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Conference Spotlight
2025 ANS Winter Conference & Expo
November 9–12, 2025
Washington, DC|Washington Hilton
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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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Researchers use one-of-a-kind expertise and capabilities to test fuels of tomorrow
At the Idaho National Laboratory Hot Fuel Examination Facility, containment box operator Jake Maupin moves a manipulator arm into position around a pencil-thin nuclear fuel rod. He is preparing for a procedure that he and his colleagues have practiced repeatedly in anticipation of this moment in the hot cell.
S. Bznuni, N. Baghdasaryan, A. Amirjanyan, G. Nazaryan, P. Kohut, J. Ramsey
Nuclear Science and Engineering | Volume 186 | Number 1 | April 2017 | Pages 98-102
Technical Paper | doi.org/10.1080/00295639.2016.1273012
Articles are hosted by Taylor and Francis Online.
Bounding axial profiles for WWER-440 spent fuel pool burnup credit analysis were developed. A database of axial burnup profiles of WWER-440 type fuel assemblies and fuel followers was developed and studied to determine the burnup axial profile that results in the maximal neutron multiplication factor. Bounding axial profiles were determined based on the statistical analysis of keff of the analyzed profiles from the statistical outliers of the axial profile database. The influence of the identified bounding profiles on keff is quantified for the WWER-440 spent fuel pool. Criticality calculations using the database axial profiles were conducted by the MCNP6.1 program. The isotopic compositions of the spent WWER-440 fuels were quantified by the ORIGEN program of the SCALE 6.1 package.