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ANS, UCOR sign MOU for workforce development program
The American Nuclear Society and United Cleanup Oak Ridge have signed a memorandum of understanding that establishes a framework for collaboration to advance ANS workforce training and certification programs serving the nuclear industry.
According to the document, UCOR will provide “operational insights and subject matter expertise to inform ANS’s professional development and credentialing offerings, including the Certified Nuclear Professional [CNP] program.” The collaboration will strengthen UCOR’s workforce development efforts while advancing ANS’s mission to sustain and expand the national nuclear workforce pipeline and capabilities.
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.