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Division Spotlight
Mathematics & Computation
Division members promote the advancement of mathematical and computational methods for solving problems arising in all disciplines encompassed by the Society. They place particular emphasis on numerical techniques for efficient computer applications to aid in the dissemination, integration, and proper use of computer codes, including preparation of computational benchmark and development of standards for computing practices, and to encourage the development on new computer codes and broaden their use.
Meeting Spotlight
2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
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
Contractor selected for Belgian LLW/ILW facility
Brussels-based construction group Besix announced that is has been chosen by the Belgian agency for radioactive waste management ONDRAF/NIRAS for construction of the country’s surface disposal facility for low- and intermediate-level short-lived nuclear waste in Dessel.
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.
