Coupling Deterministic and Monte Carlo Transport Methods for the Simulation of Gamma-Ray Spectroscopy Scenarios

Smith, Leon E.; Gesh, Christopher J.; Pagh, Richard T.; Miller, Erin A.; Shaver, Mark W.; Ashbaker, Eric D.; Batdorf, Michael T.; Ellis, J.E.; Kaye, Willy; McConn, R.J.; Meriwether, G.H.; Ressler, J. J.; Valsan, A.B.; Wareing, Todd A.

doi:10.1109/tns.2008.2002819

Cited by 19 publications

(20 citation statements)

References 2 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…RAdiation Detection Scenario Analysis Toolbox (RADSAT), a code which couples deterministic and Monte Carlo transport to perform radiation detection scenario analysis in three dimensions [1], was used as the building block for the methods derived in this work. RADSAT was capable of performing coupled deterministic-Monte Carlo simulations for gamma-only and neutron-only problems.…”

Section: Discussionmentioning

confidence: 99%

“…Pointwise cross sections allow for the cross section at a specific energy be applied to the particle at that energy instead of an averaged cross section over an energy range. The cross section sets implemented by these codes have been well tested and closely approximate a continuous energy representation [1]. For example, MCNP uses cross sections in an ACER format on an energy grid which allows for linear interpolation between points; this interpolation scheme allows for a specified tolerance within the continuous energy cross section [2].…”

Section: Monte Carlo Methodsmentioning

confidence: 99%

“…For problems dominated by scattering and attenuation, discrete-ordinates codes have the potential to produce accurate results in relatively short computational times, when compared to Monte Carlo. This assumes that a reasonable geometric mesh size can be utilized in the problem [1].…”

Section: Unlike In Monte Carlo Calculations Where Computational Time mentioning

confidence: 99%

“…This biasing of particle travel causes artificial enhancement and depression of the particle flux known as ray effects [15]. An example of the ray effects calculated of the scalar flux at a constant distance from a point source in air using a discrete ordinates approximation is shown in Figure 1 [1]. The discrete ordinates calculation should produce a uniform flux over all angels at a given distance from the source in air.…”

Section: Unlike In Monte Carlo Calculations Where Computational Time mentioning

confidence: 99%

“…When modeling the detector location, it is possible to choose a position where the flux is artificially high or low. In order to mitigate this effect, the detector simulation should be carried out using a high-order angular approximation and/or using a first-collision code to generate a first collision source which will lead to an increase in the computational time required to converge on a global solution [1]. The other major issue encountered when using a deterministic code to simulate high-resolution gamma-ray detector response is the nature of the method.…”

Section: Unlike In Monte Carlo Calculations Where Computational Time mentioning

confidence: 99%

See 4 more Smart Citations

Coupled multi-group neutron photon transport for the simulation of high-resolution gamma-ray spectroscopy applications

Burns¹

2009

View full text Add to dashboard Cite

COUPLED MULTI-GROUP NEUTRON PHOTON TRANSPORT FOR THE SIMULATION OF HIGH-RESOLUTION GAMMA-RAY SPECTROSCOPY APPLICATIONS( )Probability that an Incident Neutron with Energy E n will produce a Continuum Gamma Ray with Energy E SUMMARYThe accurate and efficient simulation of coupled neutron-photon problems is necessary for several important radiation detection applications. Examples include the detection of nuclear threats concealed in cargo containers and prompt gamma neutron activation analysis for nondestructive determination of elemental composition of unknown samples. In these applications, high-resolution gamma-ray spectrometers are used to preserve as much information as possible about the emitted photon flux, which consists of both continuum and characteristic gamma rays with discrete energies. MonteCarlo transport is the most commonly used modeling tool for this type of problem, but computational times for many problems can be prohibitive. This work explores the use of coupled Monte Carlo-deterministic methods for the simulation of neutron-induced photons for high-resolution gamma-ray spectroscopy applications.RAdiation Detection Scenario Analysis Toolbox (RADSAT), a code which couples deterministic and Monte Carlo transport to perform radiation detection scenario analysis in three dimensions [1], was used as the building block for the methods derived in this work. RADSAT was capable of performing coupled deterministic-Monte Carlo simulations for gamma-only and neutron-only problems. The purpose of this work was to develop the methodology necessary to perform coupled neutron-photon calculations and add this capability to RADSAT. Performing coupled neutron-photon calculations requires four main steps: the deterministic neutron transport calculation, the neutroninduced photon spectrum calculation, the deterministic photon transport calculation, and xvii the Monte Carlo detector response calculation. The necessary requirements for each of these steps were determined.A major challenge in utilizing multigroup deterministic transport methods for neutron-photon problems was maintaining the discrete neutron-induced photon signatures throughout the simulation. Existing coupled neutron-photon cross-section libraries and the methods used to produce neutron-induced photons were unsuitable for high-resolution gamma-ray spectroscopy applications. Central to this work was the development of a method for generating multigroup neutron-photon cross-sections in a way that separates the discrete and continuum photon emissions so the neutron-induced photon signatures were preserved. The RADSAT-NG cross-section library was developed as a specialized multigroup neutron-photon cross-section set for the simulation of high-resolution gamma-ray spectroscopy applications.The methodology and cross sections were tested using code-to-code comparison with MCNP5 [2] and NJOY [3]. A simple benchmark geometry was used for all cases compared with MCNP. The geometry consists of a cubical sample with a 252Cf neutron source on one side and a HPG...

show abstract

Section: Discussionmentioning

confidence: 99%

Section: Monte Carlo Methodsmentioning

confidence: 99%

Section: Unlike In Monte Carlo Calculations Where Computational Time mentioning

confidence: 99%

Section: Unlike In Monte Carlo Calculations Where Computational Time mentioning

confidence: 99%

Section: Unlike In Monte Carlo Calculations Where Computational Time mentioning

confidence: 99%

See 3 more Smart Citations

Coupled multi-group neutron photon transport for the simulation of high-resolution gamma-ray spectroscopy applications

Burns¹

2009

View full text Add to dashboard Cite

show abstract

A new coupling method based on MOC and the SN nodal method for the neutron transport calculations

Liu

Zhang

Zhou

et al. 2022

Annals of Nuclear Energy

View full text Add to dashboard Cite

Common misconceptions in Monte Carlo particle transport

Booth

2012

Applied Radiation and Isotopes

View full text Add to dashboard Cite

Monte Carlo particle transport is often introduced primarily as a method to solve linear integral equations such as the Boltzmann transport equation. This paper discusses some common misconceptions about Monte Carlo methods that are often associated with an equation-based focus. Many of the misconceptions apply directly to standard Monte Carlo codes such as MCNP and some are worth noting so that one does not unnecessarily restrict future methods.

show abstract

Coupling Deterministic and Monte Carlo Transport Methods for the Simulation of Gamma-Ray Spectroscopy Scenarios

Cited by 19 publications

References 2 publications

Coupled multi-group neutron photon transport for the simulation of high-resolution gamma-ray spectroscopy applications

Coupled multi-group neutron photon transport for the simulation of high-resolution gamma-ray spectroscopy applications

A new coupling method based on MOC and the SN nodal method for the neutron transport calculations

Common misconceptions in Monte Carlo particle transport

Contact Info

Product

Resources

About