Citation: E. Kitcher, J. Osborn, M. Marciniak, G. Garcia, B. Batista, S. Chirayath “Application of Safeguards to a Molten Salt Reactor”, presented at 59th Annual Meeting of the Institute of Nuclear Materials Management, Baltimore, Maryland, July 22-26, 2018. [updatepublicationbutton ps=’85723′] [deletepublicationbutton psd=’85723′]
Safeguards Analysis of Pyroprocessing Product Ingot Diversions Possible Through Neutron Source Substitutions
Citation: H. Boo, S. Woo, S. Chirayath, “Safeguards Analysis of Pyroprocessing Product Ingot Diversions Possible Through Neutron Source Substitutions”, ANS Winter Meeting & Expo, Orlando, Florida, 11-15 November 2018. Associated Projects: 1. Evaluating the Proliferation Risk of Pyroprocessing, [updatepublicationbutton ps=’80935′] [deletepublicationbutton psd=’80935′]
Uncertainty Analysis of Fission Product Concentrations in MCNP Depletion Calculations
Citation: R. Schafer, E. Kitcher, S. Chirayath, “Uncertainty Analysis of Fission Product Concentrations in MCNP Depletion Calculations”, ANS Winter Meeting & Expo, Orlando, Florida, 11-15 November 2018. Associated Projects: 1. Uncertainty Quantification for Nuclear Forensic Model Computations, [updatepublicationbutton ps=’43146′] [deletepublicationbutton psd=’43146′]
Statistical Analysis of Fission Product Concentration Uncertainties from MCNP6 Multi-Time Step Depletion Calculation
Citation: Y. Minamigawa, E. Kitcher, S. Chirayath, “Statistical Analysis of Fission Product Concentration Uncertainties from MCNP6 Multi-Time Step Depletion Calculation”, ANS Winter Meeting & Expo, Orlando, Florida, 11-15 November 2018. [updatepublicationbutton ps=’56117′] [deletepublicationbutton psd=’56117′]
Risk Informed Safeguards Approaches for Molten Salt Reactors
Citation: A. Sagadevan, S. Chirayath, A. Worrall “Risk Informed Safeguards Approaches for Molten Salt Reactors”, presented at 59th Annual Meeting of the Institute of Nuclear Materials Management, Baltimore, Maryland, July 22-26, 2018. [updatepublicationbutton ps=’66117′] [deletepublicationbutton psd=’66117′]
Nonproliferation Challenges within High Temperature Gas Reactor Fuel Cycles
Citation: D. Mulyana S.S. Chirayath, “Nonproliferation Challenges within High Temperature Gas Reactor Fuel Cycles”, presented at 59th Annual Meeting of the Institute of Nuclear Materials Management, Baltimore, Maryland, July 22-26, 2018. [updatepublicationbutton ps=’2484′] [deletepublicationbutton psd=’2484′]
Stochastic Approach in Single Path Analysis of Adversary’s Intrusion Strategies in Physical Protection System (PPS) Effectiveness Evaluation
Citation: Y. Setiawan S.S. Chirayath, “Stochastic Approach in Single Path Analysis of Adversary’s Intrusion Strategies in Physical Protection System (PPS) Effectiveness Evaluation”, presented at 59th Annual Meeting of the Institute of Nuclear Materials Management, Baltimore, Maryland, July 22-26, 2018. Associated Projects: 1. Adversary Path Analysis of a Physical Protection Design Using a Stochastic Approach, [updatepublicationbutton […]
Experimental Validation of a Nuclear Forensics Methodology for Source Reactor-Type Discrimination of Chemically Separated Plutonium
Citation: J. Osborn, K. Glennon, E. Kitcher, J. Burns, C. III, S. Chirayath “Experimental Validation of a Nuclear Forensics Methodology for Source Reactor-Type Discrimination of Chemically Separated Plutonium”, presented at 59th Annual Meeting of the Institute of Nuclear Materials Management, Baltimore, Maryland, July 22-26, 2018. Associated Projects: 1. Plutonium Fingerprinting for Forensics (PuFF) Project, [updatepublicationbutton […]
Analysis of Radionuclide Deposition Ratios from the Fukushima-Daiichi Incident
Citation: M.R. Smith and C.M. Marianno, “Analysis of Radionuclide Deposition Ratios from the Fukushima-Daiichi Incident”, 58th Annual Health Physics Society Meeting, Madison, Wisconsin, 10 July 2013. Associated Project: 1. Analysis of Radionuclide Deposition Ratios from the Fukushima-Daiichi Incident [updatepublicationbutton ps=’36068′] [deletepublicationbutton psd=’36068′]
Methodology Development for Combined Evaluation of Security and Safety Risk
Citation: S.S. Chirayath, P.J. O’Neal, “Methodology Development for Combined Evaluation of Security and Safety Risk”, Transactions of American Nuclear Society, 2017 ANS Winter Meeting, October 29-November 2, (2017). Associated Projects: 1. Methodology Development for Combined Evaluation of Security and Safety Risk, [updatepublicationbutton ps=’40637′] [deletepublicationbutton psd=’40637′]
PNAR Measurements of Fugen Fuel
Citation: J. Eigenbrodt, S.J. Tobin, W.S. Charlton, A.M. Bolind, H.O. Menlove, M. Seya, and H.R. Trellue, “PNAR Measurements of Fugen Fuel”, 55th Annual Meeting of the Institute of Nuclear Materials Management, Atlanta, Georgia, 20-14 July 2014. Abstract: The Next Generation Safeguards Initiative Spent Fuel (NGSI-SF) Project deployed a non-destructive assay (NDA) Passive Neutron Albedo Reactivity […]
Investigation of Trace U-236 Content Variation in Geologic Uranium Deposits
Citation: C.C. Keith W.S. Charlton “Investigation of Trace U-236 Content Variation in Geologic Uranium Deposits”, 55th Annual Meeting of the Institute of Nuclear Materials Management, Atlanta, Georgia, 20-14 July 2014. Abstract: Uranium-236 is naturally present in uranium ores at very low concentrations (~10-10a/o). With the increasing precision of mass spectroscopy, specifically accelerator mass spectroscopy (AMS), […]
NRX Reactor Spent Fuel Study
Citation: G. Spence, “NRX Reactor Spent Fuel Study”, INMM 54th Annual Meeting, 14-18 July 2013, Palm Desert, California, USA. Abstract: In safeguards and nonproliferation, we routinely need the ability to estimate isotopic inventories of spent fuel. However, those estimates are usually produced without reporting uncertainties which limit their usability. In this work, we describe a […]
