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Division Spotlight
Reactor Physics
The division's objectives are to promote the advancement of knowledge and understanding of the fundamental physical phenomena characterizing nuclear reactors and other nuclear systems. The division encourages research and disseminates information through meetings and publications. Areas of technical interest include nuclear data, particle interactions and transport, reactor and nuclear systems analysis, methods, design, validation and operating experience and standards. The Wigner Award heads the awards program.
Meeting Spotlight
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver 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!
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Will Palisades be the “comeback kid”?
Mike Mlynarek believes in this expression: “In the end it will be OK; and if it’s not OK, it’s not the end.”
As the site vice president at Palisades nuclear power plant in Covert Township, Mich., Mlynarek is overseeing one of the most exciting projects in the United States nuclear power industry. If all goes according to plan, Holtec’s Palisades plant will be splitting atoms once again by the end of 2025 and become the first U.S. nuclear facility to restart after being slated for decommissioning.
Zoltán Hózer, Péter Windberg, Imre Nagy, László Maróti, Lajos Matus, Márta Horváth, Anna Pintér Csordás, Márton Balaskó, Aladár Czitrovszky, Péter Jani
Nuclear Technology | Volume 141 | Number 3 | March 2003 | Pages 244-256
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT03-A3365
Articles are hosted by Taylor and Francis Online.
In the late phase of a severe reactor accident, the molten corium interacts with the vessel wall, and it can lead to the failure of the lower head. Through the failed bottom wall, part of the corium can flow into the cavity, and air can enter the primary circuit. The residual fuel in the core periphery will be further oxidized in air atmosphere. The degradation process will accelerate, and new chemical species will be formed, which can have an impact on the release of radioactive materials.Two experiments were carried out with electrically heated nine-rod pressurized water reactor-type bundles in the CODEX (COre Degradation EXperiment) facility to provide experimental data on the behavior of real fuel bundles under air oxidation conditions. The main objective of the tests was the investigation of oxidation phenomena, and some other important aspects (e.g., enhanced fission product release) were not addressed.The CODEX air ingress tests indicated the acceleration of oxidation phenomena and core degradation processes during the late phase of the vessel melt through accident, when air can have access to the residual fuel bundles in the reactor core. The degradation process was accompanied with zirconium-nitride formation and release of uranium-rich aerosols.