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
Operations & Power
Members focus on the dissemination of knowledge and information in the area of power reactors with particular application to the production of electric power and process heat. The division sponsors meetings on the coverage of applied nuclear science and engineering as related to power plants, non-power reactors, and other nuclear facilities. It encourages and assists with the dissemination of knowledge pertinent to the safe and efficient operation of nuclear facilities through professional staff development, information exchange, and supporting the generation of viable solutions to current issues.
Meeting Spotlight
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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
January 2025
Nuclear Technology
Fusion Science and Technology
Latest News
Christmas Night
Twas the night before Christmas when all through the houseNo electrons were flowing through even my mouse.
All devices were plugged in by the chimney with careWith the hope that St. Nikola Tesla would share.
H. Zhang, A. Ying, M. Abdou
Fusion Science and Technology | Volume 64 | Number 3 | September 2013 | Pages 651-656
Test Blanket, Fuel Cycle, and Breeding | Proceedings of the Twentieth Topical Meeting on the Technology of Fusion Energy (TOFE-2012) (Part 2) Nashville, Tennessee, August 27-31, 2012 | doi.org/10.13182/FST12-579
Articles are hosted by Taylor and Francis Online.
A SiC-based flow channel insert (FCI) is used as an electrical and thermal insulator in the Dual Coolant Lead Lithium (DCLL) blanket. To reduce the stress of the FCI structural material, the pressure equalization slot (PES) is implemented in the FCI wall. However, the PES affects the tritium transfer behavior and loss rate. Therefore it is important to examine the tritium loss rate and ensure it remains below an allowable limit. In the present study, we analyze tritium transport and quantify the tritium loss rate in a front duct of the DCLL-type outboard blanket where PbLi moves poloidally. Three types of poloidal ducts have been considered: one without the PES, one with the PES in the wall parallel to the magnetic field and one with the PES in the wall perpendicular to the magnetic field. Tritium concentration fields are obtained by solving a fully 3-D problem with appropriate boundary conditions at various interfaces. Results show a high tritium concentration at the location of reversed flow when a PES was located in the wall parallel to the field. Furthermore, when any PES was introduced, the PES changed the velocity profiles and thus changed the tritium concentrations in the core and gaps, which increases the tritium losses from 1.244% to 1.413% under the calculation conditions.