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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
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
Christmas Night
Twas the night before Christmas when all through the houseNo electrons were flowing through even my mouse.
All devices were plugged in by the chimney with careWith the hope that St. Nikola Tesla would share.
Glen R. Longhurst, Alex Kratville
Fusion Science and Technology | Volume 66 | Number 3 | November 2014 | Pages 385-393
Technical Paper | doi.org/10.13182/FST14-801
Articles are hosted by Taylor and Francis Online.
A simple laboratory experiment was constructed to demonstrate in a classroom setting hydrogen permeation under conditions typical of some nuclear applications. The goal was to allow students to find both solubility and diffusivity parameters for hydrogen moving through commercial stainless steel tubing. The purpose of the present work is to compare test results from this laboratory experiment with results from others to validate the experiment. Hydrogen mixed with argon was admitted to a heated test chamber containing a coiled Type 316 stainless steel tube. Pure argon sweep gas was passed through the tube to a process-gas mass spectrometer where composition transients of pertinent gas species were recorded. Fits of a theoretical transient model to the experimental data gave values of both diffusivity and solubility of hydrogen in the stainless steel tube. Tests were conducted at hydrogen partial pressures ranging from 1.7 to 83 kPa and tube temperatures from 636 to 770 K. The form of the permeation transient data was fit well by a classical theoretical model. Observed values of diffusivity and solubility of hydrogen in the stainless steel from these transients were similar to literature values with some notable differences. Evidence of permeation delay due to interference by the diluting Ar was observed. Limitations of the experimental system are discussed.