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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
2024 ANS Winter Conference and Expo
November 17–21, 2024
Orlando, FL|Renaissance Orlando at SeaWorld
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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Industry experts discuss nuclear’s role in powering data centers, meeting climate goals
As a primer to the American Nuclear Society Winter Conference and Expo, ANS Executive Director/Chief Executive Craig Piercy hosted a panel discussion titled “The State of Nuclear,” sponsored by the ANS Trustees of Nuclear. The October 29 discussion, the first in a two-part series, featured five thought leaders from the nuclear community as they reviewed the current state of nuclear power. The second panel took place during the ANS Winter Conference in Orlando, Fla., on November 18.
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.