ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
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
Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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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Jul 2024
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Nuclear Science and Engineering
August 2024
Nuclear Technology
Fusion Science and Technology
Latest News
BWXT will scout potential TRISO fuel production sites in Wyoming
BWX Technologies Inc. announced today that its Advanced Technologies subsidiary has signed a cooperation agreement with the state of Wyoming to evaluate locations and requirements for siting a potential new TRISO nuclear fuel fabrication facility in the state.
S.D. Harkness, J. A. Tesk, Che-Yu Li
Nuclear Technology | Volume 9 | Number 1 | July 1970 | Pages 24-30
Fuel Cladding Model | Symposium on Theoretical Models for Predicting In-Reactor Performance of Fuel and Cladding Material | doi.org/10.13182/NT70-A28724
Articles are hosted by Taylor and Francis Online.
A model has been developed for the evolution of voids and dislocation loops during fast neutron irradiation of austenitic stainless steel. The model is based on a thermodynamic approach that calculates void nucleation and growth rates in terms of the supersaturation of vacancies and interstitials. It is recognized that the steady-state point-defect concentrations decrease with fluence as the result of the creation of additional sinks (voids and loops). The ability to monitor both the microstructural development and the steady-state concentrations of defects allows discussion of the in-pile mechanical properties. The yield strength of austenitic stainless steel is expected to increase rapidly during irradiation at 400°C due to the effectiveness of voids and dislocation loops as obstacles to dislocation motion. Irradiation at 600°C is predicted to result in a slowly increasing yield strength. In-reactor creep behavior is discussed in terms of a climb-controlled model for a dispersion strengthened system. Radiation-enhanced climb is expected to predominate at lower temperatures and stresses over the thermal climb component. Discussion of the possible effects of neutron flux and fluence on the in-pile steady-state creep rate is also included.