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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.
T. Ozawa, T. Abe
Nuclear Technology | Volume 156 | Number 1 | October 2006 | Pages 39-55
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT156-39
Articles are hosted by Taylor and Francis Online.
Annular fuel is very beneficial for fast reactors because of its availability for both high power and high burnup. Most of the annular pellets irradiated up to high burnup showed central-hole shrinkage due to deformation and restructuring during irradiation. This shrinkage has a great influence on power-to-melt, which is a main factor in deciding the maximum power in the fuel design. To predict precisely the central-hole shrinkage during irradiation, the CEPTAR code was developed and verified by using the results of various experiments. In this code, the central-hole diameter is decided in accordance with the law of conservation of mass by using the radial profile of fuel density computed with the void migration model, and its deformation caused by the thermal expansion, swelling, and creep is computed by stress-strain analysis using the approximation of plane strain. Furthermore, this code can also estimate the effect of joint oxide gain (JOG) observed in a gap between the cladding and the fuel pellet with high burnup, which tends to decrease the fuel swelling and to improve the gap conductance due to deposition of solid fission product to the JOG layer. In this paper, an outline of the CEPTAR code and the results of verification are presented.