Equations of motion for two-phase flow in a pin bundle of a nuclear reactor

Author:

Chawla T.C.,Ishii M.

Publisher

Elsevier BV

Subject

Fluid Flow and Transfer Processes,Mechanical Engineering,Condensed Matter Physics

Reference17 articles.

1. A mathematical model for transient subchannel analysis of rod-bundle nuclear fuel elements;Rowe;J. Heat Transfer,1973

2. Cobra-II, a digital computer program for thermal hydraulic subchannel analysis of rod bundle nuclear fuel elements;Rowe;Battelle Pacific Northwest Laboratory Report BNWL-1229,1970

3. HAMBO, a computer programme for the subchannel analysis of the hydraulic and burnout characteristics of rod clusters;Bowring;General description, United Kingdom Atomic Energy Authority Report AEEW-R524,1967

4. SASS Code 1, Subchannel analysis for the steady state;Peirre;Atomic Energy of Canada Limited Report AECL-APPE-41,1966

5. Crossflow mixing between parallel flow channels during boiling;Rowe;Measurement of flow and enthalpy in two parallel channels, Battelle Pacific Northwest Laboratory Report BNWL-371. part 2,1967

Cited by 7 articles. 订阅此论文施引文献 订阅此论文施引文献,注册后可以免费订阅5篇论文的施引文献,订阅后可以查看论文全部施引文献

1. Mesh generation and numerical simulation of fluid entering a large tube bundle;Journal of Thermophysics and Heat Transfer;1996-01

2. Blocked Flow Subchannel Simulation Comparison With Single-Phase Flow Data;Journal of Fluids Engineering;1992-06-01

3. Two-fluid model and hydrodynamic constitutive relations;Nuclear Engineering and Design;1984-10

4. A Drift-Flux Model Flow-Regime Map of Two-Phase Flows for Thermal-Hydraulic Calculations;Nuclear Science and Engineering;1983-06

5. Two-Phase Flow Models and their Limitations;Advances in Two-Phase Flow and Heat Transfer;1983

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