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Aerospace Nuclear Science & Technology
Organized to promote the advancement of knowledge in the use of nuclear science and technologies in the aerospace application. Specialized nuclear-based technologies and applications are needed to advance the state-of-the-art in aerospace design, engineering and operations to explore planetary bodies in our solar system and beyond, plus enhance the safety of air travel, especially high speed air travel. Areas of interest will include but are not limited to the creation of nuclear-based power and propulsion systems, multifunctional materials to protect humans and electronic components from atmospheric, space, and nuclear power system radiation, human factor strategies for the safety and reliable operation of nuclear power and propulsion plants by non-specialized personnel and more.
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2024 ANS Winter Conference and Expo
November 17–21, 2024
Orlando, FL|Renaissance Orlando at SeaWorld
Standards Program
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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Latest News
Bruce Power refurbishment project ahead of schedule
Bruce Power has announced the completion of its Unit 3 reactor removal—a milestone on its Major Component Replacement (MCR) project aimed at extending the Bruce plant’s operational life through 2064.
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.