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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.
Kohyu Fukunishi
Nuclear Science and Engineering | Volume 67 | Number 3 | September 1978 | Pages 296-308
Technical Paper | doi.org/10.13182/NSE78-A27250
Articles are hosted by Taylor and Francis Online.
Some attempts have been made to investigate noise sources in a boiling water reactor (BWR) by multivariate random data analyses. Autoregression and multivariate coherency such as partial and/or multiple coherency have been introduced to the analysis of time series data gathered from a medium-sized BWR plant (BWR-3) of 460-MW electric power to evaluate linear relations among multiple inputs and outputs that are coupled with each other by sophisticated feedbacks. Through these attempts, the main local disturbance that leads to the peak in the spectrum of reactor power noise and is classified as global noise has been concluded to be caused by noise sources originated, not outside the reactor core, but inside the reactor core itself Furthermore, the noise sources in the core have been found to be the turbulence of bubble generation and extinction in the lower region of coolant flow channel. It is found that the noise sources have different resonant frequencies that depend on the running speeds of coolant flows in fuel assemblies near the bottom local detector. It can also be shown that pressure waves induced by the local disturbances propagate into the coolant water in the lower core plenum, where they are mixed together into a single-pressure wave whose resonant frequency corresponds to the peak frequency in the spectrum of reactor power noise.