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
Mathematics & Computation
Division members promote the advancement of mathematical and computational methods for solving problems arising in all disciplines encompassed by the Society. They place particular emphasis on numerical techniques for efficient computer applications to aid in the dissemination, integration, and proper use of computer codes, including preparation of computational benchmark and development of standards for computing practices, and to encourage the development on new computer codes and broaden their use.
Meeting Spotlight
Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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
Jul 2024
Jan 2024
Latest Journal Issues
Nuclear Science and Engineering
August 2024
Nuclear Technology
Fusion Science and Technology
Latest News
ARPA-E announces $40 million to develop transmutation technologies for UNF
The Department of Energy’s Advanced Research Projects Agency–Energy (ARPA-E) announced $40 million in funding to develop cutting-edge technologies to enable the transmutation of used nuclear fuel into less-radioactive substances. According to ARPA-E, the new initiative addresses one of the agency’s core goals as outlined by Congress: to provide transformative solutions to improve the management, cleanup, and disposal of radioactive waste and spent nuclear fuel.
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.