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
Feb 2026
Jul 2025
Latest Journal Issues
Nuclear Science and Engineering
March 2026
Nuclear Technology
February 2026
Fusion Science and Technology
January 2026
Latest News
CLEAN SMART bill reintroduced in Senate
Senators Ben Ray Luján (D., N.M.) and Tim Scott (R., S.C.) have reintroduced legislation aimed at leveraging the best available science and technology at U.S. national laboratories to support the cleanup of legacy nuclear waste.
The Combining Laboratory Expertise to Accelerate Novel Solutions for Minimizing Accumulated Radioactive Toxins (CLEAN SMART) Act, introduced on February 11, would authorize up to $58 million annually to develop, demonstrate, and deploy innovative technologies, targeting reduced costs and safer, faster remediation of sites from the Manhattan Project and Cold War.
C. R. Brinkman, G. E. Korth, R. R. Hobbins
Nuclear Technology | Volume 16 | Number 1 | October 1972 | Pages 297-307
Technical Paper | Reactor Materials Performance / Material | doi.org/10.13182/NT72-A31195
Articles are hosted by Taylor and Francis Online.
Comparing data obtained from tests conducted on unirradiated Type 316 stainless steel in either the solution annealed or solution annealed and aged condition showed that aging was beneficial in improving both the fatigue and creep-fatigue properties at 593°C (1100°F). An indication was found that unirradiated Type 304 stainless steel would be more suitable for applications involving creep-fatigue interaction than unirradiated Type 316 stainless steel. Irradiation to fluences of 0.17 to 6.1 × 1021 n/cm2 E > 0.1 MeV (450°C), resulted in a pronounced effect on the creep-fatigue resistance of these materials when tested at a strain range of 1%. Both fatigue and creep damage values were calculated using actual times and cycles to failure and design times and cycles to failure. These damage values were summed linearly. Damage sums obtained were not found to be a unique value but dependent upon strain range, length of tensile hold time, and material condition. Comparisons between estimates of irradiated fatigue behavior and actual irradiated fatigue lifetimes were made using limited data available. Estimates made using irradiated tensile data were usually found to be conservative in predicting pure fatigue behavior.