ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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Division Spotlight
Operations & Power
Members focus on the dissemination of knowledge and information in the area of power reactors with particular application to the production of electric power and process heat. The division sponsors meetings on the coverage of applied nuclear science and engineering as related to power plants, non-power reactors, and other nuclear facilities. It encourages and assists with the dissemination of knowledge pertinent to the safe and efficient operation of nuclear facilities through professional staff development, information exchange, and supporting the generation of viable solutions to current issues.
Meeting Spotlight
2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
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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Nuclear Science and Engineering
June 2025
Nuclear Technology
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Latest News
NRC v. Texas: Supreme Court weighs challenge to NRC authority in spent fuel storage case
The State of Texas has not one but two ongoing federal court challenges to the Nuclear Regulatory Commission that could, if successful, turn decades of NRC regulations, precedent, and case law on its head.
K. R. Merckx
Nuclear Technology | Volume 9 | Number 3 | September 1970 | Pages 309-316
Fuel Element Performance Model | Symposium on Theoretical Models for Predicting In-Reactor Performance of Fuel and Cladding Material | doi.org/10.13182/NT70-A28785
Articles are hosted by Taylor and Francis Online.
A computer program has been developed and used to validate and adjust models for predicting fuel-pin deformations. An existing computer program, DEFORM, was combined with a clad swelling model to be a subroutine for calculating fuel-pin deformations. Predictions of deformations made with this subroutine are compared with measured deformations in a parameter fitting program, SIMPLEX. A comparison of analyses made with this program, using input data collected from experiments on four irradiated fuel pins, indicated that the program version assuming only a clad swelling model predicted the mean deformations of these pins better than the program version assuming both clad swelling and a mechanical interaction between the fuel material and the clad material.