Publisher's Synopsis
The fast-neutron breeder reactor is the principal means now envisaged of exploiting the very large resource of energy residing in the naturally abundant isotope of uranium 238. Extensive research and development programmes are being carried out in a number of countries to realize this potential. There are about a dozen substantial reactors operating, and wide-ranging supporting programmes include fuel processing and development, and safety and environmental issues.;This Discussion Meeting held at the Royal Society in May 1989, brought together experts from all participating countries. The technical sessions included: basic science and engineering; reports on progress in the U.S.S.R.,U.S.A., Japan and Western Europe; the fuel cycle, including fuel design, reprocessing and environmental aspects; reactor safety and engineering; economics. A concluding session summarized participants' thoughts on the future of fast reactors.