Bent-Crystal Spectrometer Analyzing Plutonium K X-Rays for Applications in Nuclear Forensics
Citation: W. Charlton, A. Goodsell, “Bent-Crystal Spectrometer Analyzing Plutonium K X-Rays for Applications in Nuclear Forensics”, Proceedings of the INMM 52nd Annual Meeting, Palm Desert, CA, July 17-21, 2011. Abstract: The ability to quickly quantify the Pu content within used nuclear fuel is essential to nuclear forensics. Analysis of the Pu to U ratio can […]
Exploration of Ion-Exchanged Glass for Seals Applications
Citation: W. Charlton, R. Ghanbari, “Exploration of Ion-Exchanged Glass for Seals Applications”, Proceedings of the INMM 52nd Annual Meeting, Palm Desert, CA, July 17-21, 2011. Abstract: As the nuclear industry grows around the globe, it brings with it a need for more safeguards and proliferation resistant technologies. Tags and seals are an area where innovation […]
Analytical Inverse Model for Post Event Attribution of Plutonium
Citation: J. Miller, “Analytical Inverse Model for Post Event Attribution of Plutonium”, Proceedings of the 2009 Annual Meeting of the Institute of Nuclear Materials Management, Tucson, AZ, July 12-15, 2009. Abstract: An integral part of deterring nuclear terrorism is the swiftattributionof anyeventto a particular state or organization. By quickly being able to identify the responsible […]
Advancing Methods for Providing Attribution for the HEU Used in a Terrorist Nuclear Weapon
Citation: W. Charlton, A. LaFleur, “Advancing Methods for Providing Attribution for the HEU Used in a Terrorist Nuclear Weapon”, Proceedings of the 29th ESARDA Annual Meeting, Aix-en-Provence, France, May 22-24, 2007. Abstract: An algorithm was developed that uses measured isotopic ratios from fission product residue following the detonation of a high-enriched uranium nuclear weapon to […]
Measurement of Uranium in Bio Matrices for Nuclear Forensic Purposes
Citation: W. Charlton, J. Miller, “Measurement of Uranium in Bio Matrices for Nuclear Forensic Purposes”, Proceedings of the 51st Annual Meeting for the Institute of Nuclear Materials Management, Baltimore, Maryland, July 11-15, 2010. Abstract: As the proliferation of nuclear technology increases, there is a growing need for the ability to detect, confirm, and determine an individual’s […]
Nuclear Nonproliferation Analysis Using Agent Based Modeling in an Entropy Empowered Intelligent Agent Bayesian Framework
Citation: R. Elmore, W. Charlton, “Nuclear Nonproliferation Analysis Using Agent Based Modeling in an Entropy Empowered Intelligent Agent Bayesian Framework”, 2014 Winter Simulation Conference, Savannah, GA, December 7-10, 2014 Abstract: For decades, scholars have studied the proliferation of nuclear weapons by states. There have traditionally been two theories of proliferation: (1) the demand side in […]
Nonproliferation Informatics: Employing Bayesian Analysis, Agent Based Modeling, and Information Theory for Dynamic Proliferation Pathway Studies
Citation: R. Elmore, W. Charlton, “Nonproliferation Informatics: Employing Bayesian Analysis, Agent Based Modeling, and Information Theory for Dynamic Proliferation Pathway Studies”, 2015 Institute of Electrical and Electronics Engineers Intelligence and Security Informatics Conference, Baltimore, MD, May 27-29, 2015 Abstract: Realistically, no two nuclear proliferating or defensive entities are exactly identical; Agent Based Modeling (ABM) is […]
Passive Neutron Detection in Ports for Homeland Security Applications
Citation: E. Pedicini “Passive Neutron Detection in Ports for Homeland Security Applications”, M.S. Thesis, Texas A & M University, May 2013. Abstract: The smuggling of special nuclear material (SNM) has long been a concern. In April 2009, President Obama declared that a terrorist acquiring a nuclear weapon was the most immediate threat to global security. […]
An Analysis of a Spreader Bar Crane Mounted Gamma Ray Radiation Detection System
Citation: C. Marianno, M. Grypp, “An Analysis of a Spreader Bar Crane Mounted Gamma Ray Radiation Detection System”, 58th Annual Health Physics Society Meeting, Madison, Wisconsin, 10 July 2013. Associated Projects: 1. SHIELD (Smuggled HEU Interdiction through Enhanced anaLysis and Detection): A Framework for Developing Novel Detection Systems Focused on Interdicting Shielded HEU, [updatepublicationbutton ps=’36073′] […]
Utilizing RadResponder in Emergency Response Instruction
Citation: J. Erchinger and C.M. Marianno, “Utilizing RadResponder in Emergency Response Instruction”, 59th Annual Meeting Health Physics Society, Baltimore, Maryland, 13-17 July 2014. [updatepublicationbutton ps=’36072′] [deletepublicationbutton psd=’36072′]
A Radiation Contamination Exercise for Urban Search and Rescue Teams
Citation: C.M. Marianno, M. Smith, J. Trevino, and J. Erchinger, “A Radiation Contamination Exercise for Urban Search and Rescue Teams”, 59th Annual Meeting Health Physics Society, Baltimore, Maryland, 13-17 July 2014. Associated Project: 1. Post RDD-Scenario Dosimetry of Search and Rescue Dogs [updatepublicationbutton ps=’36071′] [deletepublicationbutton psd=’36071′]
Determining Location of a Radiation Source in a Box
Citation: M. Smith, C.M. Marianno, T. Coles, D. Custead, S. Horowitz, T. Lancon, and P. Mendoza, “Determining Location of a Radiation Source in a Box”, 59th Annual Meeting Health Physics Society, Baltimore, Maryland, 13-17 July 2014. [updatepublicationbutton ps=’36070′] [deletepublicationbutton psd=’36070′]
A review of the Indonesian Emergency Response Plan
Citation: M. Volia and C.M. Marianno, “A review of the Indonesian Emergency Response Plan”, 58th Annual Health Physics Society Meeting, Madison, Wisconsin, 10 July 2013. Associated Project: 1. Implementation of Integrated Planning Concept to Strengthen Indonesian Radiation Emergency Response Capabilities [updatepublicationbutton ps=’36067′] [deletepublicationbutton psd=’36067′]
