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2025 ANS Winter Conference & Expo
November 9–12, 2025
Washington, DC|Washington Hilton
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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.
M. Guyette
Nuclear Technology | Volume 9 | Number 1 | July 1970 | Pages 60-69
Fuel Cladding Model | Symposium on Theoretical Models for Predicting In-Reactor Performance of Fuel and Cladding Material | doi.org/10.13182/NT70-A28728
Articles are hosted by Taylor and Francis Online.
The computer program CRASH allows the calculation of triaxial stress and strain states in the sheath of cylindrical fuel elements when creep or plasticity occur in the cladding material. Any creep or plasticity law may be used in the program and any type of external stresses and strains assumed. A short description of the program is given in the first part of this paper. Its second part deals with some applications: examples of plastic thermal ratchetting under cyclic conditions and creep of cladding due to contact pressure are presented. These few examples show that the CRASH program is a useful and flexible tool for the cladding design of fuel elements. Moreover, its calculation time is sufficiently small as to allow intensive parametric studies.