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
October 2025
Latest News
Researchers use one-of-a-kind expertise and capabilities to test fuels of tomorrow
At the Idaho National Laboratory Hot Fuel Examination Facility, containment box operator Jake Maupin moves a manipulator arm into position around a pencil-thin nuclear fuel rod. He is preparing for a procedure that he and his colleagues have practiced repeatedly in anticipation of this moment in the hot cell.
S. Benedek
Nuclear Technology | Volume 53 | Number 3 | June 1981 | Pages 381-387
Technical Paper | Nuclear Fuel Cycle Education Module / Nuclear Safety | doi.org/10.13182/NT81-A32646
Articles are hosted by Taylor and Francis Online.
Some disturbances in operation can result in the separation of primary coolant into two phases, thus establishing a water level so that the cladding is cooled only with steam. A calculation model was developed to examine such cases. In comparing the calculation results with the measurement results, the measurements confirmed the calculations. The measurements taken at low pressures covered only the examination of the drying process. For a reactor, as an example, examinations were carried out with the calculation model to determine the extent of cooling of the core in such cases. The extent of cooling was found to be sufficient to avoid an intensive zirconium reaction if the closed primary circuit is cooled through the steam generators.