Neutronics modeling and simulation of sharp for fast reactor analysis

W. S. Yang, M. A. Smith, C. H. Lee, A. Wollaber, D. Kaushik, A. S. Mohamed

Research output: Contribution to journalArticle

15 Citations (Scopus)

Abstract

This paper presents the neutronics modeling capabilities of the fast reactor simulation system SHARP, which ANL is developing as part of the U.S. DOE's NEAMS program. We discuss the three transport solvers (PN2ND, SN2ND, and MOCFE) implemented in the UNIC code along with the multigroup cross section generation code MC2-3. We describe the solution methods and modeling capabilities, and discuss the improvement needs for each solver, focusing on massively parallel computation. We present the performance test results against various benchmark problems and ZPR-6 and ZPPR critical experiments. We also discuss weak and strong scalability results for the SN2ND solver on the ZPR-6 critical assembly benchmarks.

Original languageEnglish
Pages (from-to)520-545
Number of pages26
JournalNuclear Engineering and Technology
Volume42
Issue number5
DOIs
Publication statusPublished - Oct 2010

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Keywords

  • Fast reactor
  • Multigroup cross section
  • Neutron transport
  • Simulation

ASJC Scopus subject areas

  • Nuclear Energy and Engineering

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