Deterministic Transport Methods for the Simulation of Gamma-Ray Spectroscopy Scenarios

Smith, Leon E.; Gesh, Christopher J.; Pagh, Richard T.; McConn, R.J.; Ellis, J.E.; Kaye, Willy; Meriwether, G.H.; Miller, Erin A.; Shaver, Mark W.; Starner, Jason R.; Valsan, A.B.; Wareing, Todd A.

doi:10.1109/nssmic.2006.356224

Cited by 9 publications

(2 citation statements)

References 5 publications

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“…mitigation of ray effects, mesh refinement, solutionaccuracy assessment). Applications considered in previous RADSAT development included radiation portal monitors, instrumented containers for in-transit monitoring of maritime cargo, UF 6 cylinder verification for fuel-cycle safeguards, and prompt gamma neutron activation analysis for chemical munitions assay [3]…”

Section: Radsat For Snm Movement Detection Scenariosmentioning

confidence: 99%

Radiation Detection Scenario Analysis Toolbox (RADSAT) Test Case Implementation Final Report

Shaver¹

2010

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This project was designed to demonstrate the use of the Radiation Detection Scenario Analysis Toolbox (RADSAT) radiation detection transport modeling package (developed in a previous NA-22 project) for specific radiation detection scenarios important to proliferation detection. RADSAT is founded on a 3-dimensional deterministic radiation transport solver capable of efficiently computing the radiation field at all points in complex, large-scale problems (e.g. buildings). These results are then coupled to a Monte Carlo detector response simulator. For this project Pacific Northwest National Laboratory (PNNL) staff applied RADSAT to two specific instruments and scenarios, in close collaboration with the developers of each technology. The first is a neutron-scatter camera for detection of concealed neutron-emitting sources developed at Sandia National Laboratories (SNL) and the second is a spent-fuel verification system for fuel assemblies in storage casks developed at Idaho National Laboratory (INL). To simulate detector responses, RADSAT uses a source modified version of Monte Carlo N-Particle Version 5 (MCNP5), which does not produce all of the information required to produce images for the scatter camera system. SNL models the scatter camera with Monte Carlo N-Particle-Politecnico di Milano (MCNP-PoliMi), which utilizes more accurate neutron elastic scattering physics and secondary gamma-ray production essential for modeling time-dependent events in multiple detectors. Therefore, RADSAT currently will not work for generating images for the scatter camera. However, it was demonstrated that RADSAT calculated the correct individual detector response, which indicates that RADSAT could be an appropriate tool for modeling neutron scatter cameras if MCNP-PoliMi were to be used as the RADSAT Monte Carlo detector response module. Incorporating MCNP-PoliMi into RADSAT in addition to MCNP5 would require a minimal amount of code development, testing, and quality assurance. In terms of computational run time, for very simple low scattering scenarios, RADSAT may not have a computational speed advantage over MCNP5, but for more complicated, larger, or highly scattering problems (which are probably more realistic), RADSAT may have computational run times shorter than MCNP5. For the simulation of the spent fuel cask gamma-ray scanner, the solution accuracies for the RADSAT simulations were reasonable (less than 15% different from experimental results) and comparable to the current standard (MCNPX) for all of the compared values for both full and empty assembly positions. RADSAT also ran 60% faster than Monte Carlo N-Particle eXtended (MCNPX), with both codes optimized for speed. In addition, the time to set up a RADSAT run is probably much less than the time to set up and optimize an MCNPX input deck with appropriate variance reduction, making the total time to solution even faster for RADSAT than just the computational run time advantage. v

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Section: Radsat For Snm Movement Detection Scenariosmentioning

confidence: 99%

Radiation Detection Scenario Analysis Toolbox (RADSAT) Test Case Implementation Final Report

Shaver¹

2010

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“…Those techniques involve the use of a deterministically calculated adjoint flux solution as an importance mapping for forward MCNP calculations. Some of this work is being done in collaboration with Oak Ridge National Laboratory (Mosher et al 2009) and builds on previous work by PNNL in the area of coupled deterministic-Monte Carlo simulations for complex radiation detection scenarios (Smith et al 2008).…”

Section: Mcnp Modelsmentioning

confidence: 99%

Enrichment Assay Methods Development for the Integrated Cylinder Verification System

Smith¹,

Misner²,

Hatchell³

et al. 2009

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International Atomic Energy Agency (IAEA) inspectors currently perform periodic inspections at uranium enrichment plants to verify UF 6 cylinder enrichment declarations. Measurements are typically performed with handheld high-resolution instruments on a statistically determined sampling of cylinders taken to be representative of the facility's entire product-cylinder inventory. Pacific Northwest National Laboratory (PNNL) is developing a concept to automate the verification of enrichment plant cylinders to enable 100 percent product-cylinder verification and potentially, mass-balance calculations on the facility as a whole (by also measuring feed and tails cylinders). The Integrated Cylinder Verification System (ICVS) could be located at key measurement points to positively identify each cylinder, measure its mass and enrichment, store the collected data in a secure database (mailbox), and maintain continuity of knowledge on measured cylinders until IAEA inspector arrival. PNNL's ICVS concept uses measurement systems that can be operated in an unattended mode: medium-resolution scintillators for gamma-ray spectroscopy and moderated He-3 neutron detectors. Prior proof-of-principle studies of advanced nondestructive assay (NDA) methods for automated enrichment assay, particularly neutron-related signatures spawned by U-234 alpha emission, have encouraged further development of NDA methods suitable for an ICVS prototype. The work described in this report was supported by NA-243 funding in late FY09, following completion of the initial PNNL Laboratory Directed Research and Development (LDRD)-funded study that focused on non-traditional NDA signatures. A proposal has been submitted to NA-241 for design and testing of a prototype ICVS that utilizes both non-traditional and traditional NDA signatures. Work on the components of the ICVS that do not involve research and development will continue to be supported under NA-243, and are addressed in separate reports. The three main objectives of this FY09 project are summarized here and described in more detail in the report: 1) Develop a preliminary design for a prototype NDA system, 2) Refine PNNL's MCNP models of the NDA system, and 3) Procure and test key pulse-processing components. Progress against these tasks to date, and next steps, are discussed. v

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A Simulation Framework for Evaluating Detector Performance in Cargo Screening Applications

Robinson

Smith

Jarman

et al. 2006

2006 IEEE Nuclear Science Symposium Conference Record

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Deterministic Transport Methods for the Simulation of Gamma-Ray Spectroscopy Scenarios

Cited by 9 publications

References 5 publications

Radiation Detection Scenario Analysis Toolbox (RADSAT) Test Case Implementation Final Report

Radiation Detection Scenario Analysis Toolbox (RADSAT) Test Case Implementation Final Report

Enrichment Assay Methods Development for the Integrated Cylinder Verification System

A Simulation Framework for Evaluating Detector Performance in Cargo Screening Applications

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