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 Technology
Fusion Science and Technology
Latest News
NWMO to select Canadian repository site this year
Canada’s Nuclear Waste Management Organization, a not-for-profit organization responsible for the long-term management of the country’s intermediate- and high-level radioactive waste, is set to select a site for a deep geologic repository by the end of the year.
M. E. Sawan, C. S. Aplin, G. Sviatoslavsky, I. N. Sviatoslavsky, A. R. Raffray
Fusion Science and Technology | Volume 52 | Number 4 | November 2007 | Pages 771-775
Technical Paper | Nuclear Analysis and Experiments | doi.org/10.13182/FST07-A1583
Articles are hosted by Taylor and Francis Online.
A blanket concept made of the low electrical conductivity SiCf/SiC composite and utilizing Li17Pb83 as coolant and tritium breeder has been developed and integrated with the magnetic diversion system. Neutronics issues related to tritium breeding adequacy particularly with the area lost to the dump plates at the ring and point cusps were addressed. Radiation damage and lifetime considerations for the SiCf/SiC structural material were also addressed. Another issue of concern is providing adequate shielding for the superconducting cusp magnets. Detailed neutronics analyses show that tritium self-sufficiency can be achieved. A 0.5 m thick water-cooled steel shield that doubles as the vacuum vessel is a reweldable lifetime component and will provide adequate shielding for the magnets.