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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.
C. Vaglio-Gaudard, A. Santamarina, D. Bernard, G. Noguère, J. M. Ruggieri, J. F. Vidal, A. Lyoussi
Nuclear Science and Engineering | Volume 166 | Number 3 | November 2010 | Pages 267-275
Technical Paper | doi.org/10.13182/NSE09-103
Articles are hosted by Taylor and Francis Online.
The 56Fe international covariance matrices recommend variances for capture, elastic, and inelastic cross sections. Analysis shows that these matrices are often inconsistent and unrealistic. A new covariance matrix was established on the basis of feedback from the interpretation of two integral benchmarks representative of Generation III and Generation IV reflectors. Flux attenuation in the reflector at various energies demonstrates good agreement between calculation and experiment. The RDN code based on a nonlinear regression method using an iterative technique (limited to the first Gauss-Newton iteration in this study) was used to reestimate 56Fe cross sections and to deduce the a posteriori covariance matrix associated with the JEFF3.1.1 library. The results highlight that the 56Fe cross-section levels in the JEFF3.1.1 library are satisfactory. The new covariance matrix can then be used as a reference to calculate uncertainty propagation.