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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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Dry Ice Blasting: A Game-Changer for Safe Cleaning and Decontamination in Nuclear Power Plants
The nuclear energy industry is critical not only for meeting the world’s growing demand for electricity but also for advancing global decarbonization goals. As the sector evolves—through life extensions of existing plants, decommissioning, innovations like small modular reactors (SMRs) and microreactors, and new facility construction—the need for safe, efficient, and environmentally responsible maintenance and decommissioning continues to grow. Whether a plant is coming online, operating beyond its original design life, or entering decommissioning, cleanliness and operational integrity remain non-negotiable. That’s where dry ice blasting stands out—a powerful, safe cleaning method ideally suited for the high-stakes demands of nuclear environments.
Tohru Mitsutake, Shigeaki Tsunoyama, Shigeru Kanemoto, Hideaki Namba, Shirley A. Sandoz
Nuclear Technology | Volume 65 | Number 3 | June 1984 | Pages 365-373
Technical Paper | Fission Reactor | doi.org/10.13182/NT84-A33391
Articles are hosted by Taylor and Francis Online.
The multivariable autoregressive (AR) model identification technique has been applied in the study of the boiling water reactor core stability test analysis. It has been demonstrated through the analysis of core stability tests performed at the Peach Bottom-2 reactor, so that the AR model technique is effective in estimating core stability performance. Neutron flux to dome pressure open-loop stability performance is estimated by two methods, the ordinary correlation method and the AR model technique. Results obtained by both methods are in good agreement. The AR model technique can provide closed-loop decay ratios. This kind of decay ratio is considered to represent the actual core stability characteristic. Based on these test analysis results, the closed-loop in-reactor characteristic is more stable than the open-loop characteristic, which is usually considered to be the stability index for the reactor core. It was attempted to evaluate error in the AR model technique through indirect ways. It has been concluded that the AR model technique for the stability test data analysis is quantitatively highly effective in identifying and evaluating the core stability characteristics.