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.
Division Spotlight
Operations & Power
Members focus on the dissemination of knowledge and information in the area of power reactors with particular application to the production of electric power and process heat. The division sponsors meetings on the coverage of applied nuclear science and engineering as related to power plants, non-power reactors, and other nuclear facilities. It encourages and assists with the dissemination of knowledge pertinent to the safe and efficient operation of nuclear facilities through professional staff development, information exchange, and supporting the generation of viable solutions to current issues.
Meeting Spotlight
2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
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
May 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
June 2025
Nuclear Technology
Fusion Science and Technology
Latest News
Atomic Museum marks 20 years of education
The National Atomic Testing Museum, better known as the Atomic Museum, is celebrating its 20th anniversary this year. Located in Las Vegas, Nev., the museum was established in 2005 to preserve the legacy of the Nevada Test Site, now called the Nevada National Security Sites.
A. J. Lovell
Nuclear Technology | Volume 26 | Number 3 | July 1975 | Pages 297-306
Technical Paper | Material | doi.org/10.13182/NT75-A24431
Articles are hosted by Taylor and Francis Online.
Specimens of annealed Type 316 stainless steel were irradiated in Experimental Breeder Reactor II at temperatures ranging from 900 to 1450°F and to fluences from 0.2 to 7 × 1022 n/cm2 (En > 0.1 MeV). Uniaxial and biaxial creep tests were performed at 1000, 1100, 1200, and 1400°F with rupture times from <1 to >1000 h. The test data show that rupture life changes due to irradiation can be substantial. The stress, fluence, and temperature dependence of rupture life are reduced to a mathematical form, , where A and B are temperature-dependent terms and the term ti/tn is temperature and fluence dependent.