Plutonium Sphere Multiplicity Simulations with MCNP-PoliMi
Abstract not provided.
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Jump to search filtersA Multisensor Fusion Approach to the Model-Based Solution of Inverse Radiation Transport Problems
Abstract not provided.
Benchmarks for GADRAS performance validation
The performance of the Gamma Detector Response and Analysis Software (GADRAS) was validated by comparing GADRAS model results to experimental measurements for a series of benchmark sources. Sources for the benchmark include a plutonium metal sphere, bare and shielded in polyethylene, plutonium oxide in cans, a highly enriched uranium sphere, bare and shielded in polyethylene, a depleted uranium shell and spheres, and a natural uranium sphere. The benchmark experimental data were previously acquired and consist of careful collection of background and calibration source spectra along with the source spectra. The calibration data were fit with GADRAS to determine response functions for the detector in each experiment. A one-dimensional model (pie chart) was constructed for each source based on the dimensions of the benchmark source. The GADRAS code made a forward calculation from each model to predict the radiation spectrum for the detector used in the benchmark experiment. The comparisons between the GADRAS calculation and the experimental measurements are excellent, validating that GADRAS can correctly predict the radiation spectra for these well-defined benchmark sources.
Neutron Count Rate Calculation in GADRAS Version 15.3
Abstract not provided.
Monte Carlo Simulations of Multiplicity Measurements of the Plutonium BeRP Ball
Abstract not provided.
Automated Radionuclide Identification on Compact Devices
Abstract not provided.
Alpha79i Neutron Cross-Section Library Performance Testing
Abstract not provided.
MCNP Model of Los Alamos Neutron Pod
Abstract not provided.
A multisensor fusion approach to the model-based solution of inverse radiation transport problems
Abstract not provided.
Solution of Multivariate Inverse Radiation Transport Problems
Abstract not provided.
A framework for the solution of inverse radiation transport problems
IEEE Nuclear Science Symposium Conference Record
Radiation sensing applications for SNM detection, identification, and characterization all face the same fundamental problem: each to varying degrees must infer the presence, identity, and configuration of a radiation source given a set of radiation signatures. This is a problem of inverse radiation transport: given the outcome of a measurement, what was thesource and transport medium that caused that observation? This paper presents a framework for solving inverse radiation transport problems, describes its essential components, and illustrates its features and performance. © 2008 IEEE.
FY2008 Report on GADRAS Radiation Transport Methods
The primary function of the Gamma Detector Response and Analysis Software (GADRAS) is the solution of inverse radiation transport problems, by which the configuration of an unknown radiation source is inferred from one or more measured radiation signatures. GADRAS was originally developed for the analysis of gamma spectrometry measurements. During fiscal years 2007 and 2008, GADRAS was augmented to implement the simultaneous analysis of neutron multiplicity measurements. This report describes the radiation transport methods developed to implement this new capability. This work was performed at the direction of the National Nuclear Security Administration's Office of Nonproliferation Research and Development. It was executed as an element of the Proliferation Detection Program's Simulation, Algorithm, and Modeling element.
GADRAS Gamma Detector Response Analysis Software
Abstract not provided.
Update on the Integration of Neutron Multiplicity Analysis into GADRAS
Abstract not provided.
Synthesis of the Feynman-Y Neutron Multiplicity Metric using Deterministic Transport
Abstract not provided.
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