A fission matrix approach to calculate pin-wise 3-D fission density distribution

William Walters, Nathan Roskoff, Alireza Haghighat

Research output: Chapter in Book/Report/Conference proceedingConference contribution

9 Scopus citations

Abstract

This paper presents utilization of the fission matrix (FM) methodology to analyze a spent fuel pool. This FM approach utilizes a pre-calculated MCNP-generated database of fission matrix coefficients which are created at different burnups and cooling times. Certain simplifying assumptions are made based on geometric and physical considerations, greatly reducing the amount of pre-computation required. This approach is capable of quickly and accurately determine pin-wise, axial-dependent fission density distribution and subcritical multiplication (M) or criticality (fc) of a spent fuel pool, in any arrangement, without recalculating FM coefficients. This paper examines the use of the FM approach for different test pool arrangements and conditions. Excellent agreements with an MCNP reference calculation have been achieved with several orders of magnitude reduction in computation time.

Original languageEnglish (US)
Title of host publicationMathematics and Computations, Supercomputing in Nuclear Applications and Monte Carlo International Conference, M and C+SNA+MC 2015
PublisherAmerican Nuclear Society
Pages1351-1361
Number of pages11
ISBN (Electronic)9781510808041
StatePublished - 2015
EventMathematics and Computations, Supercomputing in Nuclear Applications and Monte Carlo International Conference, M and C+SNA+MC 2015 - Nashville, United States
Duration: Apr 19 2015Apr 23 2015

Publication series

NameMathematics and Computations, Supercomputing in Nuclear Applications and Monte Carlo International Conference, M and C+SNA+MC 2015
Volume2

Other

OtherMathematics and Computations, Supercomputing in Nuclear Applications and Monte Carlo International Conference, M and C+SNA+MC 2015
Country/TerritoryUnited States
CityNashville
Period4/19/154/23/15

All Science Journal Classification (ASJC) codes

  • Mathematics(all)
  • Nuclear and High Energy Physics

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