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Isotopes & Radiation
Members are devoted to applying nuclear science and engineering technologies involving isotopes, radiation applications, and associated equipment in scientific research, development, and industrial processes. Their interests lie primarily in education, industrial uses, biology, medicine, and health physics. Division committees include Analytical Applications of Isotopes and Radiation, Biology and Medicine, Radiation Applications, Radiation Sources and Detection, and Thermal Power Sources.
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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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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Glass strategy: Hanford’s enhanced waste glass program
The mission of the Department of Energy’s Office of River Protection (ORP) is to complete the safe cleanup of waste resulting from decades of nuclear weapons development. One of the most technologically challenging responsibilities is the safe disposition of approximately 56 million gallons of radioactive waste historically stored in 177 tanks at the Hanford Site in Washington state.
ORP has a clear incentive to reduce the overall mission duration and cost. One pathway is to develop and deploy innovative technical solutions that can advance baseline flow sheets toward higher efficiency operations while reducing identified risks without compromising safety. Vitrification is the baseline process that will convert both high-level and low-level radioactive waste at Hanford into a stable glass waste form for long-term storage and disposal.
Although vitrification is a mature technology, there are key areas where technology can further reduce operational risks, advance baseline processes to maximize waste throughput, and provide the underpinning to enhance operational flexibility; all steps in reducing mission duration and cost.
B. Laponche, M. Brunet, Y. Bouedo
Nuclear Science and Engineering | Volume 48 | Number 3 | July 1972 | Pages 305-318
Technical Paper | doi.org/10.13182/NSE72-A22488
Articles are hosted by Taylor and Francis Online.
A method is described for the analysis of oscillation measurements in critical assemblies where fissions are produced predominantly by thermal neutrons. The oscillation method developed in the CEA deals with the measurement of two signals: the “global” signal, which gives a representation of the sample reactivity, and the “local” signal, which gives the variation of the neutron density at the vicinity of the sample. Using a double calibration of the reactor by samples of enriched or depleted uranium and boronated uranium, it is possible to obtain independently the absorption and production reaction rates for plutonium in each sample, as a function of 235U reaction rates. The equivalent sample method is a more recent development and is based on the fact that a given perturbation of the absorption cross section, with any law of variation with energy in the thermal region, can be replaced by an absorption of well-known variation with energy which has the same effect on the neutronic density in the reactor beyond a small distance where spectrum effects are still appreciable. A series of measurements of uranium/plutonium rods performed in the CESAR reactor, from 20 to 400°C, is analyzed, and modifications of the absorption and fission cross sections of plutonium isotopes are proposed.