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 Annual Conference
May 31–June 3, 2026
Denver, CO|Sheraton Denver
Standards Program
The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
Latest Magazine Issues
Nov 2025
Jul 2025
Latest Journal Issues
Nuclear Science and Engineering
December 2025
Nuclear Technology
Fusion Science and Technology
November 2025
Latest News
X-energy raises $700M in latest funding round
Advanced reactor developer X-energy has announced that it has closed an oversubscribed Series D financing round of approximately $700 million. The funding proceeds are expected to be used to help continue the expansion of its supply chain and the commercial pipeline for its Xe-100 advanced small modular reactor and TRISO-X fuel, according the company.
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.