Published 2005 | Version v1
Journal article

Automated variance reduction for MCNP using deterministic methods

  • 1. Applied Physics Div., Los Alamos National Laboratory, Los Alamos, NM 87545 (United States)
  • 2. Schlumberger-Doll Research, 36 Old Quarry Road, Ridgefield, CT 06877 (United States)

Description

In order to reduce the user's time and the computer time needed to solve deep penetration problems, an automated variance reduction capability has been developed for the MCNP Monte Carlo transport code. This new variance reduction capability developed for MCNP5 employs the PARTISN multigroup discrete ordinates code to generate mesh-based weight windows. The technique of using deterministic methods to generate importance maps has been widely used to increase the efficiency of deep penetration Monte Carlo calculations. The application of this method in MCNP uses the existing mesh-based weight window feature to translate the MCNP geometry into geometry suitable for PARTISN. The adjoint flux, which is calculated with PARTISN, is used to generate mesh-based weight windows for MCNP. Additionally, the MCNP source energy spectrum can be biased based on the adjoint energy spectrum at the source location. This method can also use angle-dependent weight windows. (authors)

Availability note (English)

Available from doi: http://dx.doi.org/10.1093/rpd/nci257

Additional details

Identifiers

Publishing Information

Journal Title
Radiation Protection Dosimetry
Journal Volume
116
Journal Issue
1-4
Journal Page Range
p. 508-512
ISSN
0144-8420

Conference

Title
10. International Conference on Radiation Shielding, and 13. ANS Topical Meeting on Radiation Protection and Shielding - ICRS-10/RPS 2004
Dates
9-14 May 2004
Place
Funchal, Madeira Island (Portugal)

INIS

Country of Publication
United Kingdom
Country of Input or Organization
France
INIS RN
44036037
Subject category
S97: MATHEMATICAL METHODS AND COMPUTING; S61: RADIATION PROTECTION AND DOSIMETRY;
Resource subtype / Literary indicator
Conference
Descriptors DEI
ADJOINT FLUX; COMPUTER CODES; COMPUTERIZED SIMULATION; DISCRETE ORDINATE METHOD; EFFICIENCY; MONTE CARLO METHOD; RADIATION PROTECTION; SHIELDS
Descriptors DEC
CALCULATION METHODS; NEUTRON FLUX; RADIATION FLUX; SIMULATION

Optional Information

Notes
12 refs