# positions[].organizations[].label
Institute for Engineering Education and Innovation

# positions[].organizations[].parent[].label
Texas A&M Engineering Experiment Station (TEES)

# keywords[]
Estimate Of Adversary Sequence Interruption

# keywords[]
3505 Human Resources And Industrial Relations

# keywords[]
35 Commerce, Management, Tourism And Services

# keywords[]
4019 Resources Engineering And Extractive Metallurgy

# keywords[]
4012 Fluid Mechanics And Thermal Engineering

# keywords[]
16 Peace, Justice And Strong Institutions

# keywords[]
3507 Strategy, Management And Organisational Behaviour

# keywords[]
35 Commerce, Management, Tourism And Services

# keywords[]
Ion Beam Induced Charge (ibic) Technique

# keywords[]
3505 Human Resources And Industrial Relations

# keywords[]
35 Commerce, Management, Tourism And Services

# keywords[]
4019 Resources Engineering And Extractive Metallurgy

# keywords[]
4012 Fluid Mechanics And Thermal Engineering

# educationAndTraining[].organization.label
University of Calicut - (Malappuram, Kerala, India)

# educationAndTraining[].organization.label
Texas A&M University - (College Station, Texas, United States)

# educationAndTraining[].organization.label
University of Madras - (Chennai, Tamil Nadu, India)

# educationAndTraining[].organization.label
University of Calicut - (Malappuram, Kerala, India)

# publications[].label
Nuclear forensics methodology identifies legacy plutonium from the Manhattan Project

# publications[].label
Nuclear Security Risk Analysis: An Insider-Outsider Collusion Scenario

# publications[].label
Safeguards analysis of pyroprocessing product ingot diversions possible through neutron source substitutions

# publications[].label
Design and Analysis of an Internal Remote Monitoring System for Spent Nuclear Fuel Stored in a Dry Cask

# publications[].label
A Novel Nuclear Material Control Technique for Pebble Bed Reactors

# publications[].label
Correlation Between Exposure Rate and Residual Activity in Felines Undergoing 131I Thyroid Ablation Therapy.

# publications[].label
Ten years of nuclear security education, research and training at Texas A&M University

# publications[].label
Analysis of a sustainable gas cooled fast breeder reactor concept

# publications[].label
Sensitivity studies on a novel nuclear forensics methodology for source reactor-type discrimination of separated weapons grade plutonium

# publications[].label
Game-based Learning in Non-proliferation at Argonne National Laboratory and Texas A&M University

# publications[].label
Uncertainty Quantification of Fission Product Concentration Estimation in MCNP Fuel Depletion Simulations

# publications[].label
A simple and low-cost directional detection technique for radiation source localization for nuclear security applications

# publications[].label
Characterization of plutonium for nuclear forensics using machine learning techniques

# publications[].label
Assessment of proliferation resistance requirements for fast-reactor fuel-cycle facilities

# publications[].label
Generation of view factors for RELAP5 using MCNP

# publications[].label
Investigations on the Pu-to-244Cm ratio method for Pu accountancy in pyroprocessing

# publications[].label
Investigations on Detecting Potential Nuclear Material Diversion from a Pyroprocessing Facility

# publications[].label
Semi-empirical analysis of the spatial variation of Pu quality ratio in a reactor core for application in pyroprocessing of used nuclear fuel

# publications[].label
The Nuclear Security Science Policy Institute at Texas A&M University

# publications[].label
Detecting nuclear materials smuggling: performance evaluation of container inspection policies.

# publications[].label
Neutronics performance analysis of a small modular integral pressurized water reactor

# publications[].label
Neutronic and nonproliferation characteristics of (PuO2-UO2) and (PuO2-ThO2) as fast reactor fuels

# publications[].label
Measuring key Sm isotope ratios in irradiated UO2 for use in plutonium discrimination nuclear forensics

