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Concurrent source iteration in the solution of three-dimensional, multigroup discrete ordinates neutron transport equations

Journal Article · · Nuclear Science and Engineering
OSTI ID:220655
;  [1]
  1. Lawrence Livermore National Lab., CA (United States)
A strategy for implementing source iteration on massively parallel computers for use in solving multigroup discrete ordinates neutron transport equations on three-dimensional Cartesian grids is proposed and analyzed. Based on an analysis of the memory requirement and floating-point complexity of the formal matrix-vector multiplication effected by a single source iteration, a data decomposition and communication strategy is presented that is designed to achieve good scalability with respect to all phase-space variables, i.e., neutron position, energy, and direction. A performance model is developed to analyze the scalability properties of the algorithm and to provide computational and heuristic strategies for determining a data decomposition that minimizes wall clock execution time. Numerical results are presented to demonstrate the performance of a specific implementation of this approach on a 1,024-node nCUBE/2.
DOE Contract Number:
W-7405-ENG-48
OSTI ID:
220655
Journal Information:
Nuclear Science and Engineering, Journal Name: Nuclear Science and Engineering Journal Issue: 3 Vol. 122; ISSN NSENAO; ISSN 0029-5639
Country of Publication:
United States
Language:
English