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2025 ANS Winter Conference & Expo
November 9–12, 2025
Washington, DC|Washington Hilton
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ANS continues to expand its certificate offerings
It’s almost been a full year since the American Nuclear Society held its inaugural section of Nuclear 101, a comprehensive certificate course on the basics of the nuclear field. Offered at the 2024 ANS Winter Conference and Expo, that first sold-out course marked a massive milestone in the Society’s expanding work in professional development and certification.
Om Pal Singh, P. Bhaskar Rao
Nuclear Technology | Volume 71 | Number 2 | November 1985 | Pages 411-416
Technical Paper | Nuclear Safety | doi.org/10.13182/NT85-A33693
Articles are hosted by Taylor and Francis Online.
The core disruptive accident (CDA) analysis of liquid-metal fast breeder reactors is often performed using the saturated vapor pressure equation of state for the fuel. However, during the transient heating of the fuel in a voided core in the disassembly phase of CDAs, the fuel vapor pressure buildup may lag behind the temperature rise and thus may lead to the delayed disassembly of the core and the consequent large energy release. The formulations for such transient vapor pressure buildup and the results on the dynamics of fuel vapor pressure during the transient heating and its influence on the thermal energy release in a CDA are presented. The energy release calculations have been performed by incorporating the present formalism in the disassembly analysis code VENUS-II. In view of the uncertainties in some of the physical parameters, a parametric study was conducted to evaluate the effects of such uncertainties in their values on the results. These results are discussed in detail.