Dose Estimation and Effects of Radioactive Particulate Inhalation in Search and Rescue Dogs”
Citation: J. Trevino and C.M. Marianno, “Dose Estimation and Effects of Radioactive Particulate Inhalation in Search and Rescue Dogs””, 58th Annual Health Physics Society Meeting, Madison, Wisconsin, 10 July 2013. Associated Project: 1. Post RDD-Scenario Dosimetry of Search and Rescue Dogs [updatepublicationbutton ps=’36066′] [deletepublicationbutton psd=’36066′]
Radiological Emergency Response Education: Teaching the Next Generation of Radiation Professionals
Citation: C.M. Marianno, “Radiological Emergency Response Education: Teaching the Next Generation of Radiation Professionals”, 58th Annual Health Physics Society Meeting, Madison, Wisconsin, 10 July 2013. [updatepublicationbutton ps=’36065′] [deletepublicationbutton psd=’36065′]
Radiation Shield Design and Dose Rate Analysis of the Independent Spent Fuel Dry Cask Storage Installation at Commanche Peak Power Plant
Citation: J.W. Poston, S.S. Chirayath, P.V. Tsvetkov, C.M. Marianno, R.P. Kelly, and E.D. Kitcher, “Radiation Shield Design and Dose Rate Analysis of the Independent Spent Fuel Dry Cask Storage Installation at Commanche Peak Power Plant”, Health Physics Society 58th Annual Meeting, Madison, Wisconsin, USA, 7-11, July 2013. [updatepublicationbutton ps=’36023′] [deletepublicationbutton psd=’36023′]
Effect of Grouping Motivations on State Proliferation Pathways
Citation: M. Subbaiah, W.S. Charlton, R. Elmore, R. Coogan, and D. Sweeney, “Effect of Grouping Motivations on State Proliferation Pathways”, 2014 American Nuclear Society Winter Meeting, Annaheim, CA, 9-13 November 2014 Associated Project: 1. Proliferation Resistance Methods Development 2. Analyzing a General Smuggling Network to Optimize the Use of Radiation Portal Monitors for US Homeland […]
Proliferation Resistance Analysis of Nuclear Fuel Cycle Facilities to Quantify the Importance of Containment, Surveillance and Physical Protection Systems
Citation: R.A. Elmore, S.S. Chirayath, and S. Edreev, “Proliferation Resistance Analysis of Nuclear Fuel Cycle Facilities to Quantify the Importance of Containment, Surveillance and Physical Protection Systems”, 2014 American Nuclear Society Winter Meeting, Annaheim, CA, 9-13 November 2014 Abstract: Associated Project: 1. Proliferation Resistance Methods Development 2. Proliferation Resistance Analysis And Evaluation Tool for Observed […]
Comparison of FBR and HFIR Monte-Carlo Simulations with Validation from Gamma Spectroscopy in Support of the NFASP Project
Citation: M.W. Swinney S.S. Chirayath, “Comparison of FBR and HFIR Monte-Carlo Simulations with Validation from Gamma Spectroscopy in Support of the NFASP Project”, 2014 ANS Winter Meeting, Annaheim, CA, 9-13 November 2014 Abstract: The work presented is part of the Nuclear Forensics Analysis of Separated Plutonium for foreign fuel cycles (NFASP) project, an ongoing eort […]
Determining the Effects of Construction Materials on Background Readings for Second Line of Defense Program Portal Monitoring Systems
Citation: C.M. Ryan, C.M. Marianno, W.S. Charlton, A.A. Solodov, J. Livesay, “Determining the Effects of Construction Materials on Background Readings for Second Line of Defense Program Portal Monitoring Systems”, Proceedings of the 51st Annual Meeting of the Institute of Nuclear Materials and Management, Baltimore, MD, USA, July 11-15, 2010. Abstract: Document Link Associated Project: 1. […]
Mass Verification Method for Actinide Mixtures Using a Multi Energy Spectrum Active Well Coincidence Counter
Citation: Braden Goddard, William S. Charlton, Angela L. Lousteau, “Mass Verification Method for Actinide Mixtures Using a Multi Energy Spectrum Active Well Coincidence Counter”, Proceedings of the 51st Annual Meeting of the Institute of Nuclear Materials and Management, Baltimore, MD, USA, July 11-15, 2010. Abstract: Document Link Associated Project: 1. Development of a Mass Verification […]
The Impact of Front End Non-Destructive Assay Techniques on Accountancy Systems at Reprocessing Facilities
Citation: J.S. Feener, W.S. Charlton, “The Impact of Front End Non-Destructive Assay Techniques on Accountancy Systems at Reprocessing Facilities”, Proceedings of the 51st Annual Meeting of the Institute of Nuclear Materials and Management, Baltimore, MD, USA, July 11-15, 2010. Abstract: Document Link [updatepublicationbutton ps=’3470′] [deletepublicationbutton psd=’3470′]
Using MCNP as a Vulnerability Assessment Tool on the TAMU Safeguards Laboratory
Citation: C. Gariazzo, S. Chirayath, “Using MCNP as a Vulnerability Assessment Tool on the TAMU Safeguards Laboratory”, Proceedings of the 51st Annual Meeting of the Institute of Nuclear Materials and Management, Baltimore, MD, USA, July 11-15, 2010. Associated Projects: 1. Novel Detection Technologies for Safeguards and Security Applications, [updatepublicationbutton ps=’3469′] [deletepublicationbutton psd=’3469′]
Latency as a Basis for Safeguards
Citation: D.J. Sweeney and W.S. Charlton, “Latency as a Basis for Safeguards”, Transactions of the 2009 American Nuclear Society Winter Meeting, Washington, D.C., November 15-19, 2009. Associated Project: 1. Nuclear Weapons Latency [updatepublicationbutton ps=’3462′] [deletepublicationbutton psd=’3462′]
Quantifying Nuclear Weapons Latency
Citation: D. Sweeney, J. Slanker, W.S. Charlton, and R. Juzaitis, “Quantifying Nuclear Weapons Latency”, Proceedings of the 2009 Annual Meeting of the Institute of Nuclear Materials Management, Tucson, AZ, July 12-15, 2009. Abstract: Document Link Associated Project: 1. Nuclear Weapons Latency [updatepublicationbutton ps=’3461′] [deletepublicationbutton psd=’3461′]
What Determines the Extent of National Reliance on Civil Nuclear Power?
