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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.
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2024 ANS Winter Conference and Expo
November 17–21, 2024
Orlando, FL|Renaissance Orlando at SeaWorld
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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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National awards presented at ANS Winter Conference
One of the few constants at American Nuclear Society national meetings is the recognition of exceptional individuals in the nuclear community. ANS President Lisa Marshall has named this season’s award recipients, who received recognition at this week's Winter Conference and Expo in Orlando, Fla.
ANS also announced the winners of awards presented by the Society’s professional divisions. These awards have been mailed to the recipients, and the divisions have recognized or will recognize honorees at various division functions and meetings this fall. The 19 professional divisions of ANS are constituent units and represent a vast array of nuclear science and technology disciplines.
X. Gaus-Liu, A. Miassoedov, J. Foit, T. Cron, F. Kretzschmar, Alexander Palagin, T. Wenz, S. Schmidt-Stiefel
Nuclear Technology | Volume 181 | Number 1 | January 2013 | Pages 216-226
Technical Paper | Special Issue on the 14th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-14) / Fission Reactors; Reactor Safety | doi.org/10.13182/NT13-A15769
Articles are hosted by Taylor and Francis Online.
The LIVE-L4 and LIVE-L5L experiments investigated the thermal-hydraulic behavior of the corium pool in the reactor pressure vessel lower head with the three-dimensional test vessel LIVE. The simulant material is a noneutectic binary mixture of 20% NaNO3-80% KNO3. Transient and steady-state parameters such as melt temperature and heat flux distribution through the vessel wall as well as crust formation characteristics were obtained. The two tests demonstrated that transient events like repeated melt relocation and change of decay power density facilitate crust deformation and change of crust thickness. Massive crust formation in a noneutectic melt pool leads to a change of melt pool composition and a decrease of melt-crust interface temperature. The melt temperature and heat flux at the same pool height and same power density can be roughly compared independent of heating history and initial melt pouring pattern. The dimensionless melt temperature as well as the dimensionless heat flux through the wall during the steady state are independent of power density if the pools have the same height. But, they are dependent on the pool height. For a low pool, the gradients with height of both melt temperature and heat flux through the vessel are larger than those for a high pool.
