Consulting metallurgist, Nuclear Utility Services, Inc., Washington, D. C.,
Pages: 1 Published: Jan 1964
With the increasing interest in the use of zirconium and, in particular, zirconium alloys in high-temperature, high-pressure, water- and steam-cooled reactor systems, it is appropriate to pause and evaluate our present knowledge of the various factors involved in the corrosion of alloys of this system. To this end, a Symposium on Corrosion of Zirconium Alloys was held at the 1963 Meeting of the American Nuclear Society. The work of organizing this most important and timely symposium was a joint effort of the Program Committee, Materials Division, American Nuclear Society, and of Subcommittee IX, Committee B-3 on Corrosion of Nonferrous Metals and Alloys, American Society for Testing and Materials. At that time, W. Kermit Anderson, of General Electric's Knolls Atomic Power Laboratory (KAPL), was chairman of both these committees, and we owe special thanks to him, as well as to his fellow members of both organizations, for the time and toil expended in arranging the program. Thanks are also due cochairman William Cashin of KAPL who so ably represented the American Nuclear Society. The coverage of the subject is as complete as can be hoped for in the limited time available. It is hoped that a “sequel” symposium can be arranged in the near future to extend the dissemination of our knowledge in these areas. For example, our participants have pointed out that we do not have agreement on the effects of radiation on the surface films of zirconium and its alloys, nor do we fully understand the mechanism involved in such contradictory effects as have been observed. A symposium devoted entirely to all phases of this important problem might well be scheduled. Also, the problems involved in the use of this class of materials at higher temperatures and in superheated steam are only partially solved, and this symposium has served to illuminate the problem. Much work, however, remains to be done.
Paper ID: STP47069S