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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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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.
M. Grounes
Nuclear Technology | Volume 5 | Number 4 | October 1968 | Pages 228-235
Technical Paper and Note | doi.org/10.13182/NT68-A28024
Articles are hosted by Taylor and Francis Online.
The susceptibility to irradiation effects in different heats of the same steel and in parts of a reactor vessel that had gone through different stages in the manufacturing process was investigated. Fourteen sets of miniature impact specimens of Uddeholm UHB 2103/R3 steel, the pressure vessel material of the Ågesta reactor, were irradiated at 235 ± 15°C to a neutron fluence of 4 × 1018 − 1019 n/cm2 (>1 MeV). The results indicate that there might be a difference by a factor of 2 in irradiation-induced transition temperature increases between materials from different parts of the vessel. Generally, changes in the hot-pressed material seemed to be larger. If irradiation-damage studies are performed on flat, normalized plate, the results are valid if an extra safety margin of 30°C is applied.