IEEE Transactions on Nuclear Science · 2008 · 19 citations · 7 references
Monte Carlo ModelEngineeringSimulationRadiative TransferNumerical SimulationTransport PhenomenaModeling And SimulationComputational ElectromagneticsBiophysicsRadiation DetectionPhysicsMonte CarloRadiation TransportCosmic RayAngular Flux DataMonte Carlo SamplingGamma-ray Spectroscopy ScenariosSynchrotron RadiationSequential Monte CarloRadiative Transfer ModellingMonte Carlo MethodDeterministic Transport
Simulation of gamma‑ray spectrometers is common for technology assessment, with Monte Carlo methods offering accurate pulse‑height spectra but incurring long runtimes, while deterministic transport codes promise faster calculations yet lack direct pulse‑height capability. This study explores coupling angular flux data from a 3‑D deterministic transport code to a Monte Carlo spectrometer model. Ray‑effect mitigation techniques are applied to the deterministic field calculations to improve accuracy before coupling. The coupled approach shows comparable accuracy to pure Monte Carlo while reducing computational time, though its performance depends on problem characteristics.
Simulation is often used to predict the response of gamma-ray spectrometers in technology viability and comparative studies for homeland and national security scenarios. Candidate radiation transport methods generally fall into one of two broad categories: stochastic (Monte Carlo) and deterministic. Monte Carlo methods are the most heavily used in the detection community and are particularly effective for calculating pulse-height spectra in instruments. However, computational times for scattering- and attenuation-dominated problems can be extremely long - many hours or more on a typical desktop computer. Deterministic codes that discretize the transport in space, angle, and energy offer potential advantages in computational efficiency for these same kinds of problems, but pulse-height calculations are not readily accessible. This paper investigates a method for coupling angular flux data produced by a three-dimensional deterministic code to a Monte Carlo model of a gamma-ray spectrometer. Techniques used to mitigate ray effects, a potential source of inaccuracy in deterministic field calculations, are described. Strengths and limitations of the coupled methods, as compared to purely Monte Carlo simulations, are highlighted using example gamma-ray detection problems and two metrics: (1) accuracy when compared to empirical data and (2) computational time on a typical desktop computer.
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MCNP-A General Monte Carlo N-Particle Transport Code
Judith F. Briesmeister · 1993 · 5.1K citations
Engineering, Physics, Novice User +15