References
- F. W. AISCH, H. P. FUCHS, and R. HOLZER, “Hüllrohrbeanspruchung von Brennstäben in Druckwasserreaktoren,” Proc. Dt. Reaktortagung, Bonn, DATF, p. 554 (1970).
- H. M. FERRARI, “Pressurization Improves Fuel Rod Reliability,” Nucl. Eng. Int., p. 623 (1970).
- R. HOLZER, D. KNÖDLER, and H. STEHLE, “Pellet Clad Interaction Testing and Evaluation: A KWU Review,” Proc. Topl. Mtg. Water Reactor Fuel Performance, St. Charles, p. 207 (1977).
- F. GARZAROLLI et al., “Observations and Hypothesis on Pellet-Clad Interaction Failures,” Kerntechnik, 20, 27 (1978).
- F. WUNDERLICH and F. GARZAROLLI, “The Influence of Thermal Feedback on the Ramping Behaviour of LWR Fuel Rods,” Proc. Dt. Reaktortagung, Hannover, DATF, p. 525 (1978).
- G. ROBERTS et al., “An Investigation of the Cladding Collapse Phenomenon in Beznau I PWR,” Proc. Topl. Mtg. Water Reactor Fuel Performance, St. Charles, p. 92 (1977).
- N. J. HOFF, W. E. JAHSMAN, and W. NACHBAR, “A Study of Creep Collapse of a Long Circular Cylindrical Shell Under Uniform External Pressure,” J. Aerospace Sci., 26, 663 (1959).
- J. P. ELLINGTON, “Creep Collapse of Tubes Under External Pressure,” DEG Report 162 (R) (1960).
- D. KNÖDLER and H. STEHLE, “KWU Fuel Manufacturing and Operational Experience,” NUCLEX-75, Technical Mtg. No. 6, Basel (1975).
- F. GARZAROLLI et al., “KWU Review on Corrosion and Dimensional Behaviour of Zircaloy Under Water Reactor Conditions,” Seventh Int. Symp. Zirconium in the Nuclear Industry, Stratford-on-Avon, U.K. (1978).
- H. ASSMANN and H. STEHLE, “Verdichtungseffekte in gesintertem UO2,” Proc. Dt. Reaktortagung, Karlsruhe, DATF, p. 409 (1973).
- H. STEHLE and H. ASSMANN, “The Dependence of In-Reactor UO2 Densification on Temperature and Micro-structure,” J. Nucl. Mater., 52, 303 (1974).
- H. ASSMANN and H. STEHLE, “Densification Modelling of UO2,” ATW, 21, 239 (1976).
- H. ASSMANN and H. STEHLE, “Thermal and In-Reactor Densification of UO2: Mechanism and Experimental Results,” Nucl. Eng. Des., 48, 49 (1978).
- M. R. WAGNER, H. FINNEMANN, K. KOEBKE, and H. J. WINTER, “Validation of the Nodal Expansion Method and the Depletion Programm MEDIUM-2 by Benchmark Calculations and Direct Comparison with Experiment,” Atomkernenergie, 30, 129 (1977).
- R. EBERLE, F. WUNDERLICH, and I. DISTLER, “The KWU Fuel Rod Code CARO,” IAEA Specialists' Mtg. Fuel Element Performance Computer Modelling, Blackpool, U.K. (1978).
- F. DEPISCH and H. GURAN, “Rechenprogramm BETHY für die Aufheizphase von Brennstäben bei Kühlmittelverlust,” Proc. Dt. Reaktortagung, Hannover, DATF, p. 379 (1978).
- M. G. WEIDINGER et al., “LOCA Fuel Rod Behaviour of KWU-Pressurized Water Reactors,” Proc. CSNI Specialists' Mtg. Behaviour of Water Reactor Fuel Element Under Accident Conditions, Spatind, Norway, Sec. II, Paper No. 26 (1976).