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 8–12, 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
Nov 2025
Jul 2025
Latest Journal Issues
Nuclear Science and Engineering
December 2025
Nuclear Technology
November 2025
Fusion Science and Technology
Latest News
ANS announces 2026 Presidential Citations
One of the privileges of being president of the American Nuclear Society is awarding Presidential Citations to individuals who have demonstrated outstanding effort in some manner for the benefit of ANS or the nuclear community at large. Citations are conferred twice each year, at the Annual and Winter Meetings.
ANS President Hash Hashemian has named this season’s recipients, who will receive recognition at the upcoming 2025 Winter Conference & Expo in Washington, D.C.
Peter Weimar, Wolfgang Ernst
Nuclear Technology | Volume 57 | Number 1 | April 1982 | Pages 81-89
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT82-A16188
Articles are hosted by Taylor and Francis Online.
Until now, experience with the consequences of longer operation of failed mixed oxide fuel pins in liquid-metal fast breeder reactor has not been available. Mol-7B, an 18-pin bundle, was originally specified and fabricated to test the SNR-300-Mk-Ia concept under extreme operating conditions, especially with a cladding temperature of 973 K. Because of larger uncertainties of flux distribution in the BR-2 reactor in Mol, Belgium, this bundle was irradiated with a rod power that was 20% higher as expected. As a consequence, 17 of the 18 pins failed during the irradiation campaign. The main reason was mechanical interaction of the fuel with the embrittled and corroded cladding and excessive fission gas pressure. Cladding opening was followed by chemical reaction between sodium coolant and the fuel. A partial blockage occurred from the buildup of the reaction product Na3MO4 and from the diameter increase due to uranate swelling. In spite of these severe failures and large fuel release to the coolant, the bundle could be operated with a high nominal rod power without cladding melting and more severe consequences on bundle integrity and on reactor safety.