Nuclear power systems

J. Santucci and J. J. Taylor, Safety, Technical and Economic Objectives of the Electric Power Institute s didvancedTight-Water Reactor Programme, lAEA-SM-332/11.1, Proceedings of International Symposium on Advanced Nuclear Power Systems, Seoul, Korea, Oct. 1993. 

Chart of the Nuclides, 12th ed.. General Electric Co., Nuclear Power Systems Division, San Jose, Calif., 1977. 

E. A. Skrabek, Proceedings of the 7th Symposium on Space Nuclear Power Systems, Albuquerque, N.M., 1990. 

Embrey, D. E (1986). SHERPA A Systematic Human Error Reliability Prediction Approach. Proceedings of the American Nuclear Society International Topical Meeting on Advances in Human Factors in Nuclear Power Systems. 

Scott, P. M., Proc. 3rd Symp. on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors. Edited by G. J. Theus and J. R. Weeks, AIME - The Metallurgical Society Inc., Warrendale, Pa., p 15, (1987)... 

Chul Kim, U. R. and van Rooyen, D., Strain rate and temperature effects on the stress corrosion cracking of Inconel 600 steam generator tubing in the (PWR) primary water conditions , Proc. 2nd Int. Conf. on Environmental Degradation of Materials in Nuclear Power Systems-VIalet Reactors, Monterey, USA, 9-12 Sept. 1985, American Nuclear Society, pp. 448-55 (1986)... 

Sheeks, C. J., Moshier, W. C., Ballinger, R. G., Latanison, R. M., Pelloux, R. M. N., Fatigue crack growth of Alloys X750 and 600 in simulated PWR and BWR environments , Proc. 1st Int. Conf. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, Myrtle Beach, USA, 22-25 Aug. 1983, NACR pp. 701-25 (1984)... 

We have all heard that public attitudes will prevent a future reliance on new nuclear power systems. However, independent polling by Hank Jenkins-Smith at the University of New Mexico (some of which was sponsored by Sandia National Laboratories), found a somewhat different picture ... 

Because early Canadian reactors used heavy water, and because it is also fundamentally the most efficient moderator, Canada naturally adopted the heavy water reactor for the development of a nuclear power system. By using heavy water both as moderator and as coolant, and by refuelling with the reactor at power, it was possible to develop the CANDU system to operate efficiently and economically with natural uranium fuel. This in turn resulted in the simplest possible fuel cycle. 

Magwood, W. D., IV. 2000. Roadmap to the next generation of nuclear power systems A vision for a powerful future. Nuclear News, 43, 35-38. 

T.C. Wallace. Transactions 8th Symposium on Space Nuclear Power Systems, (AIP CONF-910116, 1991), 1024. 

Young, L.M., Andresen, P.L., in Proc. 7th Int. Symp. On Environmental Degradation of Materials in Nuclear Power Systems — Water Reactors, NACE, Vol. 2, p. 1193, 1995. 

Bezhunov, G.M., et al. (1989) Experimental and analytical study of prompt neutron lifetime in fast reactors with moderation zones in the reflector, in Neutronic problems of nuclear power system safety paper theses VI AU-Union Workshop on Reactor Physics, Tsniiatominform Publishers, Moscow, pp.48-50 (in Russian). 

A. Bertuch, J. Pang, D, D. Macdonald, The Argument for Low Hydrogen and Lithium Operation in PWR Primary Circuits, in the Seventh International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, Breckenridge, CO, August 6-10, 1995. 

Williams, T., Burch, P., English, C., and Ray, P. (1988) Proceedings of the Third International Symposium on Environment Degradation of Materials in Nuclear Power Systems- Water Reactors, Traverse City, 121, The Metallurgical Society,... 

In addition to its potential use in nuclear power systems, thorium has had minor industrial use in Welsbach mantles for incandescent gas lamps, in magnesium alloys to increase strength and creep resistance at high temperatures, and in refractories. 

Of the three moderators that make possible a fission chain reaction in natural uranium, heavy water, graphite, or beryllium, heavy water has become the preferred material. It is used both as coolant and moderataor in heavy-water reactors, which are the exclusive source of nuclear power in Canada, Argentina, and Pakistan, are being used in India, and are being considered in other countries wishing to have a nuclear power system not dependent on a source of enriched uranium. 

The preceding introduction to the preface of the first edition of this book can still serve as the theme of this second edition. Since 1957 nuclear power systems have become important contributors to the energy supply of most industrialized nations. This text describes the materials of special importance in nuclear reactors and the processes that have been developed to concentrate, purify, separate, and store safely these materials. Because of the growth in nuclear technology since the fust edition appeared and the great amount of published new information, this second edition is an entirely new book, following the first edition only in its general outline. 

V. 1. Subbotin, M. K. Ibragimov et al.. Hydrodynamics and Heat Transfer in Nuclear Power Systems, Atomizdat, Moscow, 1975. 

The United States Department of Energy (DOE) manages approximately 1.9 billion cubic meters of radionuclide contaminated environmental media and 4.1 million cubic meters of stored, contaminated waste at 150 different sites located in 30 different states (i, 2). This environmental legacy is a result of the massive industrial complex responsible for defense related and non-defense related research, development and testing of nuclear weapons, nuclear propulsion systems and commercial nuclear power systems. Cleaning up the environmental legacy is expected to cost several hundred billion dollars over the next 5 to 7 decades. To reduce costs and speed remediation efforts the DOE has invested in waste treatment and environmental remediation research. 

The Nil-Ductility Transition (NDT) temperature, which is the temperature at which a given metal changes from ductile to brittle fracture, is often markedly increased by neutron irradiation. The increase in the NDT temperature is one of the most important effects of irradiation from the standpoint of nuclear power system design. For economic reasons, the large core pressure vessels of large power reactors have been constructed of low carbon steels. 

T. Shoji, Progress in the mecharristic understanding of BWR SCC and its imphcation to the prediction of SCC growth behavior in plants, in Proceedings of the 11th International Symposium Environmental Degradation Materials Nuclear Power Systems-Water Reactors, American Nuclear Society, 2003, pp. 588—598. 

P.M. Scott, C. Benhamou, An overview of recent observation and interpretation of IGSCC in nickel base alloys in PWR primary water, in Proceedings of the 10th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems— Water Reactors, NACE, 2001, CDROM. 

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