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Automated variance reduction for MCNP using deterministic methods.

J Sweezy1, F Brown, T Booth

  • 1X-5, Applied Physics Division, Los Alamos National Laboratory, MS F663, Los Alamos, NM 87545, USA. jsweezy@lanl.gov

Radiation Protection Dosimetry
|April 11, 2006
PubMed
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This study introduces automated variance reduction for MCNP Monte Carlo simulations, significantly cutting computation time for deep penetration problems by using deterministic methods to create weight windows.

Area of Science:

  • Nuclear Engineering
  • Computational Physics
  • Radiation Transport

Background:

  • Deep penetration problems in radiation transport simulations require significant computational resources.
  • Existing Monte Carlo methods, like MCNP, can be inefficient for deep penetration scenarios.
  • Deterministic methods offer an alternative for generating efficiency maps.

Purpose of the Study:

  • To develop an automated variance reduction capability for the MCNP Monte Carlo code.
  • To reduce user and computer time for solving deep penetration problems.
  • To integrate deterministic and Monte Carlo methods for enhanced efficiency.

Main Methods:

  • Developed an automated variance reduction capability for MCNP5.
  • Employed the PARTISN discrete ordinates code to generate mesh-based weight windows.

Related Experiment Videos

  • Translated MCNP geometry for PARTISN and utilized adjoint flux to create weight windows.
  • Biased MCNP source energy spectrum based on adjoint energy spectrum and incorporated angle-dependent weight windows.
  • Main Results:

    • Successfully implemented automated variance reduction for MCNP.
    • Demonstrated increased efficiency in solving deep penetration problems.
    • Enabled the use of deterministic adjoint flux for Monte Carlo weight window generation.
    • Facilitated source energy spectrum biasing and angle-dependent weight windows.

    Conclusions:

    • The developed automated variance reduction capability significantly enhances MCNP efficiency for deep penetration problems.
    • The integration of deterministic (PARTISN) and Monte Carlo (MCNP) methods provides a powerful approach for radiation transport simulations.
    • This method offers flexibility through source energy biasing and angle-dependent weight windows, reducing computational time.