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Mathematics & Computation
Division members promote the advancement of mathematical and computational methods for solving problems arising in all disciplines encompassed by the Society. They place particular emphasis on numerical techniques for efficient computer applications to aid in the dissemination, integration, and proper use of computer codes, including preparation of computational benchmark and development of standards for computing practices, and to encourage the development on new computer codes and broaden their use.
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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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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Latest News
X-energy, Dow apply to build an advanced reactor project in Texas
Dow and X-energy announced today that they have submitted a construction permit application to the Nuclear Regulatory Commission for a proposed advanced nuclear project in Seadrift, Texas. The project could begin construction later this decade, but only if Dow confirms “the ability to deliver the project while achieving its financial return targets.”
Joshua Kaizer
Nuclear Technology | Volume 190 | Number 1 | April 2015 | Pages 65-71
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT14-38
Articles are hosted by Taylor and Francis Online.
Empirical models are applicable over limited ranges of their predictor variables. The space defined by those ranges, the application domain, is the entire space over which the empirical model is applied. One important assumption is that the model’s predictive behavior is consistent over the entire application domain. This assumption is commonly made for critical heat flux (CHF) models when they are applied in reactor safety analysis. The intention of this work is to demonstrate that the current assessment methods used to justify this assumption may not always identify subregions in the application domain where the model’s predictive capability is degraded. This is accomplished by intentionally placing a nonconservative subregion in a CHF model and demonstrating that the current assessment methods are unable to identify that nonconservative subregion. As the existence of a nonconservative subregion may impact reactor safety analysis, a new method is proposed that does identify the nonconservative subregion. This new method is a multidimensional approach capable of demonstrating if the CHF model’s predictive behavior is likely due to random effects or is due to a degraded predictive capability in a given subregion.