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Technical Briefs August 7, 2020
Development and Verification of Multi-Physical Coupling Calculation Code for Typical PWR Core
ASME J of Nuclear Rad Sci. doi: https://doi.org/10.1115/1.4048027
Research-Article August 7, 2020
Estimation of Radiological Consequences At a Proposed Nuclear Power Plant Site Using Atmospheric Dispersion Code
ASME J of Nuclear Rad Sci. doi: https://doi.org/10.1115/1.4048026
Research-Article August 6, 2020
Hydrogen Deflagration Analysis in THAI Experiments Using MELCOR Code
ASME J of Nuclear Rad Sci. doi: https://doi.org/10.1115/1.4048006
Research-Article August 5, 2020
CFD Thermal Analysis of Iter Pressure Suppression Tanks
ASME J of Nuclear Rad Sci. doi: https://doi.org/10.1115/1.4048007
Research-Article August 5, 2020
Finite Element Model of a Melting Terminal Debris Bed in a CANDU Calandria
ASME J of Nuclear Rad Sci. doi: https://doi.org/10.1115/1.4048008
Research-Article August 5, 2020
Supercritical Water Choking Flow Experiments Through a Convergent-Divergent Test Section
ASME J of Nuclear Rad Sci. doi: https://doi.org/10.1115/1.4048009
Research-Article July 23, 2020
Preparation and Characterization of Nb-1Zr-0.1C Alloy Suitable for Liquid Metal Coolant Channels of High Temperature Reactors
ASME J of Nuclear Rad Sci. doi: https://doi.org/10.1115/1.4047919
Research-Article July 23, 2020
Passive and Walk-Away Safe Small and Micro Reactors for Electricity Generation and Production of Process Heat for Industrial Uses
ASME J of Nuclear Rad Sci. doi: https://doi.org/10.1115/1.4047920
Review Articles July 23, 2020
A Comparative Study On Severe Accident Phenomena Related to Melt Progression in SFR and PWR
ASME J of Nuclear Rad Sci. doi: https://doi.org/10.1115/1.4047921
Technical Briefs July 13, 2020
Benefits, Drawbacks and Future Trends of Brayton Helium Gas Turbine Cycles for GFR and VHTR Generation IV Nuclear Power Plants
ASME J of Nuclear Rad Sci. doi: https://doi.org/10.1115/1.4047773
Research-Article July 7, 2020
Calculation of Dynamical Phase Diagram in U-Zr Binary System Under Irradiation
ASME J of Nuclear Rad Sci. doi: https://doi.org/10.1115/1.4047718
Research-Article July 7, 2020
Non-Contact Displacement Measurement of Nuclear Waste Canisters in a Geological Disposal by Using an Electromagnetic-Wave Approach
ASME J of Nuclear Rad Sci. doi: https://doi.org/10.1115/1.4047719
Review Articles July 7, 2020
The Intersection of Advancing Technology and Human Performance
ASME J of Nuclear Rad Sci. doi: https://doi.org/10.1115/1.4047717
Research-Article July 7, 2020
Experimental Investigation of Flow Instability in Two Vertical Parallel Channels Using Super Critical CO2
ASME J of Nuclear Rad Sci. doi: https://doi.org/10.1115/1.4047716
Guest Editorial July 7, 2020
Editorial - Special Issue on the 27th International Conference On Nuclear Engineering (ICONE-27)
ASME J of Nuclear Rad Sci. doi: https://doi.org/10.1115/1.4047731
Technology Review July 1, 2020
Current Status of Reactor Deployment and SMR Development in the World
ASME J of Nuclear Rad Sci. doi: https://doi.org/10.1115/1.4047927
Research-Article June 17, 2020
Analysis of the Effect of Vessel Failure and Melt Release On Risk of Containment Failure Due to Ex-Vessel Steam Explosion in Nordic BWR Using ROAAM+ Framework
ASME J of Nuclear Rad Sci. doi: https://doi.org/10.1115/1.4047552
Research-Article June 12, 2020
Improved CFD Framework for Reactor Core Baffle Swelling Assessment
ASME J of Nuclear Rad Sci. doi: https://doi.org/10.1115/1.4047495
Research-Article June 12, 2020
Unequivocally Nonconservative Results From One Method of Imperfection Quantification in RCC-MR
ASME J of Nuclear Rad Sci. doi: https://doi.org/10.1115/1.4047494
Research-Article June 8, 2020
Analysis Methods for High Energy Line Break Jet Flows in Nuclear Power Plants
ASME J of Nuclear Rad Sci. doi: https://doi.org/10.1115/1.4047441
Research-Article May 11, 2020
Best-Estimate Plus Uncertainty Analysis of Candu Fuel Reliability Using Manufacturing and Simulated Core Data
ASME J of Nuclear Rad Sci. doi: https://doi.org/10.1115/1.4047162
Research-Article May 11, 2020
Non-Hyperbolicity of Conservation Equations of RELAP5 Two Fluid Model in Nuclear Reactor Safety Results — Part I : Investigation and Eigenvalue Analysis
ASME J of Nuclear Rad Sci. doi: https://doi.org/10.1115/1.4047161
