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Division Spotlight
Isotopes & Radiation
Members are devoted to applying nuclear science and engineering technologies involving isotopes, radiation applications, and associated equipment in scientific research, development, and industrial processes. Their interests lie primarily in education, industrial uses, biology, medicine, and health physics. Division committees include Analytical Applications of Isotopes and Radiation, Biology and Medicine, Radiation Applications, Radiation Sources and Detection, and Thermal Power Sources.
Meeting Spotlight
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver 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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Latest News
ANS designates Armour Research Foundation Reactor as Nuclear Historic Landmark
The American Nuclear Society presented the Illinois Institute of Technology with a plaque last week to officially designate the Armour Research Foundation Reactor a Nuclear Historic Landmark, following the Society’s decision to confer the status onto the reactor in September 2024.
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.