ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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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.
2024 ANS Annual Conference
June 9–12, 2024
Las Vegas, NV|The Mirage
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 Sodium Reactor Experiment
In February 1957, construction was completed on the Sodium Reactor Experiment (SRE), a sodium-cooled, graphite-moderated reactor with an output of 20 MWt. The design of theSRE had begun three years earlier in 1954, and construction started in April 1955. On April 25, 1957, the reactor reached criticality, and the SRE operated until February 1964.
Ziping Liu, Yu Ji, Han Zhang, Jun Sun
Nuclear Technology | Volume 208 | Number 8 | August 2022 | Pages 1337-1351
Technical Paper | doi.org/10.1080/00295450.2022.2031498
Articles are hosted by Taylor and Francis Online.
Composite materials are essential in various energy fields owing to their improved heat transfer characteristics. Due to their inhomogeneous structure, it is difficult to obtain the heat transfer details. Effective thermal conductivity (ETC) is an important lumped thermal parameter used to analyze the heat transfer process in composite materials. Existing ETC models are derived by applying a temperature difference (TD) on two opposite boundaries of the composite material to induce heat flow. However, for some composite materials, such as nuclear fuels, the effect of the inner heat source (IHS) is typically ignored. Thus, the suitability of using ETC models based on a TD scheme for composite materials with IHS still requires further investigation. In this study, first the conserved quantities of ETC of the TD and IHS schemes were determined. For normal materials of the TD scheme, the conserved quantity of ETC can be selected as heat flow, whereas for nuclear fuels of the IHS scheme, the average temperatures are recommended as the conserved quantity. Then the general ETC models for composite plate were derived considering both the TD and IHS schemes and special cases with either TD or IHS were also analyzed. Finally, based on the results of this study, the idea of studying the ETC of tristructural-isotropic or TRISO particle-based nuclear fuels is proposed.