# publications[].label
Bias-dependent displacement damage effects in a silicon avalanche photodiode

# publications[].label
Improving a multi-physics coupling scheme for the analysis of xenon-induced power oscillations

# publications[].label
View-CXS neutron and photon cross-sections viewer

# publications[].label
High temperature super-critical CO<inf>2</inf>-cooled integrated multi-modular thermal reactor

# publications[].label
Statistical analysis of fission product concentration uncertainties from MCNP6 multi-time step depletion calculation

# publications[].label
Experimental Verification of Proposed Internal Remote Monitoring System for Spent Nuclear Fuel Dry Cask Storage Applications

# publications[].label
A neutron transport and thermal hydraulics coupling scheme to study xenon induced power oscillations in a nuclear reactor

# publications[].label
Analysis of x-ray spectrum obtained in electron cyclotron resonance x-ray source

# publications[].label
Computational evaluation of a novel beta radiation probe design using integrated circuits

# publications[].label
A new methodology to estimate stochastic uncertainty of MCNP-predicted isotope concentrations in nuclear fuel burnup simulations

# publications[].label
Investigation of void formations using neutron measurements in filler materials for dual-purpose canisters

# publications[].label
Proliferation resistance analysis of nuclear fuel cycle facilities to quantify the importance of containment, surveillance and physical protection systems

# publications[].label
Implementation of a machine learning technique for estimating gamma direction using a coaxial High Purity Germanium detector

# publications[].label
Investigation of Enriched Reprocessed Uranium Fuel for Inherent Protection of Uranium and Plutonium against Proliferation

# publications[].label
Neutron Measurements and Monte Carlo Simulations of Spent Nuclear Fuel in Dry Cask Storage Using a New Remote Monitoring System Prototype

# publications[].label
Roadmap for a Sustainable Professional Pipeline: The Nuclear Security Education Program at the Center for Nuclear Security Science and Policy Initiatives (NSSPI) at Texas A&M University

# publications[].label
Nondestructive and destructive assay for forensics characterization of weapons-grade plutonium produced in LEU irradiated in a thermal neutron spectrum

# publications[].label
Material balance area design for the transuranic fuel cycle employing high temperature gas cooled reactors

# publications[].label
Assessment of Collective Radiation Dose Budget for PHWR Stations

# publications[].label
Methodology development for combined evaluation of security and safety risk

# publications[].label
Effects of multi-recycling of uranium reprocessed from spent nuclear fuel on the proliferation resistance of plutonium and uranium

# publications[].label
Proliferation resistance of light water reactor versus pebble bed reactor

# publications[].label
The cost-benefit analysis of the optimal Type-I () and Type-II () error values for nuclear material accounting and safeguards

# publications[].label
VVER-1000 MOX Core Computational Benchmark analysis using indigenous codes EXCEL, TRIHEX-FA and HEXPIN

# publications[].label
Analysis of advanced fuel assemblies for the LWRs

# publications[].label
Developing a mathematical scheme to combine single-parameter perturbation results in radiation transport calculations to predict joined parameter perturbations

# publications[].label
Antineutrino detection for temporal monitoring of fuel burnup in a large nuclear reactor

# publications[].label
Doppler Coefficient of Reactivity - Benchmark Calculations for Different Enrichments of UO2

# publications[].label
Nuclear fuel reprocessing: Can pyro-processing reduce nuclear proliferation risk?

# publications[].label
Uncertainty Quantification of Plu- tonium Inventory Calculations through Xenon Gas Sampling of Underground Waste Tanks containing High-Level Radioactive Waste from Uranium Reprocessing

# publications[].label
Computational and experimental forensics characterization of weapons-grade plutonium produced in a thermal neutron environment

# publications[].label
Detecting nuclear materials smuggling: using radiography to improve container inspection policies

# publications[].label
UNCERTAINTY QUANTIFICATION OF CONCRETE UTILIZED IN DRY CASK STORAGE

# publications[].label
Nuclear forensics signature analysis of fast and thermal reactor produced weapons-grade plutonium

# publications[].label
MAPPS: A stochastic computational tool for multi-path analysis of physical protection systems

# publications[].label
A Machine Learning Method for the Forensics Attribution of Separated Plutonium

# publications[].label
Proliferation resistance evaluation of an HTGR transuranic fuel cycle using PRAETOR code

# publications[].label
Monte Carlo neutronics benchmarks on nuclear fuel depletion: A review

# publications[].label
Proliferation resistance assessment of a typical pebble bed reactor fuel

# publications[].label
Fission product decontamination factors for plutonium separated by PUREX from low-burnup, fast-neutron irradiated depleted UO2.