Citation: P. Nelson and C.M. Sprecher, “What Determines the Extent of National Reliance on Civil Nuclear Power?”, Proceedings of the INMM 49th Annual Meeting, July 2008, Nashville, TN. Associated Project: 1. Motivating Factors of States Seeking to Acquire Civil Nuclear Programs [updatepublicationbutton ps=’3446′] [deletepublicationbutton psd=’3446′]
Where will new nuclear power plants be constructed? Validation of a predictive model
Citation: P. Nelson and C.M. Sprecher, “Where will new nuclear power plants be constructed? Validation of a predictive model”, Proceedings of 31st Annual Meeting of ESARDA, May 26-28, 2009, Vilnius, Lithuania. Abstract: Upload Link Associated Project: 1. Motivating Factors of States Seeking to Acquire Civil Nuclear Programs [updatepublicationbutton ps=’3445′] [deletepublicationbutton psd=’3445′]
Determining the Benefits of Nuclear Material and Arms Control on Nuclear Security
Citation: C. Gariazzo, “Determining the Benefits of Nuclear Material and Arms Control on Nuclear Security”, 55th Annual Meeting of the Institute of Nuclear Materials Management, Atlanta, Georgia, 20-14 July 2014. Abstract: Nations that enter into a nuclear material or arms control agreement do so in an effort to enhance or create trust to mitigate a […]
Towards Safeguarding the Fast Breeder Reactor Fuel Cycle
Citation: S.B. Gerlt, P. Nelson, S Rajgopal, L.V. Krishnan, “Towards Safeguarding the Fast Breeder Reactor Fuel Cycle”, 55th Annual Meeting of the Institute of Nuclear Materials Management, Atlanta, Georgia, 20-14 July 2014. Abstract: The rising need for power for the world’s growing population has increased the demand for reliable energy production. Nuclear energy has been […]
Sharing the US Perspective of Academic Collaboration in Nuclear Nonproliferation, Security, and Safeguards: Texas A&M University and Tomsk Polytechnic University
Citation: C.A. Gariazzo, K. Spence, “Sharing the U.S. Perspective of Academic Collaboration in Nuclear Nonproliferation, Security, and Safeguards: Texas A&M University and Tomsk Polytechnic University”, 55th Annual Meeting of the Institute of Nuclear Materials Management, Atlanta, Georgia, 20-14 July 2014. Abstract: Beginning in 2009 under a research engagement program sponsored by Pacific Northwest National Laboratory […]
Monte Carlo Modeling of the Californium-Interrogation with Prompt Neutron (CIPN) Device for Spent Nuclear Fuel Measurements
Citation: R.M. Zedric, D. Henzlova, W. Charlton, S. Tobin, J. Hendricks, and H. Trellue., “Monte Carlo Modeling of the Californium-Interrogation with Prompt Neutron (CIPN) Device for Spent Nuclear Fuel Measurements”, 55th Annual Meeting of the Institute of Nuclear Materials Management, Atlanta, Georgia, 20-14 July 2014. Abstract: Associated Project: 1. Development Support for the Californium-Interrogation with […]
Trace Fission Product Ratios for Nuclear Forensics Attribution of Weapons-Grade Plutonium Separated from Fuel Irradiated in Thermal and Fast Reactor Types
Citation: J.M. Osborn, T.M. Coles, and S.S. Chirayath, “Trace Fission Product Ratios for Nuclear Forensics Attribution of Weapons-Grade Plutonium Separated from Fuel Irradiated in Thermal and Fast Reactor Types”, 55th Annual Meeting of the Institute of Nuclear Materials Management, Atlanta, Georgia, 20-14 July 2014. Abstract: Associated Project: 1. Plutonium Fingerprinting for Forensics (PuFF) Project [updatepublicationbutton […]
Simulation Analysis of Scintillation in Sodium Iodide Detector
Citation: M.D. Shah, C. Marianno, S.P. Khatri, and D.R. Boyle, “Simulation Analysis of Scintillation in Sodium Iodide Detector”, 55th Annual Meeting of the Institute of Nuclear Materials Management, Atlanta, Georgia, 20-14 July 2014. Abstract: Associated Project: 1. Radiation Detection Using Integrated Circuits [updatepublicationbutton ps=’34273′] [deletepublicationbutton psd=’34273′]
Comparative Analysis of 3S Curriculum
Citation: N. Quintero, R. Khraisat, R. Elmore, J. Erchinger, M. Shah, S. Gerlt, R Zedric, M.T. Bani Ahmad, and Z. Al-Taher, “Comparative Analysis of 3S Curriculum”, 55th Annual Meeting of the Institute of Nuclear Materials Management, Atlanta, Georgia, 20-14 July 2014. Abstract: Document Link [updatepublicationbutton ps=’34272′] [deletepublicationbutton psd=’34272′]
The Use of Self-Induced XRF to Quantify the Pu Content in PWR Spent Nuclear Fuel
Citation: W.S. Charlton, D. Strohmeyer, A. Stafford, S. Saavedra, A.S. Hoover, and C. Rudy, “The Use of Self-Induced XRF to Quantify the Pu Content in PWR Spent Nuclear Fuel”, Proceedings of 31st Annual Meeting of ESARDA, May 26-28, 2009, Vilnius, Lithuania. Abstract: Upload Link Associated Project: 1. Development of Advanced Safeguards Measurement Techniques Using the […]
Measurement of Plutonium in Spent Nuclear Fuel by Self-Induced X-ray Fluorescence
Citation: A. Hoover, W. S. Charlton, M.L. Fensin, A. Rajasingam, C. Rudy, S. Saavedra, A. Stafford, D. Strohmeyer, S. Tobin, “Measurement of Plutonium in Spent Nuclear Fuel by Self-Induced X-ray Fluorescence”, Proceedings of the 2009 Annual Meeting of the Institute of Nuclear Materials Management, Tucson, AZ, July 12-15, 2009. Abstract: Direct measurement of the plutonium […]
Determining Plutonium in Spent Fuel with Nondestructive Assay Techniques
Citation: S.J. Tobin, W.S. Charlton, M.H. Ehinger, M.L. Fensin, A.S. Hoover, H.O. Menlove, B.J. Quiter, A. Rajasingam, N.P. Sandoval, S.F. Saavedra, D. Strohmeyer, M.T. Swinhoe, S.J. Thompson, “Determining Plutonium in Spent Fuel with Nondestructive Assay Techniques”, Proceedings of 31st Annual Meeting of ESARDA, May 26-28, 2009, Vilnius, Lithuania. Abstract: Upload Link Associated Project: 1. Development […]
Modeling X-ray Fluorescence from Spent Fuel Rods
Citation: A. Rajasingam, A.S. Hoover, M.L. Fensin, S.J. Tobin, W.S. Charlton, S. Saavedra, A.A. Stafford, D. Strohmeyer, M.T. Swinhoe, “Modeling X-ray Fluorescence from Spent Fuel Rods”, Proceedings of the 2009 Annual Meeting of the Institute of Nuclear Materials Management, Tucson, AZ, July 12-15, 2009. Abstract: X-Ray Fluorescence (XRF) is one of thirteen non-destructive assay techniques […]
