ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
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.
2023 ANS Annual Meeting
June 11–14, 2023
Indianapolis, IN|Marriott Indianapolis Downtown
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 Journal Issues
Nuclear Science and Engineering
Fusion Science and Technology
Route readiness elements in a large-scale spent nuclear fuel transportation system
The scale and duration of a national campaign to transport spent nuclear fuel (SNF) from commercial nuclear power plants around the United States would be unprecedented. A meticulous level of planning that considers many elements is needed to inspire public confidence and support.
Monday, May 16, 2022|1:30–3:15PM EDT|Fountainview
Massimiliano Fratoni (UC Berkeley)
Nicolas E. Stauff (ANL)
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A Preconceptual Design of an Inverted Stable-Salt Reactor
Cihang Lu (Virginia Commonwealth Univ.), Zeyun Wu (Virginia Commonwealth Univ.)
Neutronic Design and Fuel Cycle Analysis of a Fluoride Salt-Cooled High Temperature Reactor (FHR)
Zuolong Zhu (Ohio State), Dean Wang (Ohio State)
Fast Modular Reactor Nuclear Design Parameters of Fuel Cycle and Power Distributions
Darrin Leer (General Atomics), Hangbok Choi (General Atomics), John Bolin (General Atomics), Alexander Dheming (General Atomics), Oscar Gutierrez (General Atomics)
Presented by Ron Faibish (General Atomics)
Initital Development of a Generic Fluoride Salt-Cooled Reactor Model
Robert F. Kile (Univ. Tennessee, Knoxville), Friederike Bostelmann (ORNL), Steven E. Skutnik (ORNL), William A. Wieselquist (ORNL), Nicholas R. Brown (Univ. Tennessee, Knoxville)
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