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Accelerator Applications
The division was organized to promote the advancement of knowledge of the use of particle accelerator technologies for nuclear and other applications. It focuses on production of neutrons and other particles, utilization of these particles for scientific or industrial purposes, such as the production or destruction of radionuclides significant to energy, medicine, defense or other endeavors, as well as imaging and diagnostics.
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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
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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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DOE-EM awards $74.8M Oak Ridge support services contract
The Department of Energy’s Office of Environmental Management has awarded a five-year contract worth up to $74.8 million to Independent Strategic Management Solutions for professional support services at the Oak Ridge Office of Environmental Management site in Oak Ridge, Tenn.
Eugene C. Gritton, A. Leonard
Nuclear Science and Engineering | Volume 37 | Number 3 | September 1969 | Pages 397-409
Technical Paper | doi.org/10.13182/NSE69-A19115
Articles are hosted by Taylor and Francis Online.
An exact solution of the energy-dependent Boltzmann transport equation in the region near a temperature discontinuity is obtained for a nonabsorbing medium which is infinite in extent and has a temperature T1 in one half space and T2 in the other. The scattering cross section is assumed to be energy independent, and the scattering transfer kernel is represented by a degenerate-kernel approximation to the heavy-gas model. The method of solution is based upon a space-dependent thermalization theory developed earlier using the formalism of Case. Numerical calculations of both the scalar neutron flux and the total neutron density are included for various temperature ratios and neutron-to-moderator mass ratios. These results are compared with diffusion theory to assess the accuracy and range of validity of diffusion theory. For small temperature discontinuities, both diffusion theory and transport theory give very nearly the same value of the total neutron density at the interface. Away from the interface, a discrepancy between these theories becomes apparent because diffusion theory incorrectly predicts the energy-mode relaxation lengths, thus giving rise to an incorrect spatial dependence. Diffusion theory predicts the diffusion lengths accurately only when the energy exchange between the diffusing neutrons and the moderator material is weak. In addition, diffusion theory is found to become progressively less accurate for the higher energy modes. Thus, as the higher energy modes become more important, such as for a larger neutron-to-moderator mass ratio or for a larger temperature discontinuity, transport theory calculations of the neutron flux must replace the diffusion theory analysis.