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Division Spotlight
Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
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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Fusion Science and Technology
Latest News
Ontario eyes new nuclear development
A 1,300-acre site left undeveloped on the shores of Lake Ontario four decades ago could see new life as the home to a large nuclear facility.
Hongjie Zhang, Alice Ying, Mohamed Abdou, Masashi Shimada, Bob Pawelko, Seungyon Cho
Fusion Science and Technology | Volume 72 | Number 3 | October 2017 | Pages 416-425
Technical Paper | doi.org/10.1080/15361055.2017.1333826
Articles are hosted by Taylor and Francis Online.
A mathematical model for permeation of multi-components (H2, T2, HT) through a RAFM (Reduced activation ferritic/martensitic) membrane was described based on kinetic theory. Experimental conditions of tritium permeation for ARAA (Advanced Reduced Activation Alloy) material performed at INL were recreated in simulations for model validation. Both numerical simulations and experimental data indicated that the presence of hydrogen reduces tritium permeation rate significantly in low tritium partial pressure with 1000 ppm (0.1%) hydrogen-helium gas mixture at 1atm. Experimental behavior of tritium permeation flux dependence on tritium isotope partial pressure confirmed the kinetic theory. i.e., it still follows diffusion-controlled, square root dependence, with T2 partial pressures and a linear dependence HT pressure even though it is in a diffusion-controlled regime. In addition, the numerical model was validated with literature data for mono-isotope permeation through oxidized and clean MANET II (MArtensitic for NET) samples under surface-controlled and diffusion-controlled regimes. The simulation results agreed well with the experimental data, which indicated that the mono permeation rate through the oxidized sample is much lower (~2 orders) than clean sample and the permeation rate is proportional to p1 and p0.5 for oxidized and clean MANET II samples, respectively.