ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
Explore membership for yourself or for your organization.
Conference Spotlight
2026 ANS Annual Conference
May 31–June 3, 2026
Denver, CO|Sheraton Denver
Latest Magazine Issues
Jan 2026
Jul 2025
Latest Journal Issues
Nuclear Science and Engineering
February 2026
Nuclear Technology
January 2026
Fusion Science and Technology
November 2025
Latest News
Jeff Place on INPO’s strategy for industry growth
As executive vice president for industry strategy at the Institute of Nuclear Power Operations, Jeff Place leads INPO’s industry-facing work, engaging directly with chief nuclear officers.
Jean-Louis Bernard, Georges S. Slama
Nuclear Technology | Volume 59 | Number 1 | October 1982 | Pages 136-147
Technical Paper | Material | doi.org/10.13182/NT82-A33059
Articles are hosted by Taylor and Francis Online.
The need exists to define a fatigue crack growth design curve in an air environment for austenitic stainless steels in the temperature range of 300°C, which is the operating temperature range of pressurized water reactors. In the present study, elements to determine such a curve in a deterministic way are developed. In particular, effects of R ratio (Kmin/Kmax) are reviewed, and high R ratio tests, which were lacking, have been performed. To take into account R ratio effects, a relationship giving realistic predictions in accordance with high R ratio experiments is determined. A design curve, defined from a large compilation of results from several laboratories, allows a conservative calculation of all known fatigue crack growth tests on austenitic stainless steels in the temperature range of 300°C.