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Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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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.
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.