American Nuclear Society

American Nuclear Society (ANS) 555 N. Kensington Avenue La Grange Park, lU. 60525... 

P. Cohen, Water Coolant Technology of PomrReaetors, American Nuclear Society, LaGrange Park, HI., 1980. 

S. ViUani, Isotope Separation, American Nuclear Society, HiUsdale, fll., 1976, Chapts. 9, 10, 11, and 12. 

Early research and development is described in a symposium proceedings (54). The status of the CANDU program as of 1975 is given in Reference 55 and a brief history maybe found in a more recent pubHcation of the American Nuclear Society (37). 

R. T. Lahey, Jr. and E. J. Moody, The Thermal-Hydraulics of a Boiling Water Nuclear Reactor, 2nd ed., American Nuclear Society, La Grange Park, lU., 1993. 

J. J. Taylor and E. E. Kintner, The Evolution of Self-Stabili yation in Nuclear Power Development 50 Years with NuclearFission, American Nuclear Society, La Grange, hi., 1989. 

G. H. Miley, Fusion Energy Conversion, American Nuclear Society, Washington, D.C., 1976. 

L. R. Kehnan, J. L. Armstrong, W. H. Livemash, and H. V. Rhude, Proceedings of the Ninth Conference on Hot Eaboratories and Equipment, American Nuclear Society, LaGrange Park, lU., 1963. 

S. ViUani, Isotope Separation American Nuclear Society, 1976. 

E. W. Becker and co-workers, American Nuclear Society Meeting, KFK-Bericht 2235 GeseUschaft fer Kemforschung, Kadsmlie, 1975. 

Summaries of these results were reported in a special session of the American Nuclear Society ANS trans. 53, pp. 315-325, 1986. 

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. 

Joschek, H. I. (1981). Risk Assessment in the Chemical Industry. Proceedings of the International ANS/ENS Topical Meeting on Probabilistic Risk Assessment, September 20-24,1981, New York. American Nuclear Society 555 North Kensington Avenue, LaGrange Park, IL 60525. 

American Nuclear Society, (annual). High Level Radioactive Waste Management Proceedings for the International Topical Meeting of the American Nuclear Society and the American Society of Cavil Engineers. Chicago American Nuclear Society. 

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)... 

McKibben, J. M. Starks, J. B. Brown, J. K. in "Proceedings of 27th Conference on Remote Systems Technology," American Nuclear Society, La Grange Park, IL., 1979. 

The report ofthe American Nuclear Society s International Panel on Protection and Management of Plutonium - the Seaborg Panel - was the first to emphasize the importance of... 

Figure 2.5 Idealized representation of an active cavity (a) situation at maximum boiling suppression (b) situation at incipient boiling. (From Dwyer, 1976. Copyright 1976 by American Nuclear Society, LaGrange Park, IL. Reprinted with permission.)... 

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