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Aerospace Nuclear Science & Technology
Organized to promote the advancement of knowledge in the use of nuclear science and technologies in the aerospace application. Specialized nuclear-based technologies and applications are needed to advance the state-of-the-art in aerospace design, engineering and operations to explore planetary bodies in our solar system and beyond, plus enhance the safety of air travel, especially high speed air travel. Areas of interest will include but are not limited to the creation of nuclear-based power and propulsion systems, multifunctional materials to protect humans and electronic components from atmospheric, space, and nuclear power system radiation, human factor strategies for the safety and reliable operation of nuclear power and propulsion plants by non-specialized personnel and more.
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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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Argonne’s METL gears up to test more sodium fast reactor components
Argonne National Laboratory has successfully swapped out an aging cold trap in the sodium test loop called METL (Mechanisms Engineering Test Loop), the Department of Energy announced April 23. The upgrade is the first of its kind in the United States in more than 30 years, according to the DOE, and will help test components and operations for the sodium-cooled fast reactors being developed now.
M. Levenson, F. Rahn
Nuclear Technology | Volume 53 | Number 2 | May 1981 | Pages 99-110
Technical Paper | Realistic Estimates of the Consequences of Nuclear Accident / Nuclear Safety | doi.org/10.13182/NT81-A32614
Articles are hosted by Taylor and Francis Online.
In estimating the real risk to the public from an accident at a nuclear power plant, several quantities are important: the probability and consequence of the accident itself and the risk resulting from any mitigating action taken. The uncertainties of the risk associated with the accident seem to be dominated by the uncertainties of the consequence estimates. The current procedure of using “conservative” assumptions (usually at each stage) in the calculations produces an estimate of the risk that is likely to be much too high (by as much as an order of magnitude or more). In and of themselves, conservative estimates as typically made in the licensing process may in fact contribute additional risk by overestimating source terms and thus overestimating benefits of activities such as evacuation. This process, in turn, leads inadvertently to putting major segments of society at greater risk than is necessary by encouraging decisions that have higher risk. The principal areas of concern focus on the treatment of a number of physical processes. These processes are always operative and can be counted on to limit the consequences of a reactor accident. Sufficient credit is not taken for their ability to reduce the release of radioactivity and confine it relatively close to its source. Estimates of risk will improve in direct proportion to improvements in quantification of these phenomena. Empirical evidence from many sources shows that these processes are indeed operative and very efficient in reducing the release of radioactivity. As a result, the policy decisions based on the source term in the event of a major reactor accident must be reassessed.