Spent Nuclear Fuel Self-Induced X-ray Fluorescence Simulations for North Anna and TMI
Citation: A. Stafford, W, S. Charlton, J. White, A. Hoover, and S. Saavedra, “Spent Nuclear Fuel Self-Induced X-ray Fluorescence Simulations for North Anna and TMI”, Proceedings of the 2009 Annual Meeting of the Institute of Nuclear Materials Management, Tucson, AZ, July 12-15, 2009. Abstract: Document Link Associated Project: 1. Development of Advanced Safeguards Measurement Techniques […]
Quantification of the Fissile Content of Incoming Spent Nuclear Fuel for the CETE Demonstration through Non-Destructive Assay Techniques
Citation: S. Saavedra, W. Charlton, and A. Solodov, “Quantification of the Fissile Content of Incoming Spent Nuclear Fuel for the CETE Demonstration through Non-Destructive Assay Techniques”, Proceedings of the Institute for Nuclear Materials Management Annual Meeting, July 13-17, 2008. Associated Project: 1. Development of Advanced Safeguards Measurement Techniques Using the Coupled End-to-End (CETE) Demonstration at […]
Applications of X-ray Fluorescence Fission Product Correlations for Nuclear Forensics
Citation: J. White, W.S. Charlton, and A. Solodov, “Applications of X-ray Fluorescence Fission Product Correlations for Nuclear Forensics”, Proceedings of the 51st Annual Meeting for the Institute of Nuclear Materials Management, Baltimore, Maryland, July 11-15, 2010. Abstract: X-ray fluorescence (XRF) and broad range fission product gamma-ray measurements are two promising non-destructive analysis (NDA) techniques for […]
Exploration of X-Ray Fluorescence Spent Nuclear Fuel Source Term
Citation: A.S. Stafford, W.S. Charlton, and C.R. Freeman, “Exploration of X-Ray Fluorescence Spent Nuclear Fuel Source Term”, Proceedings of the 2010 Annual Meeting of the Institute of Nuclear Materials Management, Baltimore, MD, July 11-15, 2010. Abstract: To improve input accountability and shipper/receiver differences at the front end of the reprocessing cycle, nondestructive assay (NDA) techniques […]
The Use of Self-induced XRF to Quantify the Pu Content in MOX Spent Nuclear Fuel
Citation: A.A. Solodov, W.S. Charlton, S. Saavedra, and L. Khodalev, “The Use of Self-induced XRF to Quantify the Pu Content in MOX Spent Nuclear Fuel”, Proceedings of the 2010 Annual Meeting of the Institute of Nuclear Materials Management, Baltimore, MD, July 11-15, 2010. Abstract: Document Link Associated Project: 1. Development of Advanced Safeguards Measurement Techniques […]
Using NDA Techniques to Improve Safeguards Metrics on Burnup Quantification and Plutonium Content in LWR SNF
Citation: S. Saavedra, W. Charlton, A. Solodov, and M. Ehinger, “Using NDA Techniques to Improve Safeguards Metrics on Burnup Quantification and Plutonium Content in LWR SNF”, Proceedings of the 2010 Annual Meeting of the Institute of Nuclear Materials Management, Baltimore, MD, July 11-15, 2010. Abstract: Document Link Associated Project: 1. Development of Advanced Safeguards Measurement […]
Safeguards Envelope: Previous Work and Examples
Citation: R. Metcalf, A. Bevill, W. Charlton, and R. Bean, “Safeguards Envelope: Previous Work and Examples”, Proceedings of 49th Annual INMM Meeting, Nashville, TN, July 13-17, 2008. Abstract: Upload Link Associated Project: 1. The Safeguards Envelope Methodology [updatepublicationbutton ps=’3410′] [deletepublicationbutton psd=’3410′]
Safeguards Envelope: The First Steps
Citation: R. Metcalf, J. Ragusa, and R. Bean, “Safeguards Envelope: The First Steps”, Proceedings of 8th International Conference on Facility Operations – Safeguards Interface, Portland, OR, March 30 – April 4, 2008. Upload Link Associated Project: 1. The Safeguards Envelope Methodology [updatepublicationbutton ps=’3409′] [deletepublicationbutton psd=’3409′]
Real-Time Detection of UREX+3a Extraction Streams for Materials Accountancy
Citation: B. Goddard, W.S. Charlton, and S.M McDeavitt, “Real-Time Detection of UREX+3a Extraction Streams for Materials Accountancy”, Proceedings of the 2009 Annual Meeting of the Institute of Nuclear Materials Management, Tucson, AZ, July 12-15, 2009. Abstract: Document Link Associated Project: 1. Development of a Mass Verification Method For UREX+3a NPEX product Using an Active Well […]
Safeguards for the Uranium Extraction (UREX) +1a Process
Citation: J.S. Feener, and W.S. Charlton, “Safeguards for the Uranium Extraction (UREX) +1a Process”, Proceedings of the 2009 Annual Meeting of the Institute of Nuclear Materials Management, Tucson, AZ, July 12-15, 2009. Abstract: Document Link Associated Project: 1. Real-Time Detection Methods to Monitor TRU Composition in the UREX + Process Stream [updatepublicationbutton ps=’3405′] [deletepublicationbutton psd=’3405′]
Thorium blended and regular MOX burn-up studies for fast reactor fuel cycle safeguards
Citation: S.S. Chirayath, J. Ragusa, and P. Nelson, “Thorium blended and regular MOX burn-up studies for fast reactor fuel cycle safeguards”, Proceedings of 50th annual meeting of INMM, July 12-16, 2009, Tucson, AZ, USA. Abstract: Upload Link Associated Project: 1. Safeguards Approaches for Fast Breeder Reactors and Associated Fuel Cycle Facilities [updatepublicationbutton ps=’3390′] [deletepublicationbutton psd=’3390′]
Developing a Safeguards Approach for a Small Graphite Moderated Reactor and Associated Fuel Cycle Facilities
Citation: E.B. Rauch, W.S. Charlton, and D.G. Ford, “Developing a Safeguards Approach for a Small Graphite Moderated Reactor and Associated Fuel Cycle Facilities”, Proceedings of the 2009 Annual Meeting of the Institute of Nuclear Materials Management, Tucson, AZ, July 12-15, 2009. Abstract: Document Link Associated Project: 1. Safeguards Approaches for Fast Breeder Reactors and Associated […]
Assessment of Proliferation Resistance Requirements for Fast-Reactor Fuel-Cycle Facilities
