Ford nuclear reactor

Forced-vibration instruments, 21 745 Force field calculations, 16 742 Force field energy, 16 742 Force field performance, 16 745 Force fields, 16 743-745 Force field simulations, 16 746-747 programs for, 16 746 Force modulation microscopy, 3 332 Forces, exponents of dimensions in absolute, gravitational, and engineering systems, 8 584t Forchlorfenuron, 13 43t, 53 Ford nuclear reactor, 17 594... 

Since its introduction, over fifty articles have been published (see references list) describing the use of NDP to investigate materials and effects directly relating to semiconductor research and device processing. The widespread application of NDP has been limited by the number of intense neutron sources available - nuclear reactors. At present, the U.S. has only two NDP facilities one at the University of Michigan Ford Nuclear Reactor (4-6), and a facility at the National Bureau of Standards Research Reactor (NBSR) in Gaithersburg, Maryland (7). Nevertheless, the literature indicates NDP has significant potential in the semiconductor industry. 

In power reactors, increases in fuel temperature produce rapid negative reactivity feedback as a result of the Doppler coefficient. This effect is not seen in the Ford Nuclear Reactor because of the very low uranium density in the fuel and because temperature variations across fuel plates are less than 1 F. 

Paquette, J., Ford, B. L. The radiation-induced formation of iodoalkanes and the radiolysis of iodomethane. Proc. 2. CSNI Workshop on Iodine Chemistry in Reactor Safety, Toronto, Can., 1988 Report AECL-9923 (1989), p. 48-73 Paquette, J., Sunder, S., Torgerson, D. F., Wren, C. J., Wren, D. J. The chemistry of iodine and cesium under reactor accident conditions. Proc. 3. BNES Conf. Water Chemistry in Nuclear Reactor Systems, Bournemouth 1983, Vol. 1, p. 71—79 Parsly, L. F. Chemical and physical properties of methyl iodide and its occurrence under reactor accident conditions. Report ORNL-NSIC-82 (1971)... 

RR Ford, Technical and management challenges associated with structural and materials degradation in nuclear reactors in the future, in Proceedings of the Thirteenth Environmental Degradation Conference, Whistler, British Columbia, Canada, August 2007. 

This facility design concept was not considered in White House reviews of reprocessing during the Ford and Carter Administrations, nor as an option for support by President Reagan, who had been elected on a platform to support reprocessing of commercial spent firel. The ERDA and the DOE had reassigned responsibilities for commercial fuel cycle to its Division of Reactor Development (later Office of Nuclear Energy) which supported pilot plant concepts of its national laboratories and rejected concepts based on successful experience and lessons learned from that experience. 

Andresen, P. L., Ford, F. P., Murphy, S. M., and Perks, J. M., State of Knowledge of Radiation Effects on Environmental Cracking in Light Water Reactor Core Materials, Proceedings of 4th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems—Water Reactors, D. Cubicciotti, Ed., NACE, Houston, TX, 1990. 

F. P. Ford, Prediction of corrosion fatigue initiation in low alloy and carbon steel water systems at 288C, Proceedings of 6th International Conference for Environmental Degradation of Materials in Nuclear Power Systems—Water Reactors, San Diego, TMS, 1993. 

P. Combrade, P. Ford, F. Nordmann, Key Results from Recent Conferences on Structural Materials Degradation in Water Cooled Reactors, Advanced Nuclear Technology International, Sweden, December 2010. LCC6 Special Report. 

P.L. Andresen, F.P. Ford, Modeling and prediction of irradiation assisted cracking, in G. Airey, et al. (Eds.), Proc. 7th Int. Symp. On Environmental Degradation of Materials in Nuclear Power Systems — Water Reactors, Breckenridge, CO, August 6—10, 1995, vol. 2, National Association of Corrosion Engineers, 1995, pp. 893—908. 

Root causes of failure of BWR piping in Swedish plants. (From Gott, K., Cracking data base as a basis for risk informed inspection, in Proceedings of Tenth International Conference on Environmental Degradation in Nuclear Power Systems-Water Reactors, Eds. F.P. Ford and G. Was, Published by National Association of Corrosion Engineers, Lake Tahoe, August 5-9,2001.)... 

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