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
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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
Jun 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
August 2025
Nuclear Technology
July 2025
Fusion Science and Technology
Latest News
DOE opens pilot program to authorize test reactors outside national labs
Details of the plan to test new reactor concepts under the Department of Energy’s authority but outside national laboratory boundaries—first outlined in one of the four executive orders on nuclear energy released on May 23—were just released in a request for applications issued by the DOE.
M. J. Pattison, S. Smolentsev, R. Munipalli, M. A. Abdou
Fusion Science and Technology | Volume 60 | Number 2 | August 2011 | Pages 809-813
Computational Tools, Modeling & Validation | Proceedings of the Nineteenth Topical Meeting on the Technology of Fusion Energy (TOFE) (Part 2) | doi.org/10.13182/FST10-309
Articles are hosted by Taylor and Francis Online.
In a Dual-Coolant Lead-Lithium (DCLL) blanket, tritium losses from the PbLi into cooling helium streams may occur when the liquid-metal breeder is moving in the poloidal ducts. Quantitative analysis of the mass transfer processes associated with the tritium transport in the breeder as well as tritium diffusion through the structural and functional materials is important for two main reasons. The first is that there can be a substantial cost in extracting tritium from helium. The second is that tritium can make its way from the helium stream into the environment. In the present study, we analyze tritium transport in the front section of the DCLL DEMO-type Outboard blanket, where PbLi moves poloidally in a rectangular duct with an insulating flow channel insert (FCI) in the presence of a strong plasma-confining magnetic field. This involves two steps, the computation of the flow field with an MHD code, followed by the solution of the mass transfer equation with a newly-developed transport code CATRYS. The analyses included a sensitivity study to investigate how uncertainties in the properties of the materials (diffusion coefficient, solubility constant) affect the results and to assess the effect of an impervious crystalline sealing layer on the FCI.