Journal of Nuclear Engineering and Radiation Science: Recent submissions
Now showing items 561-580 of 913
-
Seismic Damage at the Fukushima Daiichi Nuclear Power Station With Emphasis on Unit 1
(The American Society of Mechanical Engineers (ASME), 2019)This paper analyzes and reviews various seismic damage at the Fukushima Daiichi Nuclear Power Station (F1) caused by the Great East Japan Earthquake (the Earthquake) on March 11 in 2011. Moreover, descriptions of various ... -
Corrosion in Iron and Steel T91 Caused by Flowing Lead–Bismuth Eutectic at 400 °C and 10−7 Mass% Dissolved Oxygen
(The American Society of Mechanical Engineers (ASME), 2019)Specimens produced from technically pure iron and two different heats of ferritic/martensitic steel T91 are investigated after exposure to oxygen-containing flowing lead–bismuth eutectic (LBE) at 400 °C, 10−7 mass% dissolved ... -
A Thoria and Thorium Uranium Dioxide Nuclear Fuel Performance Model Prototype and Knowledge Gap Assessment
(The American Society of Mechanical Engineers (ASME), 2019)Thorium-based fuel cycles can improve fuel sustainability within the nuclear power industry. The Canadian supercritical water-cooled reactor (SCWR) concept uses this path to achieve the sustainability requirement of the ... -
Experimental Investigations on Carryover in a Gravity Separation-Based Steam Drum
(The American Society of Mechanical Engineers (ASME), 2019)Advanced heavy water reactor (AHWR) is a natural circulation-based, light water-cooled, heavy water-moderated pressure tube type of nuclear reactor. In AHWR, the steam separation takes place in horizontal steam drums purely ... -
Breeding Properties Study on High-Power Thorium Molten Salt Reactor
(The American Society of Mechanical Engineers (ASME), 2019)Molten salt reactor (MSR), the only one using liquid fuel in the six types “Generation IV” reactors, is very different from reactors in operation now and has initiated very extensive interests all over the world. This paper ... -
Thermo-Mechanical Safety Analyses of Preliminary Design Experiments for 238Pu Production
(The American Society of Mechanical Engineers (ASME), 2019)Safety analyses at the high flux isotope reactor (HFIR) are required to qualify experiment targets for the production of plutonium-238 (238Pu) from neptunium dioxide/aluminum cermet (NpO2/Al) pellets. High heat generation ... -
Development and Validation of SAS4A Code and Its Application to Analyses on Severe Flow Blockage Accidents in a Sodium-Cooled Fast Reactor
(The American Society of Mechanical Engineers (ASME), 2019)Local subassembly faults (LFs) have been considered to be of greater importance in safety evaluation in sodium-cooled fast reactors (SFRs) because fuel elements were generally densely arranged in the subassemblies (SAs) ... -
The AP1000 Plant and the China Project Commissioning Success
(The American Society of Mechanical Engineers (ASME), 2019) -
A Happy New Year…
(The American Society of Mechanical Engineers (ASME), 2019) -
The CNS President's Message
(The American Society of Mechanical Engineers (ASME), 2019) -
ASME Nuclear Engineering Division Chair’s Message
(The American Society of Mechanical Engineers (ASME), 2019) -
Editorial
(The American Society of Mechanical Engineers (ASME), 2019) -
Multiphysics Modeling of Pressurized Water Reactor Fuel Performance
(The American Society of Mechanical Engineers (ASME), 2018)Nuclear fuel rods operate under complex radioactive, thermal, and mechanical conditions. Nowadays, fuel rod codes usually make great simplifications on analyzing the multiphysics behavior of fuel rods. The present study ... -
Reviewer's Recognition
(The American Society of Mechanical Engineers (ASME), 2018) -
A Density Functional Theory Study on the Diffusion of Fission Gas Atoms in Uranium Dioxide
(The American Society of Mechanical Engineers (ASME), 2018)Uranium dioxide (UO2) is the typical fuel that is used in the current nuclear power plant; fission gas atoms are produced during and after the nuclear reactor operation; the fission gas atoms have a significant effect on ... -
Sputtering of Graphite by Hydrogen Isotopes in the Fusion Environment: A Molecular Dynamics Simulation Study
(The American Society of Mechanical Engineers (ASME), 2018)The sputtering of graphite due to the bombardment of hydrogen isotopes is crucial to successfully using graphite in the fusion environment. In this work, we use molecular dynamics to simulate the sputtering using the ... -
A Comparative Study of Ten Different Methods on Numerical Solving of Point Reactor Neutron Kinetics Equations
(The American Society of Mechanical Engineers (ASME), 2018)Point reactor neutron kinetics equations describe the time-dependent neutron density variation in a nuclear reactor core. These equations are widely applied to nuclear system numerical simulation and nuclear power plant ... -
Research Progress of Red Oil Explosion Accidents in Nuclear