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
Aug 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
September 2025
Nuclear Technology
Fusion Science and Technology
August 2025
Latest News
Powering the future: How the DOE is fueling nuclear fuel cycle research and development
As global interest in nuclear energy surges, the United States must remain at the forefront of research and development to ensure national energy security, advance nuclear technologies, and promote international cooperation on safety and nonproliferation. A crucial step in achieving this is analyzing how funding and resources are allocated to better understand how to direct future research and development. The Department of Energy has spearheaded this effort by funding hundreds of research projects across the country through the Nuclear Energy University Program (NEUP). This initiative has empowered dozens of universities to collaborate toward a nuclear-friendly future.
G. Kamelander, F. Putz
Nuclear Science and Engineering | Volume 74 | Number 1 | April 1980 | Pages 13-22
Technical Paper | doi.org/10.13182/NSE80-A18941
Articles are hosted by Taylor and Francis Online.
The method of overlapping neutron spectra has been developed by Selengut to calculate neutron spectra and reaction rates in weakly absorbing media with temperature discontinuities. A combination of Selengut's method with multicollision probability theory leads to a new thermalization method suitable to a wider field of application, especially to the homogenization of reactor cells. Based on this theory, the code THERMAL has been written. The results of THERMAL have been compared with those of the standard transport code THERMOS. Comparison of the results gave a satisfactory correspondence. Compared to THERMOS, the computing time and the storage capacity requirements of THERMAL are fairly small.
