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Division Spotlight
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
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!
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April 2024
Nuclear Technology
Fusion Science and Technology
February 2024
Latest News
Can hydrogen be the transportation fuel in an otherwise nuclear economy?
Let’s face it: The global economy should be powered primarily by nuclear power. And it probably will by the end of this century, with a still-significant assist from renewables and hydro. Once nuclear systems are dominant, the costs come down to where gas is now; and when carbon emissions are reduced to a small portion of their present state, it will become obvious that most other sources are only good in niche settings. I mean, why use small modular reactors to load-follow when they can just produce that power instead of buffering it?
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.