ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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Division Spotlight
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
Meeting Spotlight
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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
DOE-EM awards $37.5M to Vanderbilt University for nuclear cleanup support
The Department of Energy’s Office of Environmental Management announced on January 16 that it has awarded a noncompetitive financial assistance agreement worth $37.5 million to Vanderbilt University in Nashville, Tenn., to aid the department’s mission of cleaning up legacy nuclear waste.
S. Sanatani, L. S. Kothari
Nuclear Science and Engineering | Volume 11 | Number 2 | October 1961 | Pages 211-217
Technical Paper | doi.org/10.13182/NSE61-A28066
Articles are hosted by Taylor and Francis Online.
To study the diffusion of thermal neutrons in a solid medium, we divide the neutron energy range into two groups, one above and another below the Bragg cutoff energy for the medium. We then apply the method of groups to study the problem. As examples we have considered infinite slabs of beryllium at temperatures of 100°K and 300°K, with an infinite plane source of neutrons at one end of the slab. The flux distributions and the mean neutron energy are calculated for the different cases. It is found that, while for beryllium at 300°K the mean energy is not very much different from the Maxwellian value, for beryllium at T = 100°K results are markedly different from those for a Maxwellian distribution at that temperature. In order to emphasize the effect of the interaction between the two groups in determining the equilibrium flux distributions, we have also made calculation neglecting the interaction and compared these with the earlier results which take account of the interaction.