Research-Article May 7, 2020
Asme Boiler and Pressure Vessel Code Roadmap for Compact Heat Exchangers in High Temperature Reactors
ASME J of Nuclear Rad Sci. doi: https://doi.org/10.1115/1.4047113
Technical Briefs May 4, 2020
The Sensitivity Analysis of the Core Lower Head Molten Pool Model Based On Variance Decomposition
ASME J of Nuclear Rad Sci. doi: https://doi.org/10.1115/1.4047093
Research-Article May 4, 2020
Criticality Characteristics and Sensitivity Analysis of Fukushima Debris Beds Containing MCCI Products
ASME J of Nuclear Rad Sci. doi: https://doi.org/10.1115/1.4047094
Research-Article April 27, 2020
Heat Transfer and Hydraulic Resistance in Turbulent Flow in Vertical Round Tubes At Supercritical Pressures. Part 1. Results From Numerical Simulations Using Algebraic Turbulent Viscosity Models
ASME J of Nuclear Rad Sci. doi: https://doi.org/10.1115/1.4047042
Research-Article April 27, 2020
Radionuclide Composition of Airborne Discharges of European NPPs with WWER, PWR and BWR Reactor Facilities
ASME J of Nuclear Rad Sci. doi: https://doi.org/10.1115/1.4047044
Research-Article April 27, 2020
Heat Transfer and Hydraulic Resistance in Turbulent Flow in Vertical Round Tubes At Supercritical Pressures. Part II. Results From Numerical Simulation with Differential Turbulent Viscosity Models
ASME J of Nuclear Rad Sci. doi: https://doi.org/10.1115/1.4047043
Research-Article April 14, 2020
Steam Condensation Heat Transfer During Initial Blow-Down Period of a Severe Nuclear Accident
ASME J of Nuclear Rad Sci. doi: https://doi.org/10.1115/1.4046910
Technical Briefs April 14, 2020
A Theory and Model of Molten Salt Reactor Xenon Behavior After the Solubility Limit
ASME J of Nuclear Rad Sci. doi: https://doi.org/10.1115/1.4046909
Research-Article April 7, 2020
Study On Description of Plant Status At Fukushima Accident by Emergency Action Level
ASME J of Nuclear Rad Sci. doi: https://doi.org/10.1115/1.4046841
Research-Article April 2, 2020
A Novel Assessment of Delayed Neutron Detector Data in Candu Reactors
ASME J of Nuclear Rad Sci. doi: https://doi.org/10.1115/1.4046824
Research-Article March 25, 2020
Ni+ and He+ Implantation Effects On the Hardness and Microstructure of Heat Treated Inconel X750
ASME J of Nuclear Rad Sci. doi: https://doi.org/10.1115/1.4046716
Research-Article March 1, 2020
The Other Metallic Phase in Spent Nuclear Fuel: A Complete Thermodynamic Evaluation of the U-Pd-Rh-Ru System
ASME J of Nuclear Rad Sci. doi: https://doi.org/10.1115/1.4046784
Technical Briefs February 24, 2020
Validation of the Moody and Henry-Fauske Critical Flow Models in Apros Against Marviken Critical Flow Experiments
ASME J of Nuclear Rad Sci. doi: https://doi.org/10.1115/1.4046432
Research-Article February 17, 2020
High Reliability Micro-Grid for a Nuclear Facility Emergency Power Supply
ASME J of Nuclear Rad Sci. doi: https://doi.org/10.1115/1.4046353
Research-Article February 7, 2020
Retention of Molten Corium in Calandria Vessel of Phwr with Moderator Drain Pipe
ASME J of Nuclear Rad Sci. doi: https://doi.org/10.1115/1.4046257
Technical Briefs February 7, 2020
Assessment of the External and Internal Exposure Risk Index and the Annual Gonadals Equivalent Dose (AGED) Due to Cement in Côte D'ivoire
ASME J of Nuclear Rad Sci. doi: https://doi.org/10.1115/1.4046256
Research-Article February 7, 2020
A Simplified Two-Group Multipoint Kinetics Model
ASME J of Nuclear Rad Sci. doi: https://doi.org/10.1115/1.4046254
Research-Article February 7, 2020
Flow Instability Investigation At Supercritical Pressures in Parallel Channels by CFD Adopting Low and High Power Boundaries
ASME J of Nuclear Rad Sci. doi: https://doi.org/10.1115/1.4046255
Research-Article February 3, 2020
Organ Dose Calculations Using ICRP Adult Voxel Phantoms and Tripoli-4 Monte Carlo Code
ASME J of Nuclear Rad Sci. doi: https://doi.org/10.1115/1.4046213
Research-Article December 1, 2019
Total Cross Section Phenomenological Formulas for X-ray and Gamma Radiation Interaction with Matter for Different Energies and Absorber Types
ASME J of Nuclear Rad Sci. doi: https://doi.org/10.1115/1.4045806
Research-Article April 30, 2019
RELAP5-3D Simulation of Natural Circulation in Fast Reactors With Lead-Bismuth Eutectic Alloy Coolant
ASME J of Nuclear Rad Sci. doi: https://doi.org/10.1115/1.4036986
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