ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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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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Nuclear Science and Engineering
June 2024
Nuclear Technology
May 2024
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.
Andrew C. Kauffman, Don W. Miller, Thomas D. Radcliff, Keith W. Maupin, Daniel J. Mills, V. Matthew Penrod
Nuclear Technology | Volume 140 | Number 2 | November 2002 | Pages 222-232
Technical Paper | Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technologies | doi.org/10.13182/NT02-A3335
Articles are hosted by Taylor and Francis Online.
An in-reactor test facility has been designed and built at The Ohio State University Research Reactor to evaluate the static and dynamic performance of nuclear reactor in-core sensors in environmental and neutronic conditions comparable to those expected in a high-temperature gas reactor. The primary objective for design and construction of this facility was to evaluate the performance of prototype constant-temperature power sensors. The facility can test sensors and materials over a wide range of temperatures up to 800°C, over a range of Reynolds numbers that can be varied to evaluate thermal-dynamic response, and at a reasonable neutron flux value that can be oscillated nearly 7% (up to 100 Hz eventually) to deterministically evaluate sensor transfer functions. Testing has demonstrated that this facility safely performs its desired functions with the current limitation of a 50-Hz maximum neutron flux oscillation speed.