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Division Spotlight
Fusion Energy
This division promotes the development and timely introduction of fusion energy as a sustainable energy source with favorable economic, environmental, and safety attributes. The division cooperates with other organizations on common issues of multidisciplinary fusion science and technology, conducts professional meetings, and disseminates technical information in support of these goals. Members focus on the assessment and resolution of critical developmental issues for practical fusion energy applications.
Meeting Spotlight
ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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March 2025
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February 2025
Latest News
RP3C Community of Practice’s fifth anniversary
In February, the Community of Practice (CoP) webinar series, hosted by the American Nuclear Society Standards Board’s Risk-informed, Performance-based Principles and Policies Committee (RP3C), celebrated its fifth anniversary. Like so many online events, these CoPs brought people together at a time when interacting with others became challenging in early 2020. Since the kickoff CoP, which highlighted the impact that systems engineering has on the design of NuScale’s small modular reactor, the last Friday of most months has featured a new speaker leading a discussion on the use of risk-informed, performance-based (RIPB) thinking in the nuclear industry. Providing a venue to convene for people within ANS and those who found their way online by another route, CoPs are an opportunity for the community to receive answers to their burning questions about the subject at hand. With 50–100 active online participants most months, the conversation is always lively, and knowledge flows freely.
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.