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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.
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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Latest News
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.
Christopher R. Hughes, Oswaldo Pelaez, Duwayne Schubring, Kelly A. Jordan
Nuclear Technology | Volume 190 | Number 3 | June 2015 | Pages 292-300
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT14-74
Articles are hosted by Taylor and Francis Online.
This work concerns the comparison of supercritical water reactor (SCWR) assembly designs using coupled reactor physics and thermal-hydraulic methods. In the SCWR, large density gradients in the supercritical water (used as coolant and moderator) will require detailed multiphysics analysis. The Super Light Water Reactor (SLWR) was analyzed previously [Hughes et al., Nucl. Eng. Des., Vol. 270 (2014)], where MCNP5 was coupled with density and temperature results from a single-channel code. MCNP5 then provided the single-channel code with a linear heat profile. In the present work, that proposed assembly design is determined to have a negative density coefficient of reactivity. Two alternate designs with different geometries and water-to-fuel ratios are presently considered to address this issue. It is found that adding an additional row of pins is more effective at producing a positive density coefficient than is reducing the size of the moderator boxes.