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Division Spotlight
Young Members Group
The Young Members Group works to encourage and enable all young professional members to be actively involved in the efforts and endeavors of the Society at all levels (Professional Divisions, ANS Governance, Local Sections, etc.) as they transition from the role of a student to the role of a professional. It sponsors non-technical workshops and meetings that provide professional development and networking opportunities for young professionals, collaborates with other Divisions and Groups in developing technical and non-technical content for topical and national meetings, encourages its members to participate in the activities of the Groups and Divisions that are closely related to their professional interests as well as in their local sections, introduces young members to the rules and governance structure of the Society, and nominates young professionals for awards and leadership opportunities available to members.
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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Nuclear Science and Engineering
August 2024
Nuclear Technology
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Latest News
Four million nuclear jobs by 2050: Who will do them?
Industry leaders from around the globe met this month to discuss the talent development that will be necessary for the long-term success of the nuclear industry.
The International Conference on Nuclear Knowledge Management and Human Resources Development, hosted by the International Atomic Energy Agency, was held in Vienna earlier this month. Discussed there was the agency’s forecast for nuclear capacity to more than double—or hopefully triple—by 2050 and the requirement of more than four million professionals to support the industry.
Heinz Nabielek, Werner Schenk, Werner Heit, Alfred-Wilhelm Mehner, Daniel T. Goodin
Nuclear Technology | Volume 84 | Number 1 | January 1989 | Pages 62-81
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT89-A34196
Articles are hosted by Taylor and Francis Online.
Coated particles embedded in graphitic elements are the fuel for the High-Temperature Reactor (HTR). Experimental investigations of the performance of particles at extremely high temperatures have been conducted to achieve an understanding of coating failure mechanisms and to establish the data base for safety and risk analyses of hypothetical accidents in large-and medium-sized HTRs. The primary mechanism for coating failure and fission product release in the 1900 to 2500°C temperature range is thermal decomposition of silicon carbide (SiC). Heating tests have provided the activation energy of this process and the correlation of SiC decomposition with coating failure and subsequent fission product release. The process of fission product release proceeds in several stages. A certain amount of SiC removal at high temperatures leads to SiC deterioration, which renders a fraction of particles permeable to cesium and strontium. During 50°C/h ramped heating tests, the cesium release approaches 100% at 2500°C. With the onset of SiC failure, the release process of xenon, krypton, and iodine via diffusion through the pyrocarbon (PyC) is initiated. Under all heating conditions examined, krypton release is significantly delayed relative to cesium release due to the higher diffusivity of cesium in PyC. In the intermediate temperature range of 1600 to 1700°C (the maximum temperature in small, modular HTRs), SiC decomposition rates are negligible, and coated particle fuels retain all safety-relevant fission products.