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Division Spotlight
Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
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.
Mihály Makai
Nuclear Science and Engineering | Volume 82 | Number 3 | December 1982 | Pages 338-353
Technical Paper | doi.org/10.13182/NSE82-338
Articles are hosted by Taylor and Francis Online.
Solving problems of reactor physics is well developed for typical pressurized water and boiling water reactor geometries but less developed for high-temperature gas-cooled reactor, liquid-metal fast breeder reactor, and WWER (BBP) geometries. Several problems of reactor physics can be formulated in a geometry-independent fashion with the help of symmetry considerations, which allows the solution to be decomposed into eigenfunctions of the symmetry operations. An analytic coarse-mesh solution is derived without resorting to the cross leakage concept. The method is applicable to arbitrary geometries. A second-stage homogenization based on the Bloch theorem is presented. It is shown that the solution of the transport equation can always be made up from a cell problem set (microfunctions) and from an overall solution to the diffusion equation (macrofunction).