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Division Spotlight
Reactor Physics
The division's objectives are to promote the advancement of knowledge and understanding of the fundamental physical phenomena characterizing nuclear reactors and other nuclear systems. The division encourages research and disseminates information through meetings and publications. Areas of technical interest include nuclear data, particle interactions and transport, reactor and nuclear systems analysis, methods, design, validation and operating experience and standards. The Wigner Award heads the awards program.
Meeting Spotlight
ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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Candidates for leadership provide statements: ANS Board of Directors
With the annual ANS election right around the corner, American Nuclear Society members will be going to the polls to vote for a vice president/president-elect, treasurer, and members-at-large for the Board of Directors. In January, Nuclear News published statements from candidates for vice president/president-elect and treasurer. This month, we are featuring statements from each nominee for the Board of Directors.
C. William Savery, Y. S. Huang, George M. Kowal
Nuclear Technology | Volume 27 | Number 3 | November 1975 | Pages 327-336
Technical Paper | Reactor | doi.org/10.13182/NT75-A24308
Articles are hosted by Taylor and Francis Online.
A computer code, MNODE, for predicting the state histories and inventories of an inert gas and water liquid and vapor flowing in a zoned containment has been developed. It employs a model that describes the unsteady flow and thermodynamics of two-phase two-component mixtures flowing among 12 connected control volumes. This calculational model can be applied to problems of hypothetical high-pressure primary coolant, feed water, or steam line ruptures in such structures as nuclear containments, tunnels, or auxiliary buildings. In comparison with previously reported zoned containment computation models, this model rigorously treats the thermodynamics of two-phase two-component mixtures of water and an inert gas, is provided with several flow model options including an inertia flow equation, and is demonstrated with substantial verification. Predictions are compared with the results of an analytical gas dynamic problem, semiscale blowdown experiments, and solutions to a subcompartment analysis standard problem by other computer codes in use within the nuclear industry.