MCNP

MCNP6 Class Schedule for 2021


Online Classes

  • * We are now offering online classes using the Webex Meetings application.
  • * Before registering, you should acquire your own version of MCNP6 (see How to get MCNP).
  • * Online classes are open to all, but non-US-citizens must apply well in advance. Firm registration deadlines are listed in the schedule.
  • * Registration for US-citizens will close 2 weeks prior to the start of a class.
  • * Please register early (but after you have your own version of MCNP6).
  • * After registering, you must email proof of your MCNP6 license to the MCNP Registrar, mcnp_registrations@lanl.gov

Aug 16-20, 2021
Online
Introduction to MCNP6 (online)
Non-US citizens must register by 2021-06-11 | Mon 9:00 - Fri 12:00
$600
--FULL--
Aug 30 - Sept 1, 2021
Online
Using NJOY to Create MCNP ACE Files & Visualize Nuclear Data (online)
Non-US citizens must register by 2021-06-25 | Mon 10:00 - Wed 5:00
$600
Oct 4-8, 2021
Online
Intermediate MCNP6 (online)
Non-US citizens must register by 2021-07-30 | Mon 9:00 - Fri 12:00
$600
--FULL--
Oct 18-22, 2021
Online
Unstructured Mesh with Attila4MC (online)
Non-US citizens must register by 2021-08-13 | Mon 9:00 - Fri 4:30
$600
Nov 15-19, 2021
Online
Introduction to MCNP6 (online)
Non-US citizens must register by 2021-09-10 | Mon 9:00 - Fri 12:00
$600
Nov 29 - Dec 1, 2021
Online
Variance Reduction with MCNP6 (online)
Non-US citizens must register by 2021-09-24 | Mon 9:00 - Wed 4:30
$600
  • Classes may be cancelled or postponed if registration is too low. If a class is marked as FULL, CANCELLED, or COMPLETED, then you cannot register for it.

FEES AND REGISTRATION
[click here]


Introductory classes are for those who have little or no experience with MCNP. This class surveys the features of MCNP so the beginning user will be introduced to the capabilities of the program, and will have hands-on experience at running the code to solve simple problems. Course topics include Basic Geometry, Source Definitions, Output(Tallies), Advanced Geometry (repeated structures specification), Variance Reduction Techniques, Statistical Analysis, Criticality, Plotting of Geometry and Tallies, and Neutron / Photon / Electron Physics.

Intermediate classes are designed for people who have some experience in running MCNP Monte Carlo calculations, but would like to refresh or advance their skills. It covers a quick overview of the MCNP basics and then advances into more complex features within the code. In addition to the basic introduction material covering code input, geometry, plotting, sources, tallies, physics tables, criticality, and variance reduction, the intermediate level class topics include: Advanced CSG Geometry (universes, lattices, repeated structures); Advanced Source Definitions (repeated sources, surface source read/write); Advanced Tallies & Variance Reduction (repeated tallies, perturbations, pulse-height tallies, dxtran, weight windows); Introduction to Parameter Studies, Intrinsic Source Generation, MCNPTools.

Advanced classes - Variance Reduction, Criticality, & Unstructured Mesh are for people with MCNP experience who want to extend their knowledge and gain depth of understanding.  Most areas of MCNP operation will be discussed in detail, with emphasis on Advanced Geometry, Advanced Variance Reduction Techniques, and other advanced features of the program. Time will be available to discuss approaches to specific problems of interest to participants. Classes on specific topics are offered when there is sufficient interest.



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