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Division Spotlight
Operations & Power
Members focus on the dissemination of knowledge and information in the area of power reactors with particular application to the production of electric power and process heat. The division sponsors meetings on the coverage of applied nuclear science and engineering as related to power plants, non-power reactors, and other nuclear facilities. It encourages and assists with the dissemination of knowledge pertinent to the safe and efficient operation of nuclear facilities through professional staff development, information exchange, and supporting the generation of viable solutions to current issues.
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!
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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.
W. W. Clendenin
Nuclear Science and Engineering | Volume 36 | Number 1 | April 1969 | Pages 1-14
Technical Paper | doi.org/10.13182/NSE69-A18852
Articles are hosted by Taylor and Francis Online.
The neutron diffusion length of graphite with an added 1/v absorber has been calculated for temperatures from 200 to 2000°K. At each temperature, the entire range of absorption for which a diffusion length exists has been examined. The largest such range, which occurs for 2000°K, extends from the absorption of pure graphite to a value corresponding to 7.3 b at 0.0253 eV. For all values of temperature and absorption, the diffusion length, L, in centimeters is given within 1% by where T is the absolute temperature and σ′ (b) is the absorption cross section at 0.0253 eV. The temperature-dependent functions α(T) and β(T) are given in Figs. 1 and 2. Very good agreement exists between the values implied by this formula and recent measurements. Each calculated value of L has been obtained as an eigenvalue of a P11 approximation to the transport equation. The neutron energy spectrum is obtained accurately as the eigenfunction in the calculation. This spectrum shows the characteristic discontinuity at the Bragg limit, previously known for beryllium, which varies in magnitude with the absorption. There is also a marked hardening of the spectrum with increasing absorption, which significantly affects the value of the diffusion length.