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Nuclear Installations Safety
Devoted specifically to the safety of nuclear installations and the health and safety of the public, this division seeks a better understanding of the role of safety in the design, construction and operation of nuclear installation facilities. The division also promotes engineering and scientific technology advancement associated with the safety of such facilities.
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2024 ANS Winter Conference and Expo
November 17–21, 2024
Orlando, FL|Renaissance Orlando at SeaWorld
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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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Latest News
UMich introductory engineering course aims to revolutionize nuclear energy through community engagement
A new course at the University of Michigan offered by the Nuclear Engineering and Radiological Sciences (NERS) Department seeks to address the lack of community engagement in the design of energy technologies by pioneering a socially engaged approach.
M. Segev, M. Caner
Nuclear Science and Engineering | Volume 112 | Number 1 | September 1992 | Pages 43-53
Technical Paper | doi.org/10.13182/NSE92-A23950
Articles are hosted by Taylor and Francis Online.
A WIMS-based calculational route for pebble-bed fuel has been established. An outstanding advantage of the WIMS code is its integrated route from basic lattice data to burnup-dependent lattice cross sections. The problem in applying WIMS to pebble-bed fuel is that it lacks spherical geometry. This problem is solved by establishing a number of practical equivalences enabling the replacement of a lattice of spherical fuels by a lattice of cylindrical fuels. A special program was written to convert physical data into WIMS input files, including the Dan-coff factor required for resonance shielding in the multilayer multicell pebble lattice. This capacity provides all that is necessary to generate core-homogenized cross sections directly applicable to core studies. Also generated are zone-homogenized cross sections; in some cases, their use in a transport code results in more accurate core-homogenized cross sections. In terms of the fuel infinite criticality factor, this added accuracy is in the range of 1 to 3 mk for fuel free of absorbers or fuel carrying boron-only absorbers; it is in the range of 3 to 12 mk for fuel carrying hafnium absorbers.