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2025 ANS Winter Conference & Expo
November 9–12, 2025
Washington, DC|Washington Hilton
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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.
William T. Lee
Nuclear Technology | Volume 7 | Number 2 | August 1969 | Pages 155-163
Radioisotopes | doi.org/10.13182/NT69-A28359
Articles are hosted by Taylor and Francis Online.
During the study of the stress-rupture properties of austenitic stainless steels in high-purity static liquid sodium, zirconium foil was placed in the sodium to getter oxygen and maintain a high-purity sodium environment throughout the test. Results of the biaxial stress-rupture tests on thin-walled Type-304 and Type-316 stainless-steel tubing in the range 1200°F (649°C) to 1400°F (760°C) showed that the rupture strength of the tubing was significantly lower in the zirconium-gettered static sodium than in non-gettered static sodium or helium. This reduction in rupture strength was greater with higher test temperature and longer exposure time. In the presence of sodium, the zirconium foil decarburized the stainless steel; the decarburization process also resulted in an extensive sigma-phase formation on the region of the tubing exposed to sodium. The decarburization increased with test temperature and time of exposure. It was concluded that the decreased stress-rupture strength of specimens tested in zirconium-gettered sodium was caused by decarburization of the stainless steel.