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The division's objectives are to promote the advancement of knowledge and understanding of the fundamental physical phenomena characterizing nuclear reactors and other nuclear systems. The division encourages research and disseminates information through meetings and publications. Areas of technical interest include nuclear data, particle interactions and transport, reactor and nuclear systems analysis, methods, design, validation and operating experience and standards. The Wigner Award heads the awards program.
2023 ANS Annual Meeting
June 11–14, 2023
Indianapolis, IN|Marriott Indianapolis Downtown
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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The Civil Nuclear Credit Program: An overview
Officially established on November 15, 2021, with the signing of the $1.2 trillion Infrastructure Investment and Jobs Act—aka the Bipartisan Infrastructure Law, or BIL—the Department of Energy’s Civil Nuclear Credit Program was designed to give owners/operators of commercial U.S. reactors the opportunity to apply for certification and competitively bid on credits to help support the continued operation of economically troubled units. Finally, the federal government, and not just certain farsighted state governments, would recognize nuclear energy for its important grid reliability and decarbonization attributes.
D. Guzonas, F. Brosseau, P. Tremaine, J. Meesungnoen, J.-P. Jay-Gerin
Nuclear Technology | Volume 179 | Number 2 | August 2012 | Pages 205-219
Technical Paper | Nuclear Plant Operations and Control | doi.org/10.13182/NT12-A14093
Articles are hosted by Taylor and Francis Online.
The long-term viability of a supercritical water-cooled reactor (SCWR) will depend on the ability of designers and operators to control and maintain water chemistry conditions that will minimize corrosion and the transport of both corrosion products and radionuclides, at a pressure of 25 MPa and temperatures from 300°C to 625°C. To achieve this goal, the behavior of low concentrations of impurities such as transition metal corrosion products, chemistry control agents, impurities in the feedwater, and radionuclides (fission and activation products) in subcritical and supercritical water must be understood. A second key aspect of SCWR water chemistry control will be mitigation of the effects of water radiolysis. Preliminary studies suggest markedly different behavior than that predicted by extrapolating conventional water-cooled reactor behavior. The principal challenge in predicting corrosion and fission product transport is the lack of thermochemical and kinetic data above 300°C. Calculations with extrapolated data show that the formation of neutral complexes increases with temperature and can become important under near-critical and supercritical conditions. The most important region is from 300°C to 450°C, where the properties of water change dramatically and solvent compressibility effects exert a huge influence on solvation. The potential for increased transport and deposition of corrosion products (radioactive and inactive), leading to increased deposition on fuel cladding surfaces and increased out-of-core radiation fields and worker dose, must be assessed. The commonly used strategy of adding excess hydrogen at concentrations sufficient to suppress the net radiolytic production of primary oxidizing species may not be effective in an SCWR. Because direct measurement of the chemistry under such extreme conditions of temperature, pressure, and radiation fields is difficult, the most promising approach involves a combination of theoretical calculations, chemical models, and experimental work.