Citation: S. Chirayath, R. Metcalf, J. Ragusa, P. Nelson “Assessment of Proliferation Resistance Requirements for Fast-Reactor Fuel-Cycle Facilities”, Proceedings of the 8th International Conference on Facility Operations – Safeguards Interface, Portland, Oregon, March 30 – April 4, 2008. Abstract: Inclusion of intrinsic safeguards in fast reactor systems could lower one of the barriers to a […]
Risk Informed Safeguards Integration Studies for a Fast Reactor Fuel Cycle
Citation: S. Chirayath, W. Charlton, A. Stafford, C. Myers, B. Goddard, J. Alfred, M. Carroll, M. Sternat, E. Rauch, “Risk Informed Safeguards Integration Studies for a Fast Reactor Fuel Cycle”, Proceedings of the 51st Annual Meeting of the Institute of Nuclear Materials and Management, Baltimore, MD, USA, July 11-15, 2010. Abstract: Fast reactors with a […]
Feasibility Study of a Portable Coupled 3He Neutron Detector with LaBr3 Gamma Scintillator for the Purpose of Plutonium Identification and Quantification
Citation: D.C. Strohmeyer and W.S. Charlton, “Feasibility Study of a Portable Coupled 3He Neutron Detector with LaBr3 Gamma Scintillator for the Purpose of Plutonium Identification and Quantification”, Proceedings of 31st Annual Meeting of ESARDA, May 26-28, 2009, Vilnius, Lithuania. Abstract: Upload Link Associated Project: 1. Safeguards Instrumentation Development for Measuring Pu via Coincident Neutron-Gamma Signals […]
Characterization of a Portable Neutron Coincidence Counter
Citation: A. Thornton W. Charlton “Characterization of a Portable Neutron Coincidence Counter”, Annual Meeting of the Institute for Nuclear Materials Management, July 8-12, 2007, Tucson, AZ. Abstract: Neutron coincidence counting is a technique widely used for qualitative and quantitative analysis of nuclear material. Because different isotopes possess different coincident neutron characteristics, the coincident neutron signature […]
Development of Self-Interrogation Neutron Resonance Densitometry (SINRD) to Measure the 235U and 239Pu Content in a PWR 17×17 Spent Fuel Assembly
Citation: A.M. LaFleur, W.S. Charlton, H.O. Menlove, and M. Swinhoe, “Development of Self-Interrogation Neutron Resonance Densitometry (SINRD) to Measure the 235U and 239Pu Content in a PWR 17×17 Spent Fuel Assembly”, Proceedings of 31st Annual Meeting of ESARDA, May 26-28, 2009, Vilnius, Lithuania. Abstract: Upload Link Associated Project: 1. Development of Self-Interrogation Neutron Resonance Densitometry […]
Nondestructive Measurements of Fissile Material Using Self-Indication Neutron Resonance Absorption Densitometry (SINRAD)
Citation: A.M. LaFleur, W.S. Charlton, H.O. Menlove, M. Swinhoe “Nondestructive Measurements of Fissile Material Using Self-Indication Neutron Resonance Absorption Densitometry (SINRAD)”, Proceedings of 8th International Conference on Facility Operations – Safeguards Interface, Portland, OR, March 30 – April 4, 2008. Abstract: The use of self-indication neutron resonance absorption densitometry (SINRAD) to nondestructively measure the concentration […]
Use of Self-Interrogation Neutron Resonance Densitometry (SINRD) to Measure the Fissile Content in Nuclear Fuel
Citation: A.M. LaFleur, W.S. Charlton, H.O. Menlove, M. Swinhoe “Use of Self-Interrogation Neutron Resonance Densitometry (SINRD) to Measure the Fissile Content in Nuclear Fuel”, Proceedings of 49th Annual INMM Meeting, Nashville, TN, July 13-17, 2008. Abstract: We investigated a new method to verify the concentration of fissile material in a PWR fresh fuel assembly using […]
Experimental Benchmark of MCNPX Calculations Against Self-Interrogation Neutron Resonance Densitometry (SINRD) Fresh Fuel Measurements
Citation: A.M. LaFleur, W.S. Charlton, H.O. Menlove, M.T. Swinhoe, S.Y. Lee, S.J. Tobin, “Experimental Benchmark of MCNPX Calculations Against Self-Interrogation Neutron Resonance Densitometry (SINRD) Fresh Fuel Measurements”, Proceedings of the 51st Annual Meeting for the Institute of Nuclear Materials Management, Baltimore, Maryland, July 11-15, 2010. Abstract: Document Link Associated Project: 1. Development of Self-Interrogation Neutron […]
Development of a Custom Portal Monitor for Detection of Radioactive Contamination on Livestock
Citation: J. Erchinger, C. Marianno, and A. Herring, “Development of a Custom Portal Monitor for Detection of Radioactive Contamination on Livestock”, 58th Annual Health Physics Society Meeting, Madison, Wisconsin, 10 July 2013. Associated Project: 1. Effective Contamination Detection for Livestock Following a Radiological Event [updatepublicationbutton ps=’33590′] [deletepublicationbutton psd=’33590′]
Risk Analysis and Management of State Nuclear Security Measures
Citation: C.T. Myers, W.S. Charlton, and D.G. Ford, “Risk Analysis and Management of State Nuclear Security Measures”, Proceedings of the 51st Annual Meeting for the Institute of Nuclear Materials Management, Baltimore, Maryland, July 11-15, 2010. Associated Project: 1. State-Level Nuclear Security Measures [updatepublicationbutton ps=’3359′] [deletepublicationbutton psd=’3359′]
A Guide for Detector Development and Deployment
Citation: C.M. Marianno, D.R. Boyle, W.S. Charlton, G.M. Gaukler, and A. Veditz, “A Guide for Detector Development and Deployment”, Proceedings of the 51st Annual Meeting of the Institute of Nuclear Materials and Management, Baltimore, MD, USA, July 11-15, 2010. Abstract: Upload Link Associated Project: 1. SHIELD (Smuggled HEU Interdiction through Enhanced anaLysis and Detection): A […]
A Radiation Tolerant Phase Locked Loop Design for Digital Electronics
Citation: R. Kumar, V. Karkala, R. Garg, T. Jindal, and S. Khatri, “A Radiation Tolerant Phase Locked Loop Design for Digital Electronics”, Paper presented at the IEEE International Conference on Computer Design, Lake Tahoe, California, October 4-7, 2009. Abstract: Document Link Associated Project: 1. SHIELD (Smuggled HEU Interdiction through Enhanced anaLysis and Detection): A Framework […]
3D Simulation and Analysis of the Radiation Tolerance of Voltage Scaled Digital Circuit
