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Nuclear Installations Safety
Devoted specifically to the safety of nuclear installations and the health and safety of the public, this division seeks a better understanding of the role of safety in the design, construction and operation of nuclear installation facilities. The division also promotes engineering and scientific technology advancement associated with the safety of such facilities.
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Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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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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Christmas Night
Twas the night before Christmas when all through the houseNo electrons were flowing through even my mouse.
All devices were plugged in by the chimney with careWith the hope that St. Nikola Tesla would share.
S. Reyes, J. F. Latkowski, J. Gomez del Rio, J. Sanz
Fusion Science and Technology | Volume 39 | Number 2 | March 2001 | Pages 941-945
Safety and Environment | doi.org/10.13182/FST01-A11963361
Articles are hosted by Taylor and Francis Online.
SOMBRERO (solid moving breeder reactor) is a conceptual design of a 1000 MWe laser-driven inertial fusion energy (IFE) power plant. An important goal of the original study was the achievement of a safe and environmentally attractive reactor of relatively simple design. However, recent work has pointed out some key issues involving safety that were not completely addressed at that time, and which need to be reviewed in order to maximize the SOMBRERO design attractiveness.
The present work uses a set of computer codes traditionally used for magnetic fusion safety studies (CHEMCON, MELCOR), which have been adopted and adapted for use in IFE safety analysis. Here we consider a loss of flow accident (LOFA) combined with a simultaneous loss of vacuum accident (LOVA) produced by a breach in the confinement building. Although confinement failure would be a very unlikely event, it must be postulated in order to produce significant off-site doses. The CHEMCON code is used to simulate the long-term thermal transient in the reactor structures resulting from oxidation and radioactive decay heat. MELCOR is used to simulate a wide range of physical phenomena including thermal-hydraulics, heat transfer, aerosol physics and fusion product release and transport. As specified in the DOE Fusion Safety Standards, an off-site dose below 1 rem (10 mSv) is the requirement to avoid public sheltering and evacuation. The SOMBRERO accident analysis results will be evaluated according to this limit and suggestions will be made for improvements and future work.