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Division Spotlight
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
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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Fusion Science and Technology
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.
M. E. Rensink, T. D. Rognlien
Fusion Science and Technology | Volume 67 | Number 1 | January 2015 | Pages 125-141
Technical Paper | doi.org/10.13182/FST14-800
Articles are hosted by Taylor and Francis Online.
Simulations of the heat flux on plasma-facing components from core exhaust plasma are reported for two possible ACT1 divertor configurations. One configuration uses divertor plates strongly inclined with respect to the poloidal magnetic flux surfaces similar to that planned for ITER and results in a partially detached divertor plasma. The second configuration has divertor plates orthogonal to the flux surfaces, which leads to a fully detached divertor plasma if the width of the divertor region is sufficient. Both configurations use scrape-off layer radiation from seeded impurities to yield an acceptable peak heat flux of ∼10 MW/m2 or smaller on the divertor plates and chamber walls. The simulations are performed with the UEDGE two-dimensional transport code to model both plasma and neutral components with some supplementary neutral modeling performed with the DEGAS 2 Monte Carlo code.