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
Decommissioning & Environmental Sciences
The mission of the Decommissioning and Environmental Sciences (DES) Division is to promote the development and use of those skills and technologies associated with the use of nuclear energy and the optimal management and stewardship of the environment, sustainable development, decommissioning, remediation, reutilization, and long-term surveillance and maintenance of nuclear-related installations, and sites. The target audience for this effort is the membership of the Division, the Society, and the public at large.
Meeting Spotlight
Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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
Jul 2024
Jan 2024
Latest Journal Issues
Nuclear Science and Engineering
August 2024
Nuclear Technology
Fusion Science and Technology
Latest News
BWXT will scout potential TRISO fuel production sites in Wyoming
BWX Technologies Inc. announced today that its Advanced Technologies subsidiary has signed a cooperation agreement with the state of Wyoming to evaluate locations and requirements for siting a potential new TRISO nuclear fuel fabrication facility in the state.
M. R. Louthan, Jr., J. A. Donovan, G. R. Caskey, Jr.
Nuclear Technology | Volume 26 | Number 2 | June 1975 | Pages 192-200
Technical Paper | Material | doi.org/10.13182/NT75-A24418
Articles are hosted by Taylor and Francis Online.
Tritium absorption was determined in Type 304L austenitic stainless steel by analyzing concentration gradients obtained during prolonged exposures to high-pressure gaseous tritium. The calculated tritium diffusivities at temperatures greater than 373 K were shown to be in excellent agreement with the equation where m is the isotopic mass. This equation was previously developed for deuterium in several types of austenitic stainless steels. There was strong evidence for “short-circuit” diffusion paths and a grain size effect on tritium absorption. Such effects are assumed to cause the tritium diffusivities measured for exposures at less than 373 K to be higher than expected from the above equation. Cold work, either prior to or during exposure, significantly increased the effective tritium diffusivity. The increase in tritium diffusivity observed in the samples cold-worked prior to exposure is believed to be caused by preferential (short-circuit) diffusion through strain-induced martensite. The increase in diffusivity in specimens deformed during exposure is believed to be caused by enhanced tritium transport with moving dislocations. This analysis of concentration gradients also shows that tritium permeation rates through austenitic stainless steels will often be significantly less than rates expected from analysis of diffusion-controlled transport properties. This is because of surface barriers that limit tritium absorption, even at pressures to 69 MPa. Solubilities derived from analyses of the concentration gradients were consistently lower than expected and were significantly influenced by specimen surface conditions.