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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
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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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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.
Tarcisio Passos Ribeiro de Campos, Aquilino Senra Martinez
Nuclear Science and Engineering | Volume 102 | Number 3 | July 1989 | Pages 211-218
Technical Paper | doi.org/10.13182/NSE89-A27475
Articles are hosted by Taylor and Francis Online.
A new method is proposed for the analytical calculation of resonance integrals. Resonance integrals of infinite cylindric fuel cells are calculated according to a very simple analytical method with a reasonable level of accuracy. An escape probability based on a rational approximation is used to represent the neutron transport among the cell regions. The expression obtained for the resonance integral is a function of the temperature, geometry, and fuel rod composition, as well as the neutron energy. The terms of the expression are combinations of the well-known function J(ξ,β) and its partial derivatives in β. The formulation can be used for all resonance types (narrow, intermediate, and wide). The method parameters depend on the resonance type and can be obtained as a function of a single parameter. For this parameter, a simple expression dependent on the resonance parameters is proposed.