Citation: R. Garg and S. Khatri, “3D Simulation and Analysis of the Radiation Tolerance of Voltage Scaled Digital Circuit”, Paper presented at the IEEE International Conference on Computer Design, Lake Tahoe, California, October 4-7, 2009. Abstract: Upload Link Associated Project: 1. SHIELD (Smuggled HEU Interdiction through Enhanced anaLysis and Detection): A Framework for Developing Novel […]
3D Simulation and Analysis of the Radiation Tolerance of Voltage Scaled Digital Circuits
Citation: R. Garg and S. Khatri, “3D Simulation and Analysis of the Radiation Tolerance of Voltage Scaled Digital Circuits”, Presented at the 2009 IEEE Workshop on Silicon Errors in Logic – System Effects, Stanford, CA, March 24-25, 2009. Abstract: Upload Link Associated Project: 1. SHIELD (Smuggled HEU Interdiction through Enhanced anaLysis and Detection): A Framework […]
Nuclear Proliferation Resistance Model Backgrounds and Method Comparative Analysis
Citation: R. Elmore, W.S. Charlton, S. Chirayath, “Nuclear Proliferation Resistance Model Backgrounds and Method Comparative Analysis”, 84th Annual National Technical Association Conference, Baltimore, MD, 19-21 September 2012. Associated Project: 1. Proliferation Resistance Methods Development 2. Proliferation Resistance Analysis And Evaluation Tool for Observed Risk (PRAETOR) [updatepublicationbutton ps=’33419′] [deletepublicationbutton psd=’33419′]
Comparative Analysis of Nuclear Nonproliferation Proliferation Resistance Approaches
Citation: R. Elmore, W.S. Charlton, S. Chirayath, “Comparative Analysis of Nuclear Nonproliferation Proliferation Resistance Approaches”, Transactions of the 2012 American Nuclear Society Winter Meeting, San Diego, CA, 11-15 November 2012. Associated Project: 1. Proliferation Resistance Methods Development [updatepublicationbutton ps=’33418′] [deletepublicationbutton psd=’33418′]
Sensitivity Analysis with PRAETOR for Diversion of Plutonium Self-Protected with Pu-238
Citation: R. Elmore, W.S. Charlton, S. Chirayath, “Sensitivity Analysis with PRAETOR for Diversion of Plutonium Self-Protected with Pu-238”, Transactions of the 2013 American Nuclear Society Winter Meeting, Washington, D.C., 10-14 November 2013. Associated Project: 1. Proliferation Resistance Methods Development 2. Proliferation Resistance Analysis And Evaluation Tool for Observed Risk (PRAETOR) [updatepublicationbutton ps=’33417′] [deletepublicationbutton psd=’33417′]
Real-Time Detection of UREX+3a Extraction Streams for Materials Accountancy
Citation: B. Goddard “Real-Time Detection of UREX+3a Extraction Streams for Materials Accountancy”, M.S. Thesis, Texas A & M University, December 2009. Abstract: Reprocessing nuclear fuel is becoming more viable in the United States due to the anticipated increase in construction of nuclear power plants, the growing stockpile of existing used nuclear fuel, and a public […]
Preliminary Results of Nuclear Fluorescence Imaging of Alpha and Beta Emitting Sources
Citation: J. S. Feener and W. S. Charlton, “Preliminary Results of Nuclear Fluorescence Imaging of Alpha and Beta Emitting Sources”, Advancements in Nuclear Instrumentation Measurement Methods and their Applications 3rd Conference, Marseille, France, 23-27 June 2013. Abstract: Document Link Associated Project: 1. Fluorescence Imaging for Nuclear Arms Control Verification [updatepublicationbutton ps=’33403′] [deletepublicationbutton psd=’33403′]
Detecting Detection. Preventing the proliferation of HEU in Central Asia and the Middle East
Citation: C. Sprecher and D. Kuberski, “Detecting Detection. Preventing the proliferation of HEU in Central Asia and the Middle East”, ISAC/ISSS Annual Conference on Globalization and Security: Foreign Policy in the New Administration, Vail, CO. October 23-25, 2008. Associated Project: 1. SHIELD (Smuggled HEU Interdiction through Enhanced anaLysis and Detection): A Framework for Developing Novel […]
A Positive Non-Linear Closure for the SN Equations with Linear-Discontinuous Spatial Differencing
Citation: P. Maginot, J. Morel, and J. Ragusa, “A Positive Non-Linear Closure for the SN Equations with Linear-Discontinuous Spatial Differencing”, Proceedings of the International Conference on Mathematics, Computational Methods & Reactor Physics (M&C 2009) Saratoga Springs, New York, May 3-7, 2009. Abstract: Upload Link Associated Project: 1. SHIELD (Smuggled HEU Interdiction through Enhanced anaLysis and […]
Directionally Sensitive Neutron Detectors for Portal Monitors
Citation: G.R. Spence and W.S. Charlton, “Directionally Sensitive Neutron Detectors for Portal Monitors”, Proceedings of the 2009 Annual Meeting of the Institute of Nuclear Materials Management, Tucson, AZ, July 12-15, 2009. Associated Project: 1. Direction Sensitive Neutron Detectors for Border Monitoring 2. SHIELD (Smuggled HEU Interdiction through Enhanced anaLysis and Detection): A Framework for Developing […]
An Inverse Transport Approach to Radiation Source Location for Border Security
Citation: K.A. Miller W.S. Charlton “An Inverse Transport Approach to Radiation Source Location for Border Security”, Proceedings of the 29th Annual Meeting of the European Safeguards Research and Development Association, Aix-en-Provence, France, May 22-24, 2007. Abstract: Radiation portal monitors are being deployed at border crossings throughout the world to help prevent against the smuggling of […]
An Inverse Source Location Algorithm for Radiation Portal Monitor Applications
Citation: K.A. Miller and W.S. Charlton, “An Inverse Source Location Algorithm for Radiation Portal Monitor Applications”, Proceedings of the 2010 Annual Meeting of the Institute of Nuclear Materials Management, Baltimore, MD, July 11-15, 2010. Abstract: Document Link Associated Project: 1. Inverse Transport for Border Monitoring 2. SHIELD (Smuggled HEU Interdiction through Enhanced anaLysis and Detection): […]
An Inverse Method for Locating a Radioactive Source Using a Distributed Array of Detectors
