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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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ORAU, ANS, others to host workshops on nuclear academic programs
Oak Ridge Associated Universities (ORAU), in partnership with the American Nuclear Society, the Nuclear Energy Institute, and the Institute for Nuclear Power Operators, has announced it will host an online workshop called “Shaping the Future of Nuclear Academic Programs.” The 90-minute program is designed for university department heads and faculty interested in enhancing nuclear science and technology programs through best practices.
Luciano Burgazzi
Nuclear Technology | Volume 139 | Number 1 | July 2002 | Pages 3-9
Technical Paper | doi.org/10.13182/NT139-3-9
Articles are hosted by Taylor and Francis Online.
This paper deals with the reliability assessment of passive systems that have been developed in recent years by suppliers, industries, utilities, and research organizations, aimed at plant safety improvement and substantial simplification in its implementation. The present study concerns the passive decay heat removal systems that use, for the most part, a condenser immersed in a cooling pool. The focus of the paper is a reliability study of the isolation condenser system foreseen for advanced boiling water reactors (BWRs) for the removal of the excess sensible and core decay heat from the BWR by natural circulation. Furthermore, an approach aimed at the thermal-hydraulic performance assessment (i.e., the natural circulation failure evaluation) from the probability point of view is given. The study is not plant-specific-related but pertains to the conceptual design of the foregoing system.