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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.
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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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
Securing the advanced reactor fleet
Physical protection accounts for a significant portion of a nuclear power plant’s operational costs. As the U.S. moves toward smaller and safer advanced reactors, similar protection strategies could prove cost prohibitive. For tomorrow’s small modular reactors and microreactors, security costs must remain appropriate to the size of the reactor for economical operation.
Binh T. Pham, Grant L. Hawkes, Jeffrey J. Einerson
Nuclear Technology | Volume 196 | Number 2 | November 2016 | Pages 396-407
Technical Paper | doi.org/10.13182/NT16-31
Articles are hosted by Taylor and Francis Online.
This paper presents the quantification of uncertainty of the calculated temperature data for the Advanced Gas Reactor (AGR) fuel irradiation experiments conducted in the Advanced Test Reactor at Idaho National Laboratory in support of the Advanced Reactor Technologies Fuel Development and Qualification Program. The predicted temperatures with associated uncertainty for AGR tests using the ABAQUS finite element heat transfer code are used to validate the fission product transport and fuel performance simulation models. To quantify the uncertainty of calculated temperatures, this study identifies and analyzes model parameters of potential importance to the predicted fuel temperatures. The selection of input parameters for uncertainty quantification is based on the ranking of their influence on the variation of temperature predictions. Thus, selected input parameters include those with high sensitivity and those with large uncertainty. The propagation of model parameter uncertainty and sensitivity is then used to quantify the overall uncertainty of the calculated temperatures. The sensitivity analysis performed in this work went beyond the traditional local sensitivity. Using an experimental design, an analysis of pairwise interactions of model parameters was performed to establish the sufficiency of the first-order (linear) expansion terms in constructing the response surface. To achieve completeness, the uncertainty propagation made use of pairwise noise correlations of model parameters. The AGR-2 overall fuel temperature uncertainties reported here are less than 5% (or 60°C).