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Division Spotlight
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.
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
When your test capsule is the test: ORNL’s 3D-printed rabbit
Oak Ridge National Laboratory has, for the first time, designed, printed, and irradiated a specimen capsule—or rabbit capsule—for use in its High Flux Isotope Reactor (HFIR), the Department of Energy announced on January 15.
Chuande Yang, Pierre Benoist
Nuclear Science and Engineering | Volume 86 | Number 1 | January 1984 | Pages 47-62
Technical Paper | doi.org/10.13182/NSE84-A17969
Articles are hosted by Taylor and Francis Online.
Scattering anisotropy is often taken into account, in an isotropic formalism, by a transport correction. This correction, which, even in a homogeneous medium, is known to be false in a multigroup theory, is always incorrect for the calculation of neutron leakages in a lattice. The method presented here allows calculation of the buckling-independent diffusion coefficients in a Wigner-Seitz cell, for a linearly anisotropic scattering law. It allows testing of the degree of approximation of the transport correction in various types of lattices, and shows that the axial coefficient may be strongly underestimated in certain cases. This method also allows testing of the simple formulas presented in the past for diffusion coefficients, which lead to good results. The problem of the coupling between energy groups, which appears in the calculation of diffusion coefficients, is also analyzed by the present method; it usually appears to be weak.