# publications[].label
Road to a Sustainable Human Reliability Program and Implementation Strategy

# publications[].label
Proposal for improved nuclear fuel utilisation and economic performance by utilising thorium

# publications[].label
Effects of Reprocessed Uranium Multi-Recycle on Proliferation Resistance of Plutonium and Uranium

# publications[].label
ASSESSMENT OF THE FINGERPRINTING METHOD FOR THE VERIFICATION OF SPENT FUEL IN MACSTOR KN-400 CANDU SPENT-FUEL DRY STORAGE

# publications[].label
Proliferation Resistance Analysis and Evaluation Tool for Observed Risk (PRAETOR) Methodology

# publications[].publisher
The Institute of Nuclear Materials Management

# publications[].label
Investigation of Nuclear Safeguards Attributes Through Neutronics Simulation of Pebble Bed Reactor Core

# publications[].label
Simulation of Electron Linear Accelerator Head for 6MV Photon Beam Dose Calculations in Water Phantom Using Monte Carlo Methods

# publications[].label
Experiences with International Collaborations in Nuclear Engineering Research and Educational Exchanges-Panel

# publications[].label
Information driven safeguards approach for remote monitoring system of dry cask storage

# publications[].label
Analysis of the DPRK's Nuclear Weapons Capabilities by Estimating Its Highly Enriched Uranium Stockpile and Natural Uranium Reserves

# publications[].label
Evaluation of nuclear material accountability by the probability of detection for loss of Pu (LOPu) scenarios in pyroprocessing

# publications[].label
Evaluation of dosimetric parameters for various 192Ir brachytherapy sources under unbounded phantom geometry by Monte Carlo simulation.

# publications[].label
Nondestructive and Destructive Assay for Forensics Characterization of Weapons-Grade Plutonium Produced in Leu Irradiated in a Thermal Neutron Spectrum

# publications[].label
Physical protection system vulnerability assessment of a small nuclear research reactor due to TNT-shaped charge impact on its reinforced concrete wall

# publications[].label
Nuclide composition non-uniformity in used nuclear fuel for considerations in pyroprocessing safeguards

# publications[].label
Insider Threat Case Studies from Industry

# publications[].label
The impact of refueling schemes on the proliferation resistance of a pebble bed reactor

# publications[].label
Methodology for public safety, proliferation, and economics assessment of SMRs

# publications[].label
Sensitivity analysis with PRAETOR for diversion of plutonium self-protected with Pu-238

# publications[].label
KAMINI Reactor South Beam Port Shield-Structure Optimization

# publications[].label
Validation and Application of Transport Theory Methods for Predicting Neutron Detector Readings in FBR In-core Shields

# publications[].label
Proliferation resistance evaluation of an advanced fuel cycle employing high temperature gas cooled reactors

# publications[].label
Attribution of Separated Plutonium using Machine Learning Techniques

# publications[].label
Comparison of FBR and HFIR Monte-Carlo simulations with validation from gamma spectroscopy in support of the NFASP project

# publications[].label
Analysis of Routine Radiological Measurements in a Nuclear Power Plant

# publications[].label
A Review of Human Reliability Programs for Nuclear Security

# publications[].publisher
The Institute of Nuclear Materials Management

# publications[].label
Nuclear Science and Security Education Laboratory at Amity  Off-Line and On-line Facility Development

