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.
Explore membership for yourself or for your organization.
Conference Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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!
Latest Magazine Issues
Jul 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
August 2025
Nuclear Technology
Fusion Science and Technology
July 2025
Latest News
Hash Hashemian: Visionary leadership
As Dr. Hashem M. “Hash” Hashemian prepares to step into his term as President of the American Nuclear Society, he is clear that he wants to make the most of this unique moment.
A groundswell in public approval of nuclear is finding a home in growing governmental support that is backed by a tailwind of technological innovation. “Now is a good time to be in nuclear,” Hashemian said, as he explained the criticality of this moment and what he hoped to accomplish as president.
J. V. Donnelly
Nuclear Science and Engineering | Volume 168 | Number 2 | June 2011 | Pages 180-184
Technical Note | doi.org/10.13182/NSE10-76
Articles are hosted by Taylor and Francis Online.
MCNP applies only nuclear data tabulated at specific temperatures and does not incorporate methods for general temperature interpolation of nuclear data. However, in models representing realistic power reactor cores, it is generally necessary to represent the distribution of fuel and coolant temperatures to reliably predict detailed power distributions and reactivity feedback effects. This paper describes methods that can be easily applied for the representation of cross-section data at general temperatures, based on interpolation through mixing of nuclide representations at multiple temperatures. The discrepancies due to the interpolations have been determined to be insignificant relative to the estimated uncertainties in typical calculated eigenvalues.