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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.
Myung H. Kim, A. F. Henry
Nuclear Science and Engineering | Volume 103 | Number 3 | November 1989 | Pages 276-282
Technical Paper | doi.org/10.13182/NSE89-A23678
Articles are hosted by Taylor and Francis Online.
Equations for a few-group model applicable to transient analysis are derived from a variational principle made stationary by the continuous-energy P1, equations. Flux-adjoint (bilin-early) weighted few-group parameters result. These can be reduced to the regular flux-spectrum weighted parameters by taking the adjoint spectrum to be constant in energy. Numerical comparisons with multigroup results show that both regular and bilinearly weighted two-group models provide acceptably accurate predictions of transient behavior when realistic pressurized water reactor cases are examined. Although there are still some theoretical questions to be examined, there appears at present to be no reason to employ bilinearly weighted parameters for either static or transient analysis.