# publications[].label
Separated Plutonium Attribution Using Machine Learning Techniques

# publications[].label
Floating Micro-Modular Reactor Concept for Localized Outages

# publications[].label
Comparative analysis of nuclear nonproliferation proliferation resistance approaches

# publications[].label
Analysis of a generic small modular integral pressurized water reactor: Burnable absorber rod materials

# publications[].label
Safety Evaluation of a Spent Fuel Dry-Storage Canister with Various Fill Materials

# publications[].label
Combined nuclear safety-security risk analysis methodology development and demonstration through a case study

# publications[].label
Safeguards Approaches for Remote Monitoring System of Spent Nuclear Fuel Dry Cask Storage

# publications[].label
Experimental and Computational Verification of a New Remote Monitoring System Design for Spent Fuel Dry Cask Safeguards Using Small-Scale, Generic Diversion Scenarios

# publications[].label
A VVER-1000 LEU and MOX assembly computational benchmark analysis using the lattice burnup code EXCEL

# publications[].label
Influence of the spatial Pu variation for evaluating the Pu content in spent nuclear fuel using Support Vector Regression

# publications[].label
Nuclear Forensics Methodology for Reactor-Type Attribution of Chemically Separated Plutonium

# publications[].label
Trace Fission Product Ratios for Nuclear Forensics Attribution of Weapons-Grade Plutonium from Fast and Thermal Reactors

# publications[].tags
16 Peace, Justice and Strong Institutions

# publications[].label
Assessing the nuclear weapons proliferation risks in nuclear energy newcomer countries: The case of small modular reactors

# publications[].label
Experimental and Computational Forensics Characterization of Weapons-Grade Plutonium Produced in a Fast Reactor Neutron Environment

# publications[].label
Isolating trace fission product elements in separated plutonium for applications in nuclear forensics

# publications[].label
Using Machine Learning Techniques to Verify Mixed Plutonium Sample Attributes

# publications[].label
Insider Threats and Strategies to Manage Insider Risk

# publications[].label
Analysis of Destructive and Nondestructive Assays of Irradiated LEU Fuel Material for the Validation of MCNP and Nuclear Forensics Methodologies

# publications[].label
Computation of relative dose distribution and effective transmission around a shielded vaginal cylinder with 192Ir HDR source using MCNP4B.

# publications[].label
Fuel Pebbles Theft Analysis for Physical Protection System Development

# publications[].label
Challenges in nuclear energy adoption: Why nuclear energy newcomer countries put nuclear power programs on hold?

# publications[].label
Review: Monte Carlo Neutronics Validation Studies of Burned Nuclear Material

# publications[].label
Investigation of Iran's Nuclear Weapon Latency Time in Case of Non-Compliance with JCPOA

# publications[].label
Validation of a Machine Learning-Based Nuclear Forensics Methodology for the Discrimination of a Chemically Separated Plutonium Sample from Low-Enriched Uranium

# publications[].label
Uncertainty analysis of fission product concentrations in MCNP depletion calculations

# publications[].label
Dose distribution for endovascular brachytherapy using Ir-192 sources: comparison of Monte Carlo calculations with radiochromic film measurements.

# publications[].label
Nondestructive and Destructive Assay for Forensics Characterization of Weapons-Grade Plutonium Produced in Leu Irradiated in a Thermal Neutron Spectrum

# publications[].label
A Method to Estimate Fission Product Concentration Uncertainty in a Multi-Time-Step MCNP6 Code Nuclear Fuel Burnup Calculation

# publications[].label
Review of Monte Carlo Neutronics Isotopic Validation Studies on Nucler Fuel Depletion

# publications[].label
The Effect of Radiation Damage on the Charge Collection Efficiency of Silicon Avalanche Photodiodes

# publications[].publisher
Institute of Electrical and Electronics Engineers (IEEE)

# publications[].label
Neutronics and thermal hydraulics analysis of a small modular reactor

# publications[].label
Experimental and Computational Verification of a New Remote Monitoring System Design for Spent Fuel Dry Cask Safeguards

