By M.R. Cundy, P. Von der Hardt and R.H. Loelgen (Eds.)
Read Online or Download Measurement of Irradiation-enhanced Creep in Nuclear Materials. Proceedings of an International Conference Organized by the Commission of the European Communities at the Joint Research Centre, Petten, The Netherlands, May 5–6, 1976 PDF
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Extra info for Measurement of Irradiation-enhanced Creep in Nuclear Materials. Proceedings of an International Conference Organized by the Commission of the European Communities at the Joint Research Centre, Petten, The Netherlands, May 5–6, 1976
The experimental observations are reported and discussed in relation to models for irradiation induced low temperature creep in ceramic fuels. Le comportement au fluage du dioxyde d'uranium et du carbure d'uranium a été examiné à la fois dans des expériences de flexion et de compression dans le réacteur pour essais des matériaux DIDO. Dans UO2 aucune variation importante de la vitesse de fluage avec la dose et la température ne se produisait au-dessus de 1 0 2 5 fissions par m 3 environ et aux températures de 450° à 1230°C, les vitesses de déformation élevées mesurées en compression aux faibles doses étant largement attribuables au frittage des pores.
Stratton, Nucl. Eng. Int. Vol. 17, no. 188, Feb. 1972; and AERE R6611.  D. Brucklacher, Creep of fissile ceramic materials under neutron irradiation element, Intern. Conf, on Phys. Metallurgy of Reactor Fuel, Berkeley 1973. J. Clough, Observations on the low temperature creep properties of uranium carbide under irradiation, AERE R7772 (1974). R. MacEwen, I. Hastings, A model for in-reactor densificationofU0 2 , Phil. Mag. Vol. 31 (1) Jan. 1975. S. Perrin, BMI 1857 (1969).  R. Anderson and R.
Ceed 1000°C. Thermocouples located in the central molybdenum insert are used to calculate the specimen surface temperature whilst others, situated elsewhere in the capsule and rig provide information on the thermal stability of the experimental assembly during operation. Two heaters are used to control the specimen temperature, the upper one maintaining a constant upper platen temperature whilst the lower maintains a zero temperature difference between the upper and lower platen. Compressive stress is applied to the specimen by a manually adjusted spring loading system which is located at the top of the irradiation assembly.
Measurement of Irradiation-enhanced Creep in Nuclear Materials. Proceedings of an International Conference Organized by the Commission of the European Communities at the Joint Research Centre, Petten, The Netherlands, May 5–6, 1976 by M.R. Cundy, P. Von der Hardt and R.H. Loelgen (Eds.)