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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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.
Thursday, May 19, 2022|10:15AM–12:00PM EDT|Ellwood
Nathan J. Roskoff
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Reduced Order Modeling of Neutron Transport Using Monte Carlo Simulations with Matrix Sketching
Christophe Murphy (Jacobs), David P. Griesheimer (Naval Nuclear Laboratory)
Alpha-Eigenvalue Monte Carlo Neutron Transport Calculations with SCONE
Saad Islam (Univ. Cambridge), Paul Cosgrove (Univ. Cambridge), Valeria Raffuzzi (Univ. Cambridge)
A Programmatic Metamodel-Driven Modeling Paradigm for MCNP
Peter J. Kowal (Rensselaer Polytechnic Institute), Camden E. Blake (Rensselaer Polytechnic Institute), Kurt A. Dominesey (Rensselaer Polytechnic Institute), Wei Ji (Rensselaer Polytechnic Institute)
A Monte Carlo Transient Multilevel Implementation Applied to the C5G7-TD3 Benchmark
Evan S. Gonzalez (Univ. Michigan), Brian C. Kiedrowski (Univ. Michigan)
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