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Accelerator Applications
The division was organized to promote the advancement of knowledge of the use of particle accelerator technologies for nuclear and other applications. It focuses on production of neutrons and other particles, utilization of these particles for scientific or industrial purposes, such as the production or destruction of radionuclides significant to energy, medicine, defense or other endeavors, as well as imaging and diagnostics.
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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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College students help develop waste-measuring device at Hanford
A partnership between Washington River Protection Solutions (WRPS) and Washington State University has resulted in the development of a device to measure radioactive and chemical tank waste at the Hanford Site. WRPS is the contractor at Hanford for the Department of Energy’s Office of Environmental Management.
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.