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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 Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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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Latest News
Securing the advanced reactor fleet
Physical protection accounts for a significant portion of a nuclear power plant’s operational costs. As the U.S. moves toward smaller and safer advanced reactors, similar protection strategies could prove cost prohibitive. For tomorrow’s small modular reactors and microreactors, security costs must remain appropriate to the size of the reactor for economical operation.
Douglas W. Stamps
Nuclear Science and Engineering | Volume 128 | Number 3 | March 1998 | Pages 243-269
Technical Paper | doi.org/10.13182/NSE98-A1954
Articles are hosted by Taylor and Francis Online.
The CONTAIN code was used to predict the helium concentrations, gas temperatures and pressures, and wall temperatures of four experiments performed in the NUPEC 1/4-scale model containment. These experiments investigated the thermal-hydraulic effects of helium and steam source flow rates, source elevation, and internal water sprays. Two CONTAIN flow solvers and two nodalization schemes were assessed. One NUPEC test, International Standard Problem 35, was investigated in detail, including the pretest heating phase. The thermal hydraulics of this test were dominated by internal water sprays. A modeling approach based on the assumption that the water sprays generated a large air vortex yielded the best results. Reasons for deviations between the predictions and data are suggested based on experimental uncertainties, different analysis methods, and nodalization schemes.