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Division Spotlight
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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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
Standards Program
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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Molten salt research is focus of ANS local section presentation
The American Nuclear Society’s Chicago–Great Lakes Local Section hosted a presentation on February 27 on developments at the molten salt research reactor at Abilene Christian University’s Nuclear Energy Experimental Testing (NEXT) Lab.
A recording of the presentation is available on the ANS website.
C. F. Bonilla, J. S. Busch, H. G. Landau, L. L. Lynn
Nuclear Science and Engineering | Volume 9 | Number 3 | March 1961 | Pages 323-331
Technical Paper | doi.org/10.13182/NSE61-A25883
Articles are hosted by Taylor and Francis Online.
The development and compilation of formal solutions to heat transfer problems which occur in reactor design is an important phase of reactor engineering. Formal analytical solutions are useful both for making first approximations and as a check of more detailed work. Three solutions to three different cases of transient heat transfer in a conduit cooled on the inside by a flowing coolant are presented. The heat transfer mechanism is described by a pair of coupled partial differential equations applicable to nuclear reactor design and analysis. The first solution is for the case of coolant flowing at constant velocity through a conduit with internal heat generation a function of distance. The heat transfer coefficient from conduit to coolant is infinite for transfer so that the conduit and coolant temperatures are always equal. The coolant inlet temperature varies with time. All physical properties of the coolant and conduit are taken as constant. Four specific sets of conditions are considered. In the second case the coolant inlet temperature is constant, the heat transfer coefficient is infinite, the internal heat generation is a function of distance, and the coolant velocity decreases with time, as on loss of pumping power. Three specific sets of conditions are considered. The third case is the same problem as case one except that the heat transfer coefficient between the conduit and coolant is finite.