David J. Desimone
Los Alamos National Laboratory
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Featured researches published by David J. Desimone.
Archive | 2016
Ernst I. Esch; David J. Desimone; Rollin E. Lakis
We examined x-rays for the use as authentication and verification tool in treaty verification. Several x-ray pictures were taken to determine the quality and feasibility of x-rays for these tasks. This document describes the capability of the used x-ray system and outlines its parameters and possible use.
Archive | 2016
Martyn T. Swinhoe; Alison Victoria Goodsell; Kiril Dimitrov Ianakiev; Metodi Iliev; David J. Desimone; Carlos D. Rael; Vladimir Henzl; Paul John Polk
This report summarizes the work done under a DNDO R&D funded project on the development of the differential dieaway method to measure plutonium in spent fuel. There are large amounts of plutonium that are contained in spent fuel assemblies, and currently there is no way to make quantitative non-destructive assay. This has led NA24 under the Next Generation Safeguards Initiative (NGSI) to establish a multi-year program to investigate, develop and implement measurement techniques for spent fuel. The techniques which are being experimentally tested by the existing NGSI project do not include any pulsed neutron active techniques. The present work covers the active neutron differential dieaway technique and has advanced the state of knowledge of this technique as well as produced a design for a practical active neutron interrogation instrument for spent fuel. Monte Carlo results from the NGSI effort show that much higher accuracy (1-2%) for the Pu content in spent fuel assemblies can be obtained with active neutron interrogation techniques than passive techniques, and this would allow their use for nuclear material accountancy independently of any information from the operator. The main purpose of this work was to develop an active neutron interrogation technique for spent nuclear fuel.
Archive | 2015
Alison Victoria Goodsell; Martyn T. Swinhoe; Vladimir Henzl; Carlos D. Rael; David J. Desimone
In this report, new experimental data and MCNPX simulation results of the differential die-away (DDA) instrument response to the presence of neutron absorbers are evaluated. In our previous fresh nuclear fuel experiments and simulations, no neutron absorbers or poisons were included in the fuel definition. These new results showcase the capability of the DDA instrument to acquire data from a system that better mimics spent nuclear fuel.
Archive | 2015
Alison Victoria Goodsell; Vladimir Henzl; Martyn T. Swinhoe; Carlos D. Rael; David J. Desimone
Experimental results of the assay of mock-up (fresh) fuel with the differential die-away (DDA) instrument were compared to the Monte Carlo N-Particle eXtended (MCNPX) simulation results. Most principal experimental observables, the die-away time and the in tegral of the DDA signal in several time domains, have been found in good agreement with the MCNPX simulation results. The remaining discrepancies between the simulation and experimental results are likely due to small differences between the actual experimental setup and the simulated geometry, including uncertainty in the DT neutron generator yield. Within this report we also present a sensitivity study of the DDA instrument which is a complex and sensitive system and demonstrate to what degree it can be impacted by geometry, material composition, and electronics performance.
Archive | 2014
Alison Victoria Goodsell; Martyn T. Swinhoe; Vladimir Henzl; Carlos D. Rael; David J. Desimone
Fresh fuel experiments for the differential die-away (DDA) project were performed using a DT neutron generator, a 15x15 PWR fuel assembly, and nine 3He detectors in a water tank inside of a shielded cell at Los Alamos National Laboratory (LANL). Eight different fuel enrichments were created using low enriched (LEU) and depleted uranium (DU) dioxide fuel rods. A list-mode data acquisition system recorded the time-dependent signal and analysis of the DDA signal die-away time was performed. The die-away time depended on the amount of fissile material in the fuel assembly and the position of the detector. These experiments were performed in support of the spent nuclear fuel Next Generation Safeguards Initiative DDA project. Lessons learned from the fresh fuel DDA instrument experiments and simulations will provide useful information to the spent fuel project.
Archive | 2014
Alison Victoria Goodsell; Martyn T. Swinhoe; Vladimir Henzl; Kiril Dimitrov Ianakiev; Metodi Iliev; Carlos D. Rael; David J. Desimone
Four helium-3 (3He) detector/preamplifier packages (¾”/KM200, DDSI/PDT-A111, DDA/PDT-A111, and DDA/PDT10A) were experimentally tested to determine the deadtime effects at different DT neutron generator output settings. At very high count rates, the ¾”/KM200 package performed best. At high count rates, the ¾”/KM200 and the DDSI/PDT-A111 packages performed very well, with the DDSI/PDT-A111 operating with slightly higher efficiency. All of the packages performed similarly at mid to low count rates. Proposed improvements include using a fast recovery LANL-made dual channel preamplifier, testing smaller diameter 3He tubes, and further investigating quench gases.
IEEE Transactions on Nuclear Science | 2013
Robert J. Estep; Caroline M Boyle; Edward T. H. Clifford; David J. Desimone; John C. Determan; Ernst I. Esch; Patrick Forget; Walter J. Hansen; Joseph Francis Longo; Jeffrey S. Montoya; Richard Rasmussen; Martin B. Smith; Eric B. Sorenson
We have developed a dynamic gamma-ray emission image reconstruction method called MVIR (Moving Voxel Image Reconstruction) for lane detection in multilane portal monitor systems. MVIR was evaluated for use in the Fixed Site Detection System (FSDS), a prototype three-lane gamma-ray portal monitor system for EZ-pass toll plazas. As a baseline, we compared MVIR with a static emission image reconstruction method in analyzing the same real and simulated data sets. Performance was judged by the distributions of image intensities for source and no-source vehicles over many trials as a function of source strength. We found that MVIR produced significantly better results in all cases. The performance difference was greatest at low count rates, where source/no-source distributions were well separated with the MVIR method, allowing reliable source vehicle identification with a low probability of false positive identifications. Static emission image reconstruction of the same data produced overlapping distributions that made source vehicle identification unreliable. The performance of the static method was acceptable at high count rates. Both algorithms reliably identified two strong sources passing through at nearly the same time.
Archive | 2011
Ernst I. Esch; Robert J. Estep; Robert J Dallman; Noah G Pope; Jon B Nielsen; Mark E Abhold; David J. Desimone; Katherine C. Frame; David K. Miko; John Alan Rennie; Eric B Sorensen; Sy Stange; Michael W Strevell
Archive | 2015
David K. Miko; David J. Desimone
Archive | 2014
Ernst I. Esch; Jeffrey Goettee; Douglas R. Mayo; Jon S. Bridgewater; David J. Desimone; Steven K. Klein; Michael C. Miller; Sy Stange; Amarette N Trujillo; Michael J. Weaver