References
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- Nucl. Eng. and Des. v.35 A Porous Body Model for Predicting Assemblies in Combined Forced and Free Convection E.U. Khan;W.M. Rohsenow;A.A.Sonein;N.E. Todreas
- COO-2245-20TR, Massachusetts Institutes of Technology, Cambridge Prediction of Coolant Temperature Field in a Breeder Reactor Including Interassembly Heat Transfer B. Chen;N.E. Todreas
- PNL-3379, Pacific Northwest Laboratory SUPERENERGY-2 : A Multiassembly, Steady-State Computer Code for LMFBR Core Thermal-Hydraulic Analysis K.L. Basehore;N.E. Todreas
- Proc. 7th International Meeting on Nuclear Reactor Thermal Hydraulics, NUREG/CP-0142, Saratoga Springs, New York, September 10-15, 1995 v.3 Assessment of the SE2-ANL Code Using EBR-II Temperature Measurements W.S. Yang;A.M. Yacout
- Fast Breeder Reactors A.E. Walter;A.B. Reynolds
- Nucl. Eng. and Des. v.22 Turbulent Flow Pressure Drop Model for Fuel Rod Assemblies Utilizing a Helical Wire-Wrap Spacer System E.H. Novenstern
- COO-2245-56TR, Massachusetts Institute of Technology Flow Split Model for LMFBR Wire Wrapped Assemblies C. Chiu;W.M. Rohsenow;N.E. Todreas
- Nucl. Eng. and Des. v.92 Hydrodynamic Models and Correlations for Bare and Wire-Wrapped Hexagonal Rod Bundles-Bundle Friction Factors, Subchannel Friction Factors and Mixing Parameters S.K. Cheng;N.E. Todreas
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- Computational Methods in Engineering and Science S. Nakamura
- Argonne National Laboratory, personal communication R.B. Vilim