Nuclear, Solar, and Geothermal Energy

    Neutron Flux Reduction Programs for Reactor Pressure Vessel of Korea Nuclear Unit 1

    Development of an Active Detector for the Characterization of the Late-Time Radiation Environment from a Reactor Pulse

    Reactor Dosimetry and RPV Life Management

    Development and Testing of the VITAMIN-B7/BUGLE-B7 Coupled Neutron-Gamma Multigroup Cross-Section Libraries

    A Broad-Group Cross-Section Library Based on ENDF/B-VII.0 for Fast Neutron Dosimetry Using the CPXSD Methodology

    EPR/PTFE Dosimetry for Test Reactor Environments

    Calculation of Kobasko's Simplified Heat Transfer Coefficients from Cooling Curve Data Obtained with Small Probes

    Benchmarking of Neutron Production of Heavy-Ion Transport Codes

    Use of Cement-Treated Lightweight Soils Made from Dredged Clay

    Removal of Heavy Metals (Cu, Pb, and Zn) from Contaminated Sediment Using a Flotation Technique

    Structure Transformations in Multicomponent Amorphous Alloys in Connection with Grain-Boundary Segregations and Temper Embrittlement of Steels

    Evaluation of the Structural Sealant for Use in a Four-Sided Structural Sealant Glazing Curtain-Wall System for a Hospital Building

    Modernization of Existing VVER-1000 Surveillance Programs

    VVER-440 and VVER-1000 Reactor Dosimetry Benchmark —BUGLE-96 Versus ALPAN VII.0

    Jules Horowitz Reactor, a New Irradiation Facility: Improving Dosimetry for the Future of Nuclear Experimentation

    Updating and Extending the IRDF-2002 Dosimetry Library

    Path Forward for Dosimetry Cross Sections

    Apparatus for Use in Evaluating Protection from Low Pressure Hot Water Jets

    Fitting Method for Spectrum Deduction in High-Energy Neutron Field Induced by GeV-Protons Using Experimental Reaction-Rate Data

    An Alternative Calibration Method for Counting P-32 Reactor Monitors

    Exposure Conditions of Reactor Internals of Rovno VVER-440 Nuclear Power Plant Units 1 and 2

    Sensitivity of Adjustment to Parameter Correlations and to Response-Parameter Correlations

    Dosimetry Analyses of the Ringhals 3 and 4 Reactor Pressure Vessels

    Ex-Vessel Neutron Dosimetry Analysis for Westinghouse 4-Loop XL Pressurized Water Reactor Plant Using 3D Parallel Discrete Ordinates Code RAPTOR-M3G

    Comparison of Regulatory Guide 1.99 Fluence Attenuation Methods