Home
Research Trends
Papers list
Open Access Journals
All Journals
Search in Journals
Contact us
Nuclear Technology
Title
Publication Date
Language
Citations
Automatic Differentiation in MetaPhysicL and Its Applications in MOOSE
2021/02/22
English
18
Toward Exascale: Overview of Large Eddy Simulations and Direct Numerical Simulations of Nuclear Reactor Flows with the Spectral Element Method in Nek5000
2020/06/25
English
18
Advanced Methodology for Uncertainty Propagation in Computer Experiments with Large Number of Inputs
2019/03/09
English
16
KRUSTY Experiment: Reactivity Insertion Accident Analysis
2020/06/04
English
15
Neutronics and Safety Studies on a Research Reactor Concept for an Advanced Neutron Source
2017/07/03
English
14
Benchmark of GOTHIC to EBR-II SHRT-17 and SHRT-45R Tests
2020/01/29
English
14
Results of the KRUSTY Warm Critical Experiments
2020/06/04
English
14
Development of a Validation Approach for an Integrated Waste Glass Melter Model
2018/06/14
English
14
Thermal-Hydraulic Experimental Testing of the MYRRHA Wire-Wrapped Fuel Assembly
2019/06/20
English
14
TREAT Restart Project
2019/04/08
English
14
Fluoride-Salt-Cooled High-Temperature Reactor (FHR) Using British Advanced Gas-Cooled Reactor (AGR) Refueling Technology and Decay Heat Removal Systems That Prevent Salt Freezing
2019/04/11
English
14
Sockeye: A One-Dimensional, Two-Phase, Compressible Flow Heat Pipe Application
2021/03/31
English
14
Continuous Integration, In-Code Documentation, and Automation for Nuclear Quality Assurance Conformance
2021/01/28
English
14
Development of a Pragmatic Approach to Model Input Uncertainty Quantification for BEPU Applications
2018/10/16
English
14
Thermal Energy Storage Configurations for Small Modular Reactor Load Shedding
2018/03/02
English
13
High-Fidelity Simulation of Flow-Induced Vibrations in Helical Steam Generators for Small Modular Reactors
2018/08/24
English
13
Fluoride-Salt-Cooled High-Temperature Test Reactor Thermal-Hydraulic Licensing and Uncertainty Propagation Analysis
2019/06/05
English
13
Effects of Surface Roughness, Oxidation, and Temperature on the Emissivity of Reactor Pressure Vessel Alloys
2017/08/31
English
13
Method of Characteristics for 3D, Full-Core Neutron Transport on Unstructured Mesh
2021/07/03
English
13
Transient Reactor Test (TREAT) Facility Design and Experiment Capability
2019/05/06
English
13
Interface-Resolved Simulations of Reactor Flows
2019/06/20
English
13
Development of an Experimental Routine for Electrochemical and Laser-Induced Breakdown Spectroscopy Composition Measurements of SmCl3in LiCl-KCl Eutectic Salt Systems
2018/12/28
English
13
Design and Operation of a Sensible Heat Peaking Unit for Small Modular Reactors
2018/08/09
English
13
Methodological and Practical Comparison of Integrated Probabilistic Risk Assessment (I-PRA) with the Existing Fire PRA of Nuclear Power Plants
2018/07/16
English
13
Conventional Controller Design for the Reactor Power Control System of the Advanced Small Pressurized Water Reactor
2017/04/03
English
13
A Critical Review of the Experimentally Known Properties of U-Pu-Zr Alloys. Part 1: Phases and Phase Diagrams
2019/05/06
English
12
Simultaneous PIV/PLIF and Pulsed Shadowgraphy Measurement of Gas-Liquid Flows in a Swirling Separator
2018/07/16
English
12
Cardinal: A Lower-Length-Scale Multiphysics Simulator for Pebble-Bed Reactors
2021/01/28
English
12
Nuclear Science for the Manhattan Project and Comparison to Today’s ENDF Data
2021/11/16
English
12
Effect of Heater Material and Thickness on the Steady-State Flow Boiling Critical Heat Flux
2019/12/10
English
12
«
‹ Pervious
Next ›
»