Methods of Monte Carlo biasing using two-dimensional discrete ordinates adjoint flux

Technical Report · Tue Jun 01 00:00:00 EDT 1976

DOI:https://doi.org/10.2172/7362794· OSTI ID:7362794

Tang, J. S.; Stevens, P. N.; Hoffman, T. J.

Methods of biasing three-dimensional deep penetration Monte Carlo calculations using importance functions obtained from a two-dimensional discrete ordinates adjoint calculation have been developed. The important distinction was made between the applications of the point value and the event value to alter the random walk in Monte Carlo analysis of radiation transport. The biasing techniques developed are the angular probability biasing which alters the collision kernel using the point value as the importance function and the path length biasing which alters the transport kernel using the event value as the importance function. Source location biasings using the step importance function and the scalar adjoint flux obtained from the two-dimensional discrete ordinates adjoint calculation were also investigated. The effects of the biasing techniques to Monte Carlo calculations have been investigated for neutron transport through a thick concrete shield with a penetrating duct. Source location biasing, angular probability biasing, and path length biasing were employed individually and in various combinations. Results of the biased Monte Carlo calculations were compared with the standard Monte Carlo and discrete ordinates calculations.

• Research Organization: Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
• DOE Contract Number: W-7405-ENG-26
• OSTI ID: 7362794
• Report Number(s): ORNL/TM-5414; TRN: 76-016102
• Resource Relation: Other Information: Thesis. Submitted by J.S. Tang to Univ. of Tennessee, Knoxville
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
NEUTRON TRANSPORT THEORY
TWO-DIMENSIONAL CALCULATIONS
REACTOR KINETICS
CONCRETES
DISCRETE ORDINATE METHOD
MONTE CARLO METHOD
NEUTRON TRANSPORT
SLABS
BUILDING MATERIALS
KINETICS
MATERIALS
NEUTRAL-PARTICLE TRANSPORT
RADIATION TRANSPORT
TRANSPORT THEORY
220100* - Nuclear Reactor Technology- Theory & Calculation