Search

Search Constraints

Start Over You searched for: Committee Member Arthur Thompson Motta Remove constraint Committee Member: Arthur Thompson Motta

Search Results

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

open_access
Open Access

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

open_access
Open Access

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

open_access
Open Access

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

open_access
Open Access

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

open_access
Open Access

8. A STUDY FOR MODELING ELECTROCHEMISTRY IN LIGHT WATER REACTORS

open_access
Open Access

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

open_access
Open Access

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

open_access
Open Access

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

open_access
Open Access

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

open_access
Open Access

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

open_access
Open Access

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

open_access
Open Access

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

open_access
Open Access

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

open_access
Open Access

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

open_access
Open Access

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

open_access
Open Access

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

open_access
Open Access

21. Fundamental Experiments on Hydride Reorientation in Zircaloy

open_access
Open Access

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

open_access
Open Access

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

open_access
Open Access

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

open_access
Open Access

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

open_access
Open Access

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

open_access
Open Access

28. Hydrogen Pickup Mechanism of Zirconium Alloys

open_access
Open Access

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

open_access
Open Access

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

open_access
Open Access

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

open_access
Open Access

33. Microstructure evolution of zirconium carbide irradiated by ions

open_access
Open Access

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

open_access
Open Access

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

open_access
Open Access

37. THE EFFECT OF STRESS STATE ON ZIRCONIUM HYDRIDE REORIENTATION

open_access
Open Access

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

open_access
Open Access

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

open_access
Open Access

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

open_access
Open Access

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

open_access
Open Access

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

open_access
Open Access

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

open_access
Open Access

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

open_access
Open Access

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

open_access
Open Access

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

open_access
Open Access

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

open_access
Open Access

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

open_access
Open Access

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

open_access
Open Access