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ASCI

Criticality Calculations with MCNP


Class Length:      4 days (See schedule)
Time:      8:30 a.m. to 4:30 p.m.
Place:     Los Alamos National Laboratory

Number accepted in class:      25
Minimum enrollment required:      10
email address:      karinh@lanl.gov

This 4-day class focuses on using MCNP5 to perform criticality calculations for reactor physics and criticality safety applications. It is an intermediate level class, intended for those with at least some familiarity with MCNP.

Topics to be covered include:

  • Criticality calculations using Monte Carlo methods
  • Geometry, including lattices and repeated structures
  • Tallies and mesh tallies
  • Cross-section data
  • Statistical analysis
  • Assessing convergence of Keff and the source distribution
  • Interactive running and plotting with MCNP5

Classes will include lectures and hands-on computer use for a variety of criticality calculations. Time will be available to discuss individual questions and problems with the MCNP5 development staff, and to pursue additional advanced topics.

Note: Beginning MCNP users are encouraged to review LA-UR-04-0294, "Criticality Calculations with MCNP5: A Primer (2nd Edition)" prior to the class. (available at mcnp.lanl.gov under "Publications" - Criticality and Reactor Physics)

Address all correspondence regarding this class to Karin Hendrickson, karinh@lanl.gov,  phone:  505-606-1740

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