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Conference Spotlight
2025 ANS Winter Conference & Expo
November 9–12, 2025
Washington, DC|Washington Hilton
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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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Latest News
High temperature fission chambers engineered for AMR/SMR safety and performance
As the global energy landscape shifts towards safer, smaller, and more flexible nuclear power, Small Modular Reactors (SMRs) and Gen. IV* technologies are at the forefront of innovation. These advanced designs pose new challenges in size, efficiency, and operating environment that traditional instrumentation and control solutions aren’t always designed to handle.
Klaus L. Nissen
Nuclear Technology | Volume 95 | Number 2 | August 1991 | Pages 175-192
Technical Paper | Nuclear Fuel Cycle | doi.org/10.13182/NT91-A34555
Articles are hosted by Taylor and Francis Online.
Fuel rod computer models are utilized to predict cladding tube integrity under normal operating or transient accident conditions in a nuclear fission reactor. The METHOD2D computer code, which includes a fuel rod mechanics model based on an axisymmetric finite element formulation, is developed and verified. This two-dimensional approach gives results for the axial and radial deformation of the fuel pellets and the cladding tube for the whole fuel rod. Because an algorithm for fuel pellet/cladding tube radial contact and axial friction is incorporated, the analysis of closed fuel/cladding gap situations is possible. Calculation results for a whole fuel rod are compared with a transient CABRI experiment that led to partial fuel melting but not to cladding failure.
