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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
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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Smarter waste strategies: Helping deliver on the promise of advanced nuclear
At COP28, held in Dubai in 2023, a clear consensus emerged: Nuclear energy must be a cornerstone of the global clean energy transition. With electricity demand projected to soar as we decarbonize not just power but also industry, transport, and heat, the case for new nuclear is compelling. More than 20 countries committed to tripling global nuclear capacity by 2050. In the United States alone, the Department of Energy forecasts that the country’s current nuclear capacity could more than triple, adding 200 GW of new nuclear to the existing 95 GW by mid-century.
Jacobus J. Hancke, John C. Barry, Gerrit T. Van Rooyen, Johan P. R. De Villiers
Nuclear Technology | Volume 180 | Number 2 | November 2012 | Pages 149-158
Technical Paper | Fission Reactors | doi.org/10.13182/NT12-A14630
Articles are hosted by Taylor and Francis Online.
Coater parameters such as deposition temperature, volume percent of methyltrichlorosilane, and total gas flow were varied to study the effect on the ratio of defective TRISO nuclear fuel particles. The burn-leach test and other leach tests were performed to determine the defect ratio on samples of particles representing these variations. In the narrow ranges that were used, none of these parameters showed any correlation with the burn-leach result. However, a reduction in the density of the directly underlying carbon layer showed a marked increase in the defect ratio of particles. No trend could be observed when the density of the carbon layer was varied in the range of 1.8 to 2 g/cm3 , specified for TRISO particles. But, when the density was reduced to 1.7 and 1.6 g/cm3 , it was seldom possible to produce a batch that did not leach uranium, in spite of having a good quality SiC layer. This indicates that the integrity of the SiC layer is influenced by the quality of the underlying carbon layer. Mechanical damage is proposed as a mechanism responsible for the defective particles that are detected with the leach methods. This mechanism could be the reason for the variations in the leach results. Calculations and some examples show that all defects are not detected with the leach methods, probably because of the limited duration of these tests.