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Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
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2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
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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
Smarter waste strategies: Helping deliver on the promise of advanced nuclear
At COP28, held in Dubai in 2023, a clear consensus emerged: Nuclear energy must be a cornerstone of the global clean energy transition. With electricity demand projected to soar as we decarbonize not just power but also industry, transport, and heat, the case for new nuclear is compelling. More than 20 countries committed to tripling global nuclear capacity by 2050. In the United States alone, the Department of Energy forecasts that the country’s current nuclear capacity could more than triple, adding 200 GW of new nuclear to the existing 95 GW by mid-century.
A. I. Markin, E. A. Azizov, N. I. Siromyatnikov, V. E. Cherkovets, L. A. Rivkis, A. A. Semenov, I. G. Prikina
Fusion Science and Technology | Volume 54 | Number 2 | August 2008 | Pages 489-492
Technical Paper | Materials Interactions | doi.org/10.13182/FST08-A1860
Articles are hosted by Taylor and Francis Online.
The investigations of the tritium distribution in a surface layer and in the depth of samples using a magnetic microscope were carried out. The dependence of a saturation level in the boundary layer for hydrogen was established from a preliminary examination of samples. Conservation of the tritium distribution profile in the depth of the stainless steel samples after completion of their saturation and cooling was assigned. For Inconel-625 substantial tritium redistribution and release during storage (300K, 15 and 28 months) were experimentally ascertained to a greater degree satisfies the classical characteristics of the diffusion process. The "braking" effect of tritium diffusion was found by preliminary saturation of samples by hydrogen. Research in tritium decontamination effects for samples saturated with tritium with various technological preparation was carried out and essential increase of its efficiency was founded. The experiments emulated a model of technological operation cycle of the thermonuclear reactor.
