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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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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.
B. P. McGrail
Nuclear Technology | Volume 75 | Number 2 | November 1986 | Pages 168-186
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT86-A33859
Articles are hosted by Taylor and Francis Online.
Interactive leaching experiments were performed with Savannah River 165 defense waste glass at 90°C in a low-magnesium salt brine (∼100 mg/ℓ) with various amounts of steel present to simulate interactions between the metal container and the glass. Synergistic interactions occurred between the container material and the glass, which increased the glass dissolution rate. Measured quasi-steady-state solution concentrations of 239Pu, 237Np, and 243Am were reasonably consistent with published solubilities for the respective oxides. Decreasing 238U concentrations were observed with increasing solution pH, inconsistent with the behavior of uranyl carbonates that presumably predominate at the slightly alkaline pH of the tests. Uranium and plutonium formed pseudocolloids with hematite particles that rapidly formed during the tests. Particle size measurements showed the median size to be >5 μm in diameter.