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Division Spotlight
Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
Meeting Spotlight
ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
Standards Program
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
El Salvador: Looking to nuclear
In 2022, El Salvador’s leadership decided to expand its modest, mostly hydro- and geothermal-based electricity system, which is supported by expensive imported natural gas and diesel generation. They chose to use advanced nuclear reactors, preferably fueled by thorium-based fuels, to power their civilian efforts. The choice of thorium was made to inform the world that the reactor program was for civilian purposes only, and so they chose a fuel that was plentiful, easy to source and work with, and not a proliferation risk.
S. Tina Ghosh, Hossein Esmaili, Alfred Hathaway, Nathan Bixler, Dusty Brooks, Matthew Dennis, Douglas Osborn, Kyle Ross, Kenneth Wagner
Nuclear Technology | Volume 207 | Number 3 | March 2021 | Pages 441-451
Technical Paper | doi.org/10.1080/00295450.2021.1875737
Articles are hosted by Taylor and Francis Online.
This paper provides an overview of the U.S. Nuclear Regulatory Commission’s (NRC’s) project to develop a technical report summarizing the most important insights from its three State-of-the-Art Reactor Consequence Analyses (SOARCA) project uncertainty analyses (UAs). The NRC, with Sandia National Laboratories, has completed three UAs as part of the SOARCA project, for three different operating reactor types in three different locations in the United States. The SOARCA UAs included an integrated evaluation of uncertainty in accident progression, radiological release, and off-site health consequence projections. These three UAs are currently documented in three detailed reports. The NRC is currently developing a technical overview report summarizing the important insights from the three SOARCA UAs. The purpose of the NRC summary is to provide a useful reference for regulatory applications that require the evaluation of off-site consequence risk from beyond-design-basis-event severe accidents. Examples include regulatory and cost-benefit analyses that rely on off-site consequence projections using the MELCOR Accident Consequence Code System (MACCS) code, in conjunction with MELCOR for source term characterization. This paper provides an overview and discusses the overall scope and methodology of the SOARCA UAs and the approach for the summary report currently under development.