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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.
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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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Why should safeguards by design be a global effort?
Jeremy Whitlock
I can’t think of a more exciting time to be working in nuclear, with the diversity of advanced reactor development and increasing global support for nuclear in sustainable energy planning. But we can’t lose sight of the need to plan for efficient international safeguards at the same time.
Global nuclear deployment has been underpinned since 1970 by the Treaty on the Non-Proliferation of Nuclear Weapons (NPT), making it a key customer requirement for governments to demonstrate unequivocally that the technology is not being misused for weapons development.
The International Atomic Energy Agency (IAEA) has helped verify this commitment for more than 50 years, but it has never safeguarded many of the advanced reactors (and related fuel cycle processes) being developed today.
Yong H. Kim, Sung J. Kim, Kune Y. Suh, Joy L. Rempe, F. Bill Cheung, Sang B. Kim
Nuclear Technology | Volume 154 | Number 1 | April 2006 | Pages 13-40
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT06-A3715
Articles are hosted by Taylor and Francis Online.
This paper addresses the pool boiling critical heat flux (CHF) phenomena in one-dimensional inclined rectangular channels by changing the orientation of a copper test heater assembly. In a pool of saturated water at atmospheric pressure, an account is taken of the gap sizes of 1, 2, 5, and 10 mm and the surface orientation angles from the downward-facing position (180 deg) to the vertical position (90 deg). Tests are conducted on the basis of the visualization of boiling phenomena utilizing a high-speed digital camera. In addition, an engineering correlation relating to the CHF near the vertical position is developed anchored in the experimental results. It is observed that the CHF generally decreases as the surface inclination angle increases and as the gap size decreases. In the downward-facing position (180 deg), on the other hand, the vapor escape and liquid refill are accelerated by the squeezing gap so that the CHF tends to increase as the gap size decreases. It is also found that there exists a transition angle, around which the CHF changes with a rapid slope on account of the CHF triggering mechanism differing with the inclination angle.