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Young Members Group
The Young Members Group works to encourage and enable all young professional members to be actively involved in the efforts and endeavors of the Society at all levels (Professional Divisions, ANS Governance, Local Sections, etc.) as they transition from the role of a student to the role of a professional. It sponsors non-technical workshops and meetings that provide professional development and networking opportunities for young professionals, collaborates with other Divisions and Groups in developing technical and non-technical content for topical and national meetings, encourages its members to participate in the activities of the Groups and Divisions that are closely related to their professional interests as well as in their local sections, introduces young members to the rules and governance structure of the Society, and nominates young professionals for awards and leadership opportunities available to members.
Meeting Spotlight
2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
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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High-temperature plumbing and advanced reactors
The use of nuclear fission power and its role in impacting climate change is hotly debated. Fission advocates argue that short-term solutions would involve the rapid deployment of Gen III+ nuclear reactors, like Vogtle-3 and -4, while long-term climate change impact would rely on the creation and implementation of Gen IV reactors, “inherently safe” reactors that use passive laws of physics and chemistry rather than active controls such as valves and pumps to operate safely. While Gen IV reactors vary in many ways, one thing unites nearly all of them: the use of exotic, high-temperature coolants. These fluids, like molten salts and liquid metals, can enable reactor engineers to design much safer nuclear reactors—ultimately because the boiling point of each fluid is extremely high. Fluids that remain liquid over large temperature ranges can provide good heat transfer through many demanding conditions, all with minimal pressurization. Although the most apparent use for these fluids is advanced fission power, they have the potential to be applied to other power generation sources such as fusion, thermal storage, solar, or high-temperature process heat.1–3
Wilmer A. Coloma, Antonella L. Costa, Claubia Pereira, Clarysson A. M. da Silva
Nuclear Technology | Volume 206 | Number 4 | April 2020 | Pages 554-564
Technical Paper | doi.org/10.1080/00295450.2019.1662668
Articles are hosted by Taylor and Francis Online.
Analysis of the power time series evolution is used to investigate a stable or unstable process after the disturbance in a light water reactor of the boiling water reactor (BWR) type. Several different methodologies are currently used and the uncertainties of the various approaches are in some cases very different. In this work, the time series model known as the Autoregressive Moving Average model was used to calculate the decay ratio (DR), and the natural frequency (NF) due to power oscillations in a BWR. The method consists of locating the appropriate dominant pole of the transfer function. The autoregressive methods are quite often used to study the stability of BWR reactors. In this work the Box-Cox transformation is implemented to stabilize the variances of the power signals in order to maintain the linear assumptions that the calculation of DR and NF needs; that is, to correct biases in the distribution of errors to stabilize the variance and mainly so that the signal approaches a linear behavior. The MATLAB code was used for this purpose. This work also presents a nonlinear analysis of the power series, determining the values of the largest Lyapunov exponents with Rosenstein’s algorithm in order to analyze the stability of the system. The results of the DR and NF calculated by the used methodology are very close to the values obtained in the benchmark.
