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Division Spotlight
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.
Meeting Spotlight
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
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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Nuclear Science and Engineering
June 2025
Nuclear Technology
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May 2025
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Industry Update—May 2025
Here is a recap of industry happenings from the recent past:
TerraPower’s Natrium reactor advances on several fronts
TerraPower has continued making aggressive progress in several areas for its under-construction Natrium Reactor Demonstration Project since the beginning of the year. Natrium is an advanced 345-MWe reactor that has liquid sodium as a coolant, improved fuel utilization, enhanced safety features, and an integrated energy storage system, allowing for a brief power output boost to 500-MWe if needed for grid resiliency. The company broke ground for its first Natrium plant in 2024 near a retiring coal plant in Kemmerer, Wyo.
Hans J. Wingender, R. Leicht
Nuclear Technology | Volume 84 | Number 3 | March 1989 | Pages 260-264
Technical Paper | Probabilistic Safety Assessment and Risk Management / Nuclear Safety | doi.org/10.13182/NT89-A34209
Articles are hosted by Taylor and Francis Online.
The modular steady states approach (MSSA) has been developed to meet the particular needs of probabilistic risk assessments (PRAs) of facilities at the back end of the nuclear fuel cycle. Applicability to front-end facilities can be easily achieved by adding appropriate modules. The MSSA is not intended for nuclear power plant PRA. Atmospheric dispersion and subsequent dose assessments have been treated in the conventional manner. They are not part of the MSSA code package STAR developed for use on an IBM AT-PC. The application of MSSA is demonstrated for a high-level waste storage tank facility. The two principal release paths via the tank off-gas system and the cell exhaust-air system have been investigated. It has been found that component failures with negligible consequences are relatively frequent and typical for the off-gas system. The release risk due to failure is of the same order of magnitude as the release risk due to normal operation. Release via the cell exhaust-air system is possible only after a tank leakage and failure to pump the liquid into a reserve tank, resulting in a very low probability but relatively high release.