publication venue for
- Validation of Pronghorn Pressure Drop Correlations Against Pebble Bed Experiments. 208:1769-1805. 2022
- Experimental and Computational Verification of a New Remote Monitoring System Design for Spent Fuel Dry Cask Safeguards Using Small-Scale, Generic Diversion Scenarios. 208:1635-1648. 2022
- Modal Decomposition of the Flow in a Randomly Packed Pebble Bed with Direct Numerical Simulation. 208:1279-1289. 2022
- Experimental Verification of Proposed Internal Remote Monitoring System for Spent Nuclear Fuel Dry Cask Storage Applications. 208:1511-1521. 2022
- Design and Analysis of an Internal Remote Monitoring System for Spent Nuclear Fuel Stored in a Dry Cask. 208:428-436. 2022
- Inertial Effects and Anisotropy for the Flow in a Domain of Close Packed Spheres with a Bounding Wall. 208:539-561. 2022
- Improving Pulse Shape Discrimination in Organic Scintillation Detectors by Understanding Underlying Data Structure. 208:1522-1539. 2022
- Pressure Drop Correlation Improvement for the Near-Wall Region of Pebble-Bed Reactors. 209:90-104. 2022
- Cardinal: A Lower Length-Scale Multiphysics Simulator for Pebble-Bed Reactors. 207:1118-1141. 2021
- Coupled Computational Fluid Dynamics-Discrete Element Method Study of Bypass Flows in a Pebble Bed Reactor. 207:1599-1614. 2021
- Toward Exascale: Overview of Large Eddy Simulations and Direct Numerical Simulations of Nuclear Reactor Flows with the Spectral Element Method in Nek5000. 206:1308-1324. 2020
- Power Profile Reconstruction and Anomaly Detection Approach for FHRs Using Cerenkov Radiation. 206:1740-1750. 2020
- Surface Pressure Measurements in a Model Helical Coil Steam Generator Using Pressure Sensitive Paint. 206:565-576. 2020
- Numerical Simulation of Isothermal Flow Across Slant Five-Tube Bundle with Spectral Element Method Code Nek5000. 206:296-306. 2020
- A Method to Estimate Fission Product Concentration Uncertainty in a Multi-Time-Step MCNP6 Code Nuclear Fuel Burnup Calculation. 206:73-81. 2020
- Analysis of Velocity Distributions Across a Model Helical Coil Steam Generator. 205:881-890. 2019
- Anisotropic Radiation-Induced Changes in Type 316L Stainless Steel Rods Built by Laser Additive Manufacturing. 205:563-581. 2019
- Investigations on Detecting Potential Nuclear Material Diversion from a Pyroprocessing Facility. 205:464-473. 2019
- High-Fidelity Simulation of Flow-Induced Vibrations in Helical Steam Generators for Small Modular Reactors. 205:33-47. 2019
- Selected papers from the 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-17) Foreword. 205:V-VI. 2019
- Nuclear Forensics Methodology for Reactor-Type Attribution of Chemically Separated Plutonium. 201:1-10. 2018
- Experimental and Computational Forensics Characterization of Weapons-Grade Plutonium Produced in a Fast Reactor Neutron Environment. 197:1-11. 2017
- MELCOR and GOTHIC Analyses of a Large Dry PWR Containment to Support Resolution of GSI-191. 196:292-302. 2016
- RoverD: Use of Test Data in GSI-191 Risk Assessment. 196:270-291. 2016
- Impact of Pressure Relief Holes on Core Coolability for a PWR During a Large-Break Loss-of-Coolant Accident with Core Blockage Using RELAP5-3D. 193:88-95. 2016
- UNCERTAINTY QUANTIFICATION OF CONCRETE UTILIZED IN DRY CASK STORAGE. 190:72-87. 2015
- EXPERIMENTAL INVESTIGATION OF A SCALED WATER-COOLED REACTOR CAVITY COOLING SYSTEM. 187:282-293. 2014
- PREDICTING CONCRETE ROADWAY CONTRIBUTION TO GAMMA-RAY BACKGROUND IN RADIATION PORTAL MONITOR SYSTEMS. 186:415-426. 2014
- ASSESSMENT OF THE FINGERPRINTING METHOD FOR THE VERIFICATION OF SPENT FUEL IN MACSTOR KN-400 CANDU SPENT-FUEL DRY STORAGE. 184:320-332. 2013
- Pressure Drop in a Pebble Bed Reactor Under High Reynolds Number. 180:159-173. 2012
- EXPERIMENTAL STUDY OF THE EFFECT OF GRAPHITE DISPERSION ON THE HEAT TRANSFER PHENOMENA IN A REACTOR CAVITY COOLING SYSTEM. 177:217-230. 2012
