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
Mar 2026
Jan 2026
Latest Journal Issues
Nuclear Science and Engineering
March 2026
Nuclear Technology
February 2026
Fusion Science and Technology
April 2026
Latest News
ANS, UCOR sign MOU for workforce development program
The American Nuclear Society and United Cleanup Oak Ridge have signed a memorandum of understanding that establishes a framework for collaboration to advance ANS workforce training and certification programs serving the nuclear industry.
According to the document, UCOR will provide “operational insights and subject matter expertise to inform ANS’s professional development and credentialing offerings, including the Certified Nuclear Professional [CNP] program.” The collaboration will strengthen UCOR’s workforce development efforts while advancing ANS’s mission to sustain and expand the national nuclear workforce pipeline and capabilities.
J. L. Straalsund, M. M. Paxton
Nuclear Technology | Volume 13 | Number 1 | January 1972 | Pages 99-102
Technical Note | Material | doi.org/10.13182/NT72-A31072
Articles are hosted by Taylor and Francis Online.
Densification occurs during the aging of austenitic stainless steels. This study was conducted to determine the extent of densification during thermal aging of AISI Type 316 stainless steel. This objective was accomplished through both length change measurements and bulk density measurements on Type 316 stainless-steel tubing before and after aging treatments at 1200°F for aging times up to 1000 h. Various cold work levels, from 0 to 20%, were investigated. In all cases the tubes were found to shrink, the shrinkage increasing with cold-work level and aging time with a maximum change of −0.06% ΔL/L. A comparison of the bulk density and length change measurements indicates that within the experimental accuracy the densification phenomena are isotropic. Irradiation-induced creep and swelling in austenitic stainless steels have been a source of major concern in the development of LMFBRs. The densification or shrinkage phenomena influence measurements particularly for low values of strain and/or swelling. It is therefore important to take the densification phenomena into account when extrapolating low fluence data on swelling and creep.