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
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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!
Latest Magazine Issues
Apr 2024
Jan 2024
Latest Journal Issues
Nuclear Science and Engineering
May 2024
Nuclear Technology
Fusion Science and Technology
Latest News
X-energy receives federal tax credit for TRISO fuel facility
Advanced reactor company X-energy has been awarded $148.5 million in tax credits under the Inflation Reduction Act for construction of its TRISO-X fuel fabrication facility in Oak Ridge, Tenn.
P. W. Humrickhouse, P. Calderoni, B. J. Merrill
Fusion Science and Technology | Volume 60 | Number 4 | November 2011 | Pages 1564-1567
Interaction with Materials | Proceedings of the Ninth International Conference on Tritium Science and Technology (Part 2) | doi.org/10.13182/FST11-A12732
Articles are hosted by Taylor and Francis Online.
A number of additions have been made to the computational fluid dynamics (CFD) code Fluent in order to model hydrogen permeation. In addition to fluid dynamics, Fluent solves for heat transfer in coupled solid and fluid regions, and solves advection-diffusion equations for scalar quantities such as hydrogen concentration. The latter have been modified with additional code to satisfy Sievert's Law at solid-fluid interfaces and allow for temperature dependent diffusivity and permeability.The method has been employed to model the Tritium Heat Exchanger (THX) experiment at INL, which investigates hydrogen permeation in helium and candidate structural materials for high temperature gas reactor heat exchangers. The Arrhenius law parameters used in Fluent for Inconel 617 are initially determined via a simplified analytical method, and the resulting model predictions compare favorably with experiment data.