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