Generalized approach to the biased adjoint Monte Carlo calculation
Thesis/Dissertation
·
OSTI ID:6630011
The application of the forward (or adjoint) Monte Carlo method to the solution of deep-penetration radiation transport problems requires the use of a biasing technique such as importance sampling. A systematic approach to obtain the importance information is to solve the adjoint (or forward) transport equation and to use the solution as the importance information. In this work, a two-dimensional discrete ordinates calculation in the forward mode was used to obtain appropriate importance information for the adjoint Monte Carlo calculation. Then, methods of biasing the three-dimensional deep penetration adjoint Monte Carlo calculations using the angular flux and the emergent particle density as importance information were studied. The biasing techniques investigated include collision energy biasing and collision angular probability biasing - these procedures alter the collision kernel using the total flux or the angular flux as the importance information. Path length biasing was accomplished using the emergent particle density as the importance information. Adjoint source energy and source angular biasing by the total flux and the angular flux, respectively are also studied. The effects of applying the biasing techniques to adjoint Monte Carlo calculations were investigated for neutron transport through a thick concrete shield with a penetrating duct.
- Research Organization:
- Tennessee Univ., Knoxville (USA)
- OSTI ID:
- 6630011
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
654001* -- Radiation & Shielding Physics-- Radiation Physics
Shielding Calculations & Experiments
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
ADJOINT FLUX
BUILDING MATERIALS
CONCRETES
DISCRETE ORDINATE METHOD
DUCTS
MATERIALS
MONTE CARLO METHOD
NEUTRAL-PARTICLE TRANSPORT
NEUTRON FLUX
NEUTRON TRANSPORT
RADIATION FLUX
RADIATION TRANSPORT
SHIELDS
THREE-DIMENSIONAL CALCULATIONS
TWO-DIMENSIONAL CALCULATIONS
Shielding Calculations & Experiments
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
ADJOINT FLUX
BUILDING MATERIALS
CONCRETES
DISCRETE ORDINATE METHOD
DUCTS
MATERIALS
MONTE CARLO METHOD
NEUTRAL-PARTICLE TRANSPORT
NEUTRON FLUX
NEUTRON TRANSPORT
RADIATION FLUX
RADIATION TRANSPORT
SHIELDS
THREE-DIMENSIONAL CALCULATIONS
TWO-DIMENSIONAL CALCULATIONS