- COMPUTATIONAL FLUID DYNAMICS ANALYSIS OF VERY HIGH TEMPERATURE GAS-COOLED REACTOR CAVITY COOLING SYSTEM. 176:238-259. 2011
- FLOODING EXPERIMENTS WITH STEAM AND WATER IN A LARGE-DIAMETER VERTICAL TUBE. 175:529-537. 2011
- SPECIAL ISSUE ON THE 2009 TOUGH2 SYMPOSIUM FOREWORD. 174:315-316. 2011
- Flooding Experiments with Steam and Water in a Large-Diameter Vertical Tube 2011
- Foreword: Special Issue on the 2009 TOUGH2 Symposium. 174:315-316. 2011
- APPLICATION OF QUADRUPLE RANGE QUADRATURES TO THREE-DIMENSIONAL MODEL SHIELDING PROBLEMS. 168:424-430. 2009
- Foreword: NURETH-12 Special Issue. 167:1-1. 2009
- Simulation of Sulfur-Iodine Thermochemical Hydrogen Production Plant Coupled to High-Temperature Heat Source. 167:95-106. 2009
- Variable Property Effects on Vapor Condensation with a Noncondensable Gas. 167:13-19. 2009
- Transient Analysis of Sulfur-Iodine Cycle Experiments and Very High Temperature Reactor Simulations Using MELCOR-H2. 166:76-85. 2009
- Introduction to the best estimate methods - 2004 special issue - Dedicated to the memory of Gerassimos (Mike) Analytis. 158:1-1. 2007
- Microgravity phase separation for the Rankine cycle. 156:282-288. 2006
- MELCOR Analysis of Steam Generator Tube Creep Rupture in Station Blackout Severe Accident. 152:302-313. 2005
- KAMINI Reactor South Beam Port Shield-Structure Optimization. 135:265-272. 2001
- Analysis of Routine Radiological Measurements in a Nuclear Power Plant. 114:404-412. 1996
- A 2-DIMENSIONAL FINITE-ELEMENT METHOD LARGE-EDDY SIMULATION FOR APPLICATION TO TURBULENT STEAM-GENERATOR FLOW. 106:83-99. 1994
- A Two-Dimensional Finite Element Method Large Eddy Simulation for Application to Turbulent Steam Generator Flow. 106:83-99. 1994
- A STUDY OF RELAP5/MOD2 AND RELAP5/MOD3 PREDICTIONS OF A SMALL-BREAK LOSS-OF-COOLANT ACCIDENT SIMULATION CONDUCTED AT THE ROSA-IV LARGE-SCALE TEST FACILITY. 100:111-124. 1992
- 2-PHASE FLOW INTERFACIAL DRAG FOR ONCE-THROUGH STEAM-GENERATORS. 95:77-86. 1991
- Two-Phase Flow Interfacial Drag for Once-Through Steam Generators. 95:77-86. 1991
- Steady-state simulations of a 30-tube once-through steam generator with the RELAP5/MOD3 and RELAP5/MOD2 computer codes. 96:123-128. 1991
- A COMPARISON OF RELAP5/MOD2 RESULTS TO THE DATA OF A SMALL-BREAK LOSS-OF-COOLANT ACCIDENT EXPERIMENT OF AN IAEA STANDARD PROBLEM EXERCISE. 89:177-182. 1990
- ASSESSMENT OF BOILING HEAT TRANSFER CORRELATIONS FOR ONCE-THROUGH STEAM GENERATORS.. 81:446-449. 1988
- NODALIZATION STUDY OF THE WESTINGHOUSE-MODEL-E-STEAM GENERATOR-SECONDARY SIDE. 76:126-136. 1987
- ANALYSIS OF FLECHT AND FLECHT-SEASET REFLOOD TESTS WITH RELAP5 MOD2. 74:176-188. 1986
- INTERPRETATION OF CONDUCTIVITY-SENSITIVE LIQUID-LEVEL TRANSDUCER SIGNALS IN A SMALL BREAK LOSS-OF-COOLANT ACCIDENT TEST FACILITY. 72:49-58. 1986
- TRANSIENT 2-PHASE BLOWDOWN PREDICTIONS OF AN INITIALLY STAGNANT SATURATED LIQUID STEAM IN A VESSEL USING TRAC-PF1. 69:388-392. 1985
- Three-Dimensional Calculations of Fluid-Thermal Mixing in a Babcock & Wilcox Plant at Stagnated Loop Flow. 69:257-267. 1985
- COMPUTATIONAL INVESTIGATION OF FLUID AND THERMAL MIXING OF THE EPRI CREARE 1/5-SCALE FACILITY. 68:395-407. 1985
- AN IMPROVED MULTIDIMENSIONAL FINITE-DIFFERENCE SCHEME FOR PREDICTING STRATIFIED HORIZONTAL PIPE-FLOW. 65:454-461. 1984
- STEADY-STATE AND TRANSIENT PREDICTION OF A 19-TUBE ONCE-THROUGH STEAM-GENERATOR USING RELAP5 MOD1. 60:143-150. 1983
- Hydrogen Transport in a Toroidal Plasma Using Multigroup Discrete-Ordinates Methodology. 42:272-288. 1979
- An Improved Finite Difference Method to Evaluate Heat Transfer in Fuel Pins with Eccentrically Placed Pellets. 40:306-314. 1978
- High-Fidelity Simulation of Flow-Induced Vibrations in Helical Steam Generators for Small Modular Reactors 2019
- DESIGN, CONSTRUCTION, AND IMPLEMENTATION OF SPHERICAL TISSUE-EQUIVALENT PROPORTIONAL COUNTER 2009
- Scaling of the small-scale thermal-hydraulic transient to the real nuclear power plant 2007