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.
V. F. Baston, J. H. McFadden, W. A. Yuill
Nuclear Technology | Volume 14 | Number 3 | June 1972 | Pages 247-256
Technical Paper | Fuel | doi.org/10.13182/NT72-A31114
Articles are hosted by Taylor and Francis Online.
An analytical method based on the steady-state release model developed by Idaho Nuclear Corporation (now Aerojet Nuclear Company) is presented for calculating noble gas and iodine release to the fuel cladding gap of fuel pins in a nuclear reactor operating at steady-state conditions. This method, which employs fission gas capsule data and conservative assumptions (assumptions that result in prediction of maximum release), can be used in reactor safety analysis to predict the fission gases that could be available for release in the event of cladding failure and the pressure exerted by the fission gases on the inside of the cladding during reactor operation.