A source biasing and variance reduction technique for Monte Carlo radiation transport modeling of emission tomography problems

A source biasing and variance reduction technique for Monte Carlo radiation transport modeling of emission tomography problems

A numerical radiation transport methodology for predicting gamma emission tomographs was developed utilizing the deterministic fuel burn-up software, ORIGEN, in the SCALE code package as a source definition input for Monte Carlo N Particle Transport ver. 6.1 to simulate gamma emission spectra from i...

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Bibliographic Details
Published in:Journal of radioanalytical and nuclear chemistry Vol. 320; no. 1; pp. 37 - 45
Main Authors: Kilby, Seth, Jin, Zhongmin, Avachat, Ashish, Kanies, Bryant, Woolstenhulme, Nicholas, Lee, Hyoung K., Graham, Joseph
Format: Journal Article
Language:English
Published: Cham Springer International Publishing 01-04-2019
Springer
Springer Nature B.V
Subjects:
Chemistry
Chemistry and Materials Science
Collimation
Collimators
Computer simulation
Diagnostic Radiology
Emission spectra
Energy spectra
Field of view
Gamma emission
Hadrons
Heavy Ions
High aspect ratio
Inorganic Chemistry
Mathematical analysis
Mathematical models
Methods
Nuclear Chemistry
Nuclear energy
Nuclear fuels
Nuclear industry
Nuclear Physics
Numerical prediction
Physical Chemistry
Prejudice
Radiation (Physics)
Radiation transport
Reduction
Scintillation counters
Tomography
Oak Ridge Isotope Generation (ORIGEN)
Monte-Carlo N Particle Transport (MCNP)
Variance reduction
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Summary:A numerical radiation transport methodology for predicting gamma emission tomographs was developed utilizing the deterministic fuel burn-up software, ORIGEN, in the SCALE code package as a source definition input for Monte Carlo N Particle Transport ver. 6.1 to simulate gamma emission spectra from irradiated nuclear fuel and measured by an inorganic scintillator detector. Variance reduction utilized analytical expressions for the solid angle and field of view between source, collimator and detector to normalize the gamma energy spectrum from a non-analog monodirectionally biased beam source problem to approximate the equivalent analog problem of an isotropic source. One normalization scheme, which assumes that the source is distributed in a thin cylindrical volume, can achieve lower than 6% error and an order of 10 7 reduction in the computational cost. A different normalization scheme involving a truncated cone source distribution overestimated the count rate by approximately 45% but had similar computational savings. In both approaches, the accuracy and computational savings of the method improves with increasing collimator aspect ratio. This method is therefore useful for problems with high aspect ratio collimators.
ISSN:0236-5731
1588-2780
DOI:10.1007/s10967-019-06457-1