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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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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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
Norway’s Halden reactor takes first step toward decommissioning
The government of Norway has granted the transfer of the Halden research reactor from the Institute for Energy Technology (IFE) to the state agency Norwegian Nuclear Decommissioning (NND). The 25-MWt Halden boiling water reactor operated from 1958 to 2018 and was used in the research of nuclear fuel, reactor internals, plant procedures and monitoring, and human factors.
Yoshikazu Tamauchi, Takashi Miyata, Kazumi Takebe, Yoshiaki Hayashi, Shingo Matsuoka, Kazuya Hayashi, Katsuya Kurosu
Nuclear Technology | Volume 181 | Number 2 | February 2013 | Pages 303-316
Technical Paper | Reactor Safety/Reprocessing | doi.org/10.13182/NT13-A15785
Articles are hosted by Taylor and Francis Online.
In a reprocessing plant, the various and many accidents identified related to mechanical processes, chemical processes, and storage facilities have to be assessed to know the total risk of the plant. To assess the individual risks of so many potential accidents efficiently and effectively, we have developed a simplified quantitative method called quantitative safety assessment (QSA), based on our experience in probabilistic risk assessment (PRA) for the Rokkasho Reprocessing Plant and with reference to the integrated safety analysis used in the United States for fuel cycle facilities. Our method not only includes such PRA features as quantifiability of the results and comparability of risk importance of the contributors to accident sequences but also offers the new features of simplified presentation and easy traceability. The designation of important safety structures, systems, components, and personnel activities is thus facilitated through the use of the results of this method. In this paper, the deployment of the QSA method is demonstrated using an example of a criticality accident in a plutonium partition process.
