@inproceedings{75300aca1a4c4f35ba63bda85383a327,

title = "A fission matrix approach to calculate pin-wise 3-D fission density distribution",

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.",

author = "Walters, {William J.} and Nathan Roskoff and Alireza Haghighat",

year = "2015",

month = jan,

day = "1",

language = "English (US)",

series = "Mathematics and Computations, Supercomputing in Nuclear Applications and Monte Carlo International Conference, M and C+SNA+MC 2015",

publisher = "American Nuclear Society",

pages = "1351--1361",

booktitle = "Mathematics and Computations, Supercomputing in Nuclear Applications and Monte Carlo International Conference, M and C+SNA+MC 2015",

address = "United States",

note = "Mathematics and Computations, Supercomputing in Nuclear Applications and Monte Carlo International Conference, M and C+SNA+MC 2015 ; Conference date: 19-04-2015 Through 23-04-2015",

}