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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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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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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Nuclear News 40 Under 40 discuss the future of nuclear
Seven members of the inaugural Nuclear News 40 Under 40 came together on March 4 to discuss the current state of nuclear energy and what the future might hold for science, industry, and the public in terms of nuclear development.
To hear more insights from this talented group of young professionals, watch the “40 Under 40 Roundtable: Perspectives from Nuclear’s Rising Stars” on the ANS website.
Benjamin M. Ma, Glenn Murphy
Nuclear Science and Engineering | Volume 20 | Number 4 | December 1964 | Pages 536-546
Technical Paper | doi.org/10.13182/NSE64-A20997
Articles are hosted by Taylor and Francis Online.
The strain and stress distributions resulting from the combined effects of radiation, creep, and neutron flux levels in long externally and internally cooled tubular reactor fuel elements are determined analytically. Primary effects of thermal-cycling growth, irradiation growth, swelling, and creep of the fuel materials under operating conditions of power reactors are taken into consideration. An exact solution of the modified Bessel functions and an approximate solution (using a parabolic function) for neutron flux distribution are obtained from the simple diffusion equations. From the relation that the rate of heat generation is proportional to the neutron flux, the rate of volumetric heat generation in the fuel is found. Then the temperature distribution in the fuel is determined by using Poisson's equation of heat conduction. The equations of the displacement-strain relations, compatibility, incompressibility, stress equilibrium, yield criterion, and boundary conditions are established from some basic assumptions. The strain and stress equations for the fuel elements are derived. From the calculated results of a numerical example, the neutron flux levels, thermal and radiation dilatation, irradiation creep, thickness, and properties of the cladding material are found to have significant influences on the strain and stress distributions produced in the fuel element.