1. Wärmeübergang und Druckverlust an Reaktorbrennelementen in Form längsdurchströmter Rundstabbündel;Presser,1967
2. Gas-cooled reactor project semiannual progress report for period ending December 31, 1958;ORNL-2676 report of Oak Ridge National Laboratory, Oak Ridge, Tenn.,1959
3. Gas-cooled reactor project semiannual progress report for period ending June 30, 1959;ORNL-2767 report of Oak Ridge National Laboratory, Oak Ridge, Tenn.,1959
4. Improvement of fuel element heat transfer by use of roughened surfaces and the application to a 7-rod cluster;Draycott;ASME Int. Dev. in Heat Transfer,1961
5. Effect of wire wraps on pressure drop for axial turbulent flow through rod bundles;Waters;Report HW-65173 REV of Hanford Atomic Products Operation, Richland,1963