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Division Spotlight
Human Factors, Instrumentation & Controls
Improving task performance, system reliability, system and personnel safety, efficiency, and effectiveness are the division's main objectives. Its major areas of interest include task design, procedures, training, instrument and control layout and placement, stress control, anthropometrics, psychological input, and motivation.
Meeting Spotlight
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
Commercial nuclear innovation "new space" age
In early 2006, a start-up company launched a small rocket from a tiny island in the Pacific. It exploded, showering the island with debris. A year later, a second launch attempt sent a rocket to space but failed to make orbit, burning up in the atmosphere. Another year brought a third attempt—and a third failure. The following month, in September 2008, the company used the last of its funds to launch a fourth rocket. It reached orbit, making history as the first privately funded liquid-fueled rocket to do so.
Igor A. Bolotnov
Nuclear Technology | Volume 209 | Number 10 | October 2023 | Pages 1405-1413
Review Article | doi.org/10.1080/00295450.2023.2232222
Articles are hosted by Taylor and Francis Online.
The significant progress in the last decade of high-resolution single- and two-phase flow simulations of reactor-relevant flows is summarized in this review paper. The rapid development of high-performance computing capabilities creates exciting opportunities to study complex reactor thermal-hydraulic phenomena. Today’s advances in thermal-hydraulic analysis, interface capturing simulations, and advanced data processing and analysis approaches will help pave the way to the next level of understanding of two-phase flow behavior in nuclear reactors.
This paper discusses two major topics: (1) a brief review of interface-capturing simulations in recent years and (2) several opportunities to advance these numerical research tools in the future. The first part discusses typical computational methods used for these simulations and provides some examples of past work, as well as computational cost estimates and affordability of such simulations for research and industrial applications. In the second part, some specific examples are discussed that could be analyzed using exascale supercomputers being designed and projected to be online in the next several years. New-generation methodologies are required to take full advantage of these capabilities to greatly enhance the scientific understanding of complex two-phase flow phenomena in various conditions relevant to industrial applications.