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
Nuclear Nonproliferation Policy
The mission of the Nuclear Nonproliferation Policy Division (NNPD) is to promote the peaceful use of nuclear technology while simultaneously preventing the diversion and misuse of nuclear material and technology through appropriate safeguards and security, and promotion of nuclear nonproliferation policies. To achieve this mission, the objectives of the NNPD are to: Promote policy that discourages the proliferation of nuclear technology and material to inappropriate entities. Provide information to ANS members, the technical community at large, opinion leaders, and decision makers to improve their understanding of nuclear nonproliferation issues. Become a recognized technical resource on nuclear nonproliferation, safeguards, and security issues. Serve as the integration and coordination body for nuclear nonproliferation activities for the ANS. Work cooperatively with other ANS divisions to achieve these objective nonproliferation policies.
Meeting 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
Jun 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
August 2025
Nuclear Technology
July 2025
Fusion Science and Technology
Latest News
WIPP’s SSCVS: A breath of fresh air
This spring, the Department of Energy’s Office of Environmental Management announced that it had achieved a major milestone by completing commissioning of the Safety Significant Confinement Ventilation System (SSCVS) facility—a new, state-of-the-art, large-scale ventilation system at the Waste Isolation Pilot Plant, the DOE’s geologic repository for defense-related transuranic (TRU) waste in New Mexico.
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.