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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!
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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.
B. F. Rubin, T. J. Black, W. K. Appleby, J. D. Stephen, R. F. Hilbert
Nuclear Technology | Volume 16 | Number 1 | October 1972 | Pages 89-99
Technical Paper | Reactor Materials Performance / Material | doi.org/10.13182/NT72-A31178
Articles are hosted by Taylor and Francis Online.
Experimental determinations of cladding plastic deformation in (U,Pu)O2 fuel rods, clad with annealed Type 316 stainless steel and irradiated in EBR-II, indicate that fuel-cladding mechanical interaction takes place between ∼3 and 8 at.% burnup. At higher burnups, the cladding swelling rate increases markedly resulting in no further fuel-induced plastic deformation. The maximum cladding plastic strain exhibited by several annealed Type 316 stainless-steel-clad rods was 0.4%. Cladding plastic strain was found to be independent of smeared density in the range of 83 to 91% TD.
