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Division Spotlight
Education, Training & Workforce Development
The Education, Training & Workforce Development Division provides communication among the academic, industrial, and governmental communities through the exchange of views and information on matters related to education, training and workforce development in nuclear and radiological science, engineering, and technology. Industry leaders, education and training professionals, and interested students work together through Society-sponsored meetings and publications, to enrich their professional development, to educate the general public, and to advance nuclear and radiological science and engineering.
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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Survey says . . . Emotional intelligence important in nuclear industry
The American Nuclear Society’s Diversity and Inclusion in ANS (DIA) Committee hosted a workshop social at the 2024 Winter Conference & Expo in November that brought dozens of attendees together for an engaging—and educational—twist on the game show Family Feud.
P. Bhaskar Rao, Om Pal Singh
Nuclear Technology | Volume 75 | Number 2 | November 1986 | Pages 193-195
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT86-A33861
Articles are hosted by Taylor and Francis Online.
An extension of previous work, the study examines the implications of the approximation that the fuel vapor and liquid temperatures remain equal during the transient. Modified mathematical formulations for calculating the transient fuel vapor temperatures separately are provided as well as the results of calculations of the dynamics of fuel vapor pressure buildup during transient heating in voided liquid-metal fast breeder reactor cooling channels by dispensing with the above approximation. The results with and without the approximation are compared with each other. The study indicates that, although the fuel vapor temperatures lag the liquid-fuel temperatures, the fuel vapor pressure buildup is relatively less sensitive to this lag. The use of the above approximation results in an overprediction of the transient vapor pressure by <10%.