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

Burns, Kimberly

doi:10.2172/1023211

Cited by 2 publications

(5 citation statements)

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“…Generation of the corresponding spatially dependent neutron-induced gamma-ray spectrum using the RADSAT-NG cross section library [4][5].…”

Section: Methods Discussionmentioning

confidence: 99%

“…This is similar to the polyethylene test case implemented in the initial testing for RADSAT coupled neutron-gamma problems [4], except in a more complex geometry. The 4-inch by 4-inch by 4-inch block of graphite was modeled to replace the munition in the PINS configuration in Figure 2.…”

Section: Graphitementioning

confidence: 98%

“…RADSAT-NG cross sections were developed using a hybrid method starting at the raw ENDF cross section files, using various NJOY subroutines to process the cross sections, then partitioned into a usable format using a PNNL developed code [4][5].…”

Section: Radsat-ng Neutron Gamma Cross Section Library Preparationmentioning

confidence: 99%

“…The neutron flux in both the 1-Liter and 4-Liter benchmark cases were comparable for the MCNP and RADSAT cases but there were significantly more gamma rays present in the MCNP in the water and the detector response than were created using RADSAT. From the initial benchmarking cases done with MCNP [4][5], it is believed that this discrepancy is due to the addition of the complex geometry and not including the gamma production due to these components in the problem, not due to deficiencies in the cross section preparations. Originally, both the MCNP and RADSAT calculations were completed using ENDF/B-VII cross sections to simulate the gamma ray production in the water.…”

Section: Figure 6 Empirical Data From the Irradiation Of A 4-liter Wmentioning

confidence: 99%

“…The preparation of suitable multi-group cross sections is required in order to complete this task. Previous publications have described the standard method for producing multi-group cross sections [4] [5].…”

Section: Introductionmentioning

confidence: 99%

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RADSAT Benchmarks for Prompt Gamma Neutron Activation Analysis Measurements

Burns¹,

Gesh²

2011

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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. High-resolution gamma-ray spectrometers are used in these applications to measure the spectrum of the emitted photon flux, which consists of both continuum and characteristic gamma rays with discrete energies. Monte Carlo transport is the most commonly used simulation tool for this type of problem, but computational times can be prohibitively long. This work explores the use of multi-group deterministic methods for the simulation of coupled neutron-photon problems.The main purpose of this work is to benchmark several problems modeled with RADSAT and MCNP to experimental data. Additionally, the cross section libraries for RADSAT are updated to include ENDF/B-VII cross sections. Preliminary findings show promising results when compared to MCNP and experimental data, but also areas where additional inquiry and testing are needed. The potential benefits and shortcomings of the multi-group-based approach are discussed in terms of accuracy and computational efficiency.

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“…Generation of the corresponding spatially dependent neutron-induced gamma-ray spectrum using the RADSAT-NG cross section library [4][5].…”

Section: Methods Discussionmentioning

confidence: 99%

Section: Graphitementioning

confidence: 98%

Section: Radsat-ng Neutron Gamma Cross Section Library Preparationmentioning

confidence: 99%

Section: Figure 6 Empirical Data From the Irradiation Of A 4-liter Wmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

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RADSAT Benchmarks for Prompt Gamma Neutron Activation Analysis Measurements

Burns¹,

Gesh²

2011

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Radiation Detection Computational Benchmark Scenarios

Shaver¹,

Casella²,

Wittman³

et al. 2013

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SummaryModeling forms an important component of radiation detection development, allowing for testing of new detector designs, evaluation of existing equipment against a wide variety of potential threat sources, and assessing operation performance of radiation detection systems. This can, however, result in large and complex scenarios which are time consuming to model. A variety of approaches to radiation transport modeling exist with complementary strengths and weaknesses for different problems. This variety of approaches, and the development of promising new tools (such as ORNL's ADVANTG) which combine benefits of multiple approaches, illustrates the need for a means of evaluating or comparing different techniques for radiation detection problems.This report presents a set of 9 benchmark problems for comparing different types of radiation transport calculations, identifying appropriate tools for classes of problems, and testing and guiding the development of new methods. The benchmarks were drawn primarily from existing or previous calculations with a preference for scenarios which include experimental data, or otherwise have results with a high level of confidence, are non-sensitive, and represent problem sets of interest to NA-22. From a technical perspective, the benchmarks were chosen to span a range of difficulty and to include gamma transport, neutron transport, or both and represent different important physical processes and a range of sensitivity to angular or energy fidelity.Following benchmark identification, existing information about geometry, measurements, and previous calculations were assembled. Monte Carlo results (MCNP decks) were reviewed or created and re-run in order to attain accurate computational times and to verify agreement with experimental data, when present. Benchmark information was then conveyed to ORNL in order to guide testing and development of hybrid calculations. The results of those ADVANTG calculations were then sent to PNNL for compilation. This is a report describing the details of the selected Benchmarks and results from various transport codes.v

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

Cited by 2 publications

References 12 publications

RADSAT Benchmarks for Prompt Gamma Neutron Activation Analysis Measurements

RADSAT Benchmarks for Prompt Gamma Neutron Activation Analysis Measurements

Radiation Detection Computational Benchmark Scenarios

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