Citation: K.A. Miller and W.S. Charlton, “An Inverse Method for Locating a Radioactive Source Using a Distributed Array of Detectors”, Transactions of the 2010 American Nuclear Society Annual Meeting, San Diego, CA, June 13-17, 2010. Associated Project: 1. Inverse Transport for Border Monitoring 2. SHIELD (Smuggled HEU Interdiction through Enhanced anaLysis and Detection): A Framework […]
Analytical Inverse Model for Post-Nuclear Event Attribution of Plutonium
Citation: J. Miller W. Charlton “Analytical Inverse Model for Post-Nuclear Event Attribution of Plutonium”, Annual Meeting of the Institute for Nuclear Materials Management, July 8-12, 2007, Tucson, AZ. Abstract: An integral part of deterring nuclear terrorism is the swift attribution of any event to a particular state or organization. By quickly being able to identify […]
A Method for Determining Material Attributes from Postdetonation Fission Product Measurements of an HEU Device
Citation: A.M. LaFleur and W.S. Charlton, “A Method for Determining Material Attributes from Postdetonation Fission Product Measurements of an HEU Device”, Proceedings of 46th Annual INMM Meeting, Nashville, TN, July 16-20, 2006. Upload Link Associated Project: 1. Advancing Methods for Providing Attribution for the HEU Used in a Terrorist Nuclear Weapon [updatepublicationbutton ps=’3299′] [deletepublicationbutton psd=’3299′]
A Brief Sensitivity Analysis for the GIRM and Other Related Technique using a One-Group Cross Section Library for Graphite-Moderated Reactors
Citation: K.E. Chesson W.S. Charlton “A Brief Sensitivity Analysis for the GIRM and Other Related Technique using a One-Group Cross Section Library for Graphite-Moderated Reactors”, Proceedings of the 29th ESARDA Annual Meeting, Aix-en-Provence, France, May 22-24, 2007. Abstract: Several methods have been developed previously for estimating cumulative energy production and plutonium production from graphite-moderated reactors. […]
A Brief Sensitivity Analysis for the GIRM and Other Related Techniques using a One-Group Cross Section Library for Graphite-Moderated Reactors
Citation: K.E. Chesson W.S. Charlton “A Brief Sensitivity Analysis for the GIRM and Other Related Techniques using a One-Group Cross Section Library for Graphite-Moderated Reactors”, Annual Meeting of the Institute for Nuclear Materials Management, July 8-12, 2007, Tucson, AZ. Abstract: Several methods have been developed previously for estimating cumulative energy production and plutonium production from […]
Assessment Tool for Nuclear Weapon Acquisition Pathways
Citation: W.S. Charlton D.G. Ford “Assessment Tool for Nuclear Weapon Acquisition Pathways”, Annual Meeting of the Institute for Nuclear Materials Management, July 8-12, 2007, Tucson, AZ. Abstract: An assessment tool has been developed at Texas A&&&&M University for predicting weapons useable material acquisition based on an acquisition network simulation. The network has been designed to […]
Determining Acquisition Pathways for a Radiological Dispersal Device
Citation: G.R. Hundley, W.S. Charlton, and K. Childress, “Determining Acquisition Pathways for a Radiological Dispersal Device”, Proceedings of the 51st Annual Meeting for the Institute of Nuclear Materials Management, Baltimore, Maryland, July 11-15, 2010. Abstract: Document Link Associated Project: 1. Terrorism Pathway Analysis and Assessments [updatepublicationbutton ps=’3277′] [deletepublicationbutton psd=’3277′]
Benchmarking TransLAT for Fission Product Generation
Citation: D. Sweeney and W.S. Charlton, “Benchmarking TransLAT for Fission Product Generation”, Proceedings of the PHYSOR 2010, Pittsburgh, PA, May 9-14, 2010. Associated Project: 1. Transparency Methods Development using Fission Product Signatures [updatepublicationbutton ps=’3272′] [deletepublicationbutton psd=’3272′]
Physical Mechanisms for Fission Product Concentration Differences from Variations in Reactor Power History
Citation: D.J. Sweeney W.S. Charlton “Physical Mechanisms for Fission Product Concentration Differences from Variations in Reactor Power History”, Proceedings of 49th Annual INMM Meeting, Nashville, TN, July 13-17, 2008. Abstract: A method for uniquely determining power history characteristics of spent fuel assemblies based on the concentration of various fission products in the fuel assembly has […]
Reactor Power History from Fission Product Signatures
Citation: D.J. Sweeney W.S. Charlton “Reactor Power History from Fission Product Signatures”, Proceedings of 48th Annual INMM Meeting, Tucson, AZ, July 8-12, 2007. Abstract: The purpose of this research was to identify fission product signatures that could be used to uniquely identify a specific spent fuel assembly in order to improve international safeguards. This capability […]
Reactor Physics Modeling of Spent Nuclear Research Reactor Fuel for SNM Attribution and Nuclear Forensics
Citation: M.R. Sternat, W.S. Charlton, T.S. Nichols, R. Webb, and D.M. Beals, “Reactor Physics Modeling of Spent Nuclear Research Reactor Fuel for SNM Attribution and Nuclear Forensics”, Proceedings of the 51st Annual Meeting for the Institute of Nuclear Materials Management, Baltimore, Maryland, July 11-15, 2010. Abstract: Document Link Associated Project: 1. Uncertainty Quantification for Nuclear […]
A Flexible, Si-Based Neutron Detector for Safeguards Applications
Citation: C. Gariazzo, C. Marianno, D. Cui, X. Cheng, L. Shao, “A Flexible, Si-Based Neutron Detector for Safeguards Applications”, Proceedings of the 51st Annual Meeting for the Institute of Nuclear Materials Management, Baltimore, Maryland, July 11-15, 2010. Abstract: Neutron detectors are useful tools for detecting radioactive material in safeguard and homeland security applications. Unlike photons […]
Nuclear Fuel Cycle Assessment of India: A Technical Study for Nuclear Cooperation
Citation: T. Woddi, W.S. Charlton, Paul Nelson, Jean Ragusa, “Nuclear Fuel Cycle Assessment of India: A Technical Study for Nuclear Cooperation”, Proceedings of the 29th ESARDA Annual Meeting, Aix-en-Provence, France, May 22-24, 2007. Abstract: The recent civil nuclear cooperation proposed by the Bush Administration and Government of India has heightened the necessity of assessing India1″s […]