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.
Division Spotlight
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.
Akio Yamamoto
Nuclear Science and Engineering | Volume 172 | Number 3 | November 2012 | Pages 259-267
Technical Paper | doi.org/10.13182/NSE11-88
Articles are hosted by Taylor and Francis Online.
An approach incorporating the discontinuity factor in transport calculations based on the integrodifferential transport equation, e.g., the discrete ordinates method, the method of characteristics, and the Monte Carlo method, is proposed. In the present approach, the effect of the discontinuity factor is incorporated by correcting cross sections (absorption, production, and scattering cross sections are divided by the discontinuity factor), and the anisotropic scattering cross sections of odd order are corrected with the discontinuity factor and the total cross section. The validity of the present method is confirmed through simple benchmark calculations using the method of characteristics. The present method would be a candidate for a mitigation method for errors associated with approximations, e.g., energy condensation, spatial homogenization, or coarse discretization, in transport calculations.
