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
2025 ANS Winter Conference & Expo
November 9–12, 2025
Washington, DC|Washington Hilton
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
Oct 2025
Jul 2025
Latest Journal Issues
Nuclear Science and Engineering
November 2025
Nuclear Technology
Fusion Science and Technology
Latest News
TVA nominees promise to support advanced reactor development
Four nominees to serve on the Tennessee Valley Authority Board of Directors told the Senate Environment and Public Works Committee that they support the build-out of new advanced nuclear reactors to meet the increased energy demand being shouldered by the country’s largest public utility.
Robert David
Nuclear Technology | Volume 205 | Number 11 | November 2019 | Pages 1488-1494
Technical Paper | doi.org/10.1080/00295450.2019.1597581
Articles are hosted by Taylor and Francis Online.
Finite element analysis is used to study heat transfer from a corium pool at the bottom of the calandria to its surroundings during a severe accident in a CANDU 6 reactor. The shape of the corium crust around the pool and the steady-state heat fluxes exiting the calandria are calculated for representative accident conditions. The sensitivity of the results to several model parameters is examined. Calculated heat fluxes can be compared to measurements of the critical heat flux at different locations on the outside of the calandria in order to assess the possibility of in-vessel retention of the molten core.