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
2027 ANS Winter Conference and Expo
October 31–November 4, 2027
Washington, DC|The Westin Washington, DC Downtown
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
December 2024
Nuclear Technology
Fusion Science and Technology
November 2024
Latest News
Disney World should have gone nuclear
There is extra significance to the American Nuclear Society holding its annual meeting in Orlando, Florida, this past week. That’s because in 1967, the state of Florida passed a law allowing Disney World to build a nuclear power plant.
Neil B. Morley, Albert Medina, Mohamed A. Abdou
Fusion Science and Technology | Volume 56 | Number 1 | July 2009 | Pages 195-200
Tritium, Safety, and Environment | Eighteenth Topical Meeting on the Technology of Fusion Energy (Part 1) | doi.org/10.13182/FST09-A8901
Articles are hosted by Taylor and Francis Online.
Silicon Carbide (SiC) has been proposed as a possible candidate material for flow channel inserts for the dual coolant blanket concept. Here, the total electrical resistance of disks of high purity CVD SiC were measured with liquid lead-lithium eutectic (LLE) alloy melts serving as electrodes. From this data, the relative contributions of intrinsic resistivity and surface contact resistance as a function of measurement temperature was deduced. It was shown that after a relatively short period of exposure, once wetting at the interface was achieved, that contact resistance at the SiC/LLE interface was not significant. The contact resistance during initial exposure did not behave in a repeatable consistent way and appears to be affected by small variations in sample preparation. For modeling purposes, the electrical properties of an FCI can be based on the intrinsic electrical conductivity of the material and the dimensions. However, longer term operations and effects of impurities still need to be addressed.