# publications[].label
Probabilistic risk assessment of spent fuel pool cooling system failure considering safety & security initiating events

# publications[].label
Development of an ALARA Program based on Radiological Measurements at a Nuclear Power Plant

# publications[].label
Shield structure optimisation studies for the west beam port of the KAMINI reactor

# publications[].label
A gamma spectroscopy-based non-destructive approach for pebble bed reactor safeguards

# publications[].label
Proliferation resistance of light water reactor versus pebble bed reactor (vol 188, pg 1, 2023)

# publications[].label
Experimental validation of a nuclear forensics methodology for source reactor-type discrimination of chemically separated plutonium

# researcherOn[].label
Experimental and Computational Assessment of Fission Product Residue in Plutonium From Low-Burn-Up Thermal Reactor Fuel and Gaussian Inverse Analysis for Forensics

# researcherOn[].awardedBy.label
United States Department of Homeland Security - (New York, New York, United States)

# researcherOn[].label
Nuclear Security Culture Development through Workforce Training and Certification for Professionals of Brazil, India, Indonesia, Jordan, Nigeria, UAE and other PNS Selected Countries.

# researcherOn[].awardedBy.label
United States Department of State - (Washington D.C., District of Columbia, United States)

# researcherOn[].label
Nuclear Security Culture Development in Brazil, India, Indonesia, Nigeria and Other Selected Countries Through Academic Engagements

# researcherOn[].awardedBy.label
United States Department of State - (Washington D.C., District of Columbia, United States)

# researcherOn[].label
Nuclear Safeguards Education Outreach Through the Nuclear Safeguards Education Portal and the Nuclear Facilities Experience

# researcherOn[].awardedBy.label
United States Department of Energy - (Washington D.C., District of Columbia, United States)

# researcherOn[].label
Nuclear Security Culture Development through Workforce Training and Academic Engagements for Professionals of Brazil, Egypt, India, Saudi Arabia, Turkey, UAE and other PNS Selected Countries

# researcherOn[].awardedBy.label
United States Department of State - (Washington D.C., District of Columbia, United States)

# researcherOn[].awardedBy.preferredLabel
U.S. Department of State: Bureau of Diplomatic Security

# researcherOn[].label
Nuclear Security Culture Development in India through Academia Engagement in Collaboration with Sandia National Laboratories

# researcherOn[].awardedBy.label
United States Department of State - (Washington D.C., District of Columbia, United States)

# researcherOn[].label
Nuclear Security Culture Development in India and Brazil through Academic Engagements along with Nuclear Security Educational Module Development

# researcherOn[].awardedBy.label
United States Department of State - (Washington D.C., District of Columbia, United States)

# researcherOn[].label
Continuation of Nuclear Security Engagements with the Department of Atomic Energy (DAE) and Universities in India

# researcherOn[].awardedBy.label
United States Department of State - (Washington D.C., District of Columbia, United States)

# researcherOn[].label
Experimental and Computational Assessment of Unique Trace Elements and Isotope Ratios in Separated Plutonium from Depleted Uranium Irradiated in Fast Reactor Blanket

# researcherOn[].awardedBy.label
United States Department of Homeland Security - (New York, New York, United States)

# researcherOn[].label
International and Domestic Nuclear Facilities Experience for the U.S. Students and National Lab Professionals

# researcherOn[].awardedBy.label
United States Department of Energy - (Washington D.C., District of Columbia, United States)

# streetAddress
Texas A&M University; Nuclear Security Science & Policy Institute; 3473 TAMU

# organizations[]
Institute for Engineering Education and Innovation

# schools[]
Texas A&M Engineering Experiment Station (TEES)

# etdChairOf[].label
Wu, Huali (2013-08). Heat Transfer Simulation of Reactor Cavity Cooling System Experimental Facility using RELAP5-3D and Generation of View Factors using MCNP. Master's Thesis.

# etdChairOf[].label
Allred, Jarrod Ryan (2016-08). Experimental Analysis of Plutonium Product and Raffinate Waste Streams from a PUREX Process on A Low Burn-Up, Fast Neutron Irradiated DUO2 Pellet. Master's Thesis.

# etdChairOf[].label
Swinney, Mathew Wayne (2015-12). Experimental and Computational Assessment of Trace Nuclide Ratios in Weapons Grade Plutonium for Nuclear Forensics Analysis. Doctoral Dissertation.

# etdChairOf[].label
Setiawan, Yanuar Ady (2018-05). ADVERSARY PATH ANALYSIS OF A PHYSICAL PROTECTION SYSTEM DESIGN USING A STOCHASTIC APPROACH. Master's Thesis.

# etdChairOf[].label
Osborn, Jeremy Michael (2018-08). Nuclear Forensics Methodology for Source Reactor-Type Discrimination of Chemically Separated Plutonium. Doctoral Dissertation.

# etdChairOf[].label
Gowthahalli Chandregowda, Nandan (2012-08). Assessment of the Fingerprinting Method for Spent Fuel Verification in MACSTOR KN-400 CANDU Dry Storage. Master's Thesis.

# etdChairOf[].label
Wilcox, Andrew John (2018-05). The Kinetic and Thermodynamic Properties of the Dissolution of Sodium Bismuthate. Master's Thesis.

# etdChairOf[].label
Mendoza, Paul Michael (2018-02). Experimental Characterization of Pu Separation by Purex on a Low-Burnup, Pseudo-Fast-Neutron Irradiated DUO2 for Product Decontamination Factors and Nuclear Forensics. Doctoral Dissertation.

# etdChairOf[].label
Osborn, Jeremy (2014-08). Trace Fission Product Ratios for Nuclear Forensics Attribution of Weapons-Grade Plutonium from Fast Breeder Reactor Blankets. Master's Thesis.

# etdChairOf[].label
Kitcher, Evans Damenortey, 1987- (2012-12). Performance and Safety Analysis of a Generic Small Modular Reactor. Master's Thesis.

# etdChairOf[].label
Joe Justina, - (2012-08). Radiation Transport Simulation Studies Using MCNP for a Cow Phantom to Determine an Optimal Detector Configuration for a New Livestock Portal. Master's Thesis.

# etdChairOf[].label
Coles, Taylor Marie (2014-04). Computational Nuclear Forensics Analysis of Weapons-grade Plutonium Separated from Fuel Irradiated in a Thermal Reactor. Master's Thesis.

# etdChairOf[].label
Subbaiah, Meyappan (2016-07). An Analysis on the Correlates of Nuclear Proliferation and Nuclear Energy. Master's Thesis.

# etdChairOf[].label
Kelly, Ryan Patrick (2013-05). Uncertainty Quantification of Concrete Utilized in Dry Cask Storage. Master's Thesis.

# etdChairOf[].label
Pompilio, Lauren Marie (2017-05). Analysis of 10 CFR Part 810 General Authorization Data on Assistance to Foreign Atomic Energy Activities. Master's Thesis.

# etdChairOf[].label
Kitcher, Evans Damenortey (2016-08). Xenon Induced Power Oscillations in a Generic Small Modular Reactor. Doctoral Dissertation.

# etdChairOf[].label
Hawila, Mohammad Abdel-Majid Mustafa (2016-11). Combined Safety and Security Risk Evaluation Considering Safety and Security-Type Initiating Events. Master's Thesis.

# etdChairOf[].label
Bencomo, Marlene (2016-04). Parametric Study of 99Mo Production Using a Sub-critical Low Enriched Uranium Assembly Design Proposed by Niowave Inc.. Master's Thesis.

# etdChairOf[].label
Khudoleeva, Alexandra P (2013-02). Conceptual Development of Remote Monitoring System for Pressurized Water Reactor Spent Fuel Dry Cask Storage Through Neutron and Gamma Transport Simulations. Master's Thesis.