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
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
Meeting Spotlight
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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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How to talk about nuclear
In your career as a professional in the nuclear community, chances are you will, at some point, be asked (or volunteer) to talk to at least one layperson about the technology you know and love. You might even be asked to present to a whole group of nonnuclear folks, perhaps as a pitch to some company tangential to your company’s business. So, without further ado, let me give you some pointers on the best way to approach this important and surprisingly complicated task.
Alan J. Markworth
Nuclear Science and Engineering | Volume 49 | Number 4 | December 1972 | Pages 506-507
Technical Notes | doi.org/10.13182/NSE72-A22570
Articles are hosted by Taylor and Francis Online.
A simple model for the gas-diffusion-controlled growth of stationary gas bubbles in an isothermal solid, under constant rate of gas generation, is used to evaluate the temperature dependence of fission-gas swelling in uranium monocarbide. Using experimental data for the temperature-dependent volume diffusivity of xenon in uranium carbide, it is found that the predicted temperature at which the onset of fission-gas swelling occurs, evaluated at a given fission density, correlates relatively well with swelling data and is of the order of one-half the absolute melting point. Variations of bubble concentration and gas-generation rate are found to affect this predicted swelling-onset temperature only to a relatively slight extent.
