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3. Thin, Free-Standing Films For High Resolution Neutron Imaging

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4. SOFT ERROR RATE SIMULATION AND INITIAL DESIGN CONSIDERATIONS OF NEUTRON INTERCEPTING SILICON CHIP (NISC)

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5. MICROSTRUCTURE EVOLUTION OF NANOCRYSTALLINE METALLIC THIN-FILMS UNDER ION-BEAM IRRADIATION

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6. HIGH ACCURACY MODELING FOR ADVANCED NUCLEAR REACTOR CORE DESIGNS USING MONTE CARLO BASED COUPLED CALCULATIONS

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7. IMPROVED CRUD HEAT TRANSFER MODEL FOR DRYOUT ON FUEL PIN SURFACES AT PWR OPERATING CONDITIONS

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8. A STUDY FOR MODELING ELECTROCHEMISTRY IN LIGHT WATER REACTORS

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9. Evolution of the Oxide Structure of Ferritic-Martensitic Steels Exposed to Supercritical Water

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10. STRUCTURE OF OXIDE LAYERS FORMED ON CANDIDATE STEEL ALLOYS EXPOSED TO FLOWING LEAD-BISMUTH EUTECTIC FOR GENERATION IV REACTOR APPLICATIONS

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11. FEASIBILITY STUDY FOR THE CONCEPTUAL DESIGN OF A DUAL-CORE BOILING SUPERHEAT REACTOR

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12. Kinetics of zirconium hydride precipitation and reorientation studied using synchrotron radiation

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14. INFLUENCE OF OXIDE MICROSTRUCTURE ON CORROSION BEHAVIOR OF ZIRCONIUM-BASED MODEL ALLOYS

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15. The Development of a Non-Equilibrium Dispersed Flow Film Boiling Heat Transfer Modeling Package

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16. DEVELOPMENT OF AN ION TIME-OF-FLIGHT SPECTROMETER FOR NEUTRON DEPTH PROFILING

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17. Crack Growth Through the Thickness of Thin-Sheet Hydrided Zircaloy-4

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18. Hydride-induced Embrittlement of Zircaloy-4 Cladding under Plane-strain Tension

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19. Automated Spectral Zones Selection Methodology for Diffusion Theory Data Preparation for Pebble Bed Reactor Analysis

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20. MULTI LEVEL OPTIMIZATION OF BURNABLE POISON UTILIZATION FOR ADVANCED PWR FUEL MANAGEMENT

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21. Fundamental Experiments on Hydride Reorientation in Zircaloy

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22. Examination and improvement of the SHEM energy group structure for HTR and deep burn HTR design and analysis

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23. Evolution of the Oxide Microstructure and Oxide Growth Induced Residual Strains During Waterside Corrosion of Zirconium Alloys

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24. Guided Wave Propagation in Complex Curved Waveguides: Flexural Guided Waves and their Application for Defect Classification in Pipes

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25. Hydrogen distribution in Zircaloy under a temperature gradient: Modeling, Simulation and Experiments

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26. Deterministic Multigroup Modeling of Thermal Effect on Neutron Scattering by Heavy Nuclides

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28. Hydrogen Pickup Mechanism of Zirconium Alloys

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29. microstructural evolution of ferritic-martensitic steels under heavy ion irradiation

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31. Core Design of Pressurized Water Reactors with Fully Ceramic Microencapsulated Fuel

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32. Development of Burnup Dependent Fuel Rod Model in Cobra-tf

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33. Microstructure evolution of zirconium carbide irradiated by ions

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35. Radiation Sensitivity of Graphene Field Effect Transistors and Other Thin Film Architectures

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36. Neutronic and Economic Evaluation of Accident Tolerant Fuel Concepts for Light Water Reactors

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37. THE EFFECT OF STRESS STATE ON ZIRCONIUM HYDRIDE REORIENTATION

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38. Effect of Liquid Subcooling, Initial Surface Temperature, and Surface Properties on the Minimum Film Boiling Temperature

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39. Hydrogen Distribution in Zircaloy Under a Temperature Gradient: A Benchmark Study

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40. THE NATURE OF UNSTABLE OXIDE GROWTH IN ZIRCONIUM AND ZIRCONIUM ALLOYS

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41. Development and Operation of a Li6F:ZnS(Ag) Scintillating Plastic Capture-Gated Detector

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42. The role of nickel in hydrogen pick-up during in-reactor corrosion of zirconium alloys

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43. Localization of Neutron Sources with Mobile Radiation Detectors Based on Drone Technology

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44. MESOSCALE SIMULATIONS OF THERMAL TRANSPORT IN W-UO2 CERMET FUEL FOR NUCLEAR THERMAL PROPULSION

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45. DEVELOPMENT OF A PHASE FIELD MODEL OF HYDRIDE MORPHOLOGY IN ZIRCONIUM ALLOY NUCLEAR FUEL CLADDING

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47. Modeling the Molten Salt Reactor Experiment with the NEAMS System Analysis Module

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48. CHARACTERIZATION OF FRACKING SOIL, SEDIMENT, AND WASTEWATER SAMPLES USING COMPARATIVE NEUTRON ACTIVATION ANALYSIS METHOD

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49. Fuel Cycle Performance of Thermal and Fast Spectrum Small Modular Reactors

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50. Transmission Electron Microscopy Characterization of Zircaloy-4 Subjected to Ion Irradiation

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53. USE OF THE FISSION MATRIX FOR STEADY STATE AND QUASI-STATIC KINETIC MODELING OF THE TREAT REACTOR WITH TEMPERATURE FEEDBACK

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54. A Grand Potential Sintering Model: Derivation and Application to UO2 Thermal Sintering, Doped Sintering, and Irradiation-Enhanced Densification

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55. Modeling zirconium hydride precipitation and dissolution in zirconium alloys

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56. Surface Characterization of Piezoelectric Sensor Materials for Potential Use in Reactor Vessel Sensors

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57. Multi-scale simulation of advanced reactor fuel and cladding concepts

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59. Ratio correction, temperature feedback, and other advances for the fission-matrix based hybrid transport code RAPID

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60. Development of a Cost-effective Portable Neutron Imager and Spectrometer Using Sinusoid-based Multiplexing of Silicon Photomultipliers and Plastic Scintillators

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62. Phase field modeling and quantification of zirconium hydride morphology

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63. HIGH HEAT FLUX DAMAGE SIMULATIONS WITH AN ELECTROTHERMAL DISCHARGE DEVICE UNDERGOING INCREASING CURRENT AND PULSE LENGTH TIMES

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64. Surface Damage and Microstructure Deformation of Resolidified Tungsten in High Heat Flux Conditions

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65. Fission matrix methods for temperature and control feedback of small nuclear systems

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66. MODEL-BASED AND DATA-DRIVEN ANOMALY DETECTION AND FAULT ACCOMMODATION OF NUCLEAR POWER PLANTS

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67. Updates to the Godiva-IV Model with Experimental Improvements to K-eff Values

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68. MICROSTRUCTURAL EVOLUTION OF 21Cr32Ni AUSTENITIC MODEL ALLOY UNDER HEAVY-ION IRRADIATION AS A SURROGATE FOR REACTOR IRRADIATION

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69. Experimental and Numerical Studies of the Droplet Sizes and Velocities near the Quench Front for Transient Reflood Conditions

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