算机程序;反应堆/液态金属冷却; sodiumanl-7842;

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专利

1. Cold neutron tomography of annular coolant flow in a double subchannel model of a boiling water reactor [J] . J.L. Kickhofel, R. Zboray, M. Damsohn, Nuclear Instruments & Methods in Physics Research . 2011,第1期

机译：沸水反应堆双子通道模型中环形冷却剂流动的冷中子层析成像
2. Experimental Study on Helium Natural Convection Heat Transfer for Two Coolant Flow Channels Within Prismatic Very High Temperature Reactor [J] . Ibrahim A. Said, Mahmoud M. Taha, S. Usman, Transactions of the American nuclear society . 2017,第期

机译：棱柱形极高温反应堆内两个冷却剂流动通道氦自然对流换热的实验研究
3. Measurement and theoretical analysis of transient liquid film during micro-channel flow boiling [J] . Guo Chaohong, Tao Jie, Jiang Yuyan, International Journal of Multiphase Flow . 2020,第1期

机译：微通道流沸腾过程中瞬态膜的测量与理论分析
4. Identification and Ranking of Phenomena Leading to Peak Cladding Temperatures in Boiling Water Reactors during Large Break Loss Of Coolant Accident Transients [C] . Ruwan K. Ratnayake, S. Ergun, L. E. Hochreiter, 10th International Conference on Nuclear Engineering, Vol.3, Apr 14-18, 2002, Arlington, Virginia . 2002

机译：冷却剂事故瞬态的大破坏损失期间导致沸腾反应堆熔覆温度达到峰值的现象的识别和排序
5. THEORETICAL STUDY OF TRANSIENT SODIUM BOILING IN REACTOR COOLANT CHANNELSUTILIZING A COMPRESSIBLE FLOW MODEL [D] . SIEGMANN, ERIC RAYMOND. 1971

机译：反应器冷却剂通道旋转钠沸腾的理论研究，可压缩流动模型
6. Effects of the external pH on Ca channels: experimental studies and theoretical considerations using a two-site two-ion model. [O] . T Iijima, S Ciani, S Hagiwara 1986

机译：外部pH值对Ca通道的影响：使用两点两离子模型的实验研究和理论考虑。
7. A Thermo-Hydrodynamic Model for the Theoretical Study of the Boiling and Ejection of the Coolant from a Reactor Channel Due to a Direct Contact with Hot Molten Fuel. EUR 4292. [O] . Randles J. 1971

机译：一种热流体动力学模型，用于理论研究由于直接接触热熔燃料而从反应器通道中冷却液的沸腾和喷射。 4292欧元。
8. AN ANALYTIC STUDY OF THE TRANSIENT BOILING OF SODIUM IN REACTOR COOLANT CHANNELS, [R] . macfarlane,donald r. 1967

机译：反应器冷却通道中钠瞬态沸腾的分析研究，

Theoretical Study of Transient Sodium Boiling in Reactor Coolant Channels Utilizing a Compressible Flow Model.

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