ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
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!
Latest Magazine Issues
May 2024
Jan 2024
Latest Journal Issues
Nuclear Science and Engineering
June 2024
Nuclear Technology
Fusion Science and Technology
Latest News
Proving DRACO will deliver
The United States is now closer than it has been in over five decades to launching the first nuclear thermal rocket into space, thanks to DRACO—the Demonstration Rocket for Agile Cislunar Orbit.
Liang Shi, J. Michael Doster, Charles W. Mayo
Nuclear Technology | Volume 129 | Number 3 | March 2000 | Pages 338-355
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT00-A3066
Articles are hosted by Taylor and Francis Online.
An experimental research program into the loose part damage process identified important mechanisms that govern accumulated loose part damage to steam generator tube sheets. Relationships were developed to quantify damage due to single and multiple impacts, including such effects as tube end open diameter reduction and tube end contour deformation. These experimental investigations have led to the development of a computational model for estimating loose part impact damage on steam generator tube ends. Comparisons to experimental data show the loose part damage model to be a good approximation of actual loose part impact damage and provide a convenient and quantitative linkage between loose part impact properties and damage. Impact damage effects are local effects that depend only on the single impacts and impact overlaps in a small region of interest. The damage can be directly related to local impact density. Since in general the local impact density on a steam generator tube sheet is unknown, a model developed to simulate loose part impact distributions as a function of operating conditions is described.