As part of an increasing interest in radiation embrittlement for aging nuclear reactors, scientists gathered in New Orleans in January 1997 to consider the interests and capabilities of the scientific-testing community and of the commercial light-water-cooled power-reactor industry in terms of improving methods to characterize component integrity. The resulting 37 papers concentrate on the use of unique small and miniature specimens; nondestructive, nonintrusive, and in- situ test techniques for measuring mechanical and fracture properties; the application of tests to irradiation-induced embrittlement; and actual examples of tests to determine material integrity and to evaluate potential component life extension. They consider experimental, analytical, and computational aspects. Annotation copyrighted by Book News, Inc., Portland, OR
Design and Analyses Thomas Schulenberg Jörg Starflinger ... 600 700 800 500 600 700 800 10 15 20 25 30 0 5 10 15 Time (s) 20 25 30 Time (s) Figure 4.38: Maximal cladding temperature and its position in the hot channel of the evaporator, ...
"The limitation of 235U enrichment is a current concern among IAEA Member States.
Light Water Reactor Materials
Proceedings of the International Topical Meeting on LWR Fuel Performance: Williamsburg, Virginia, April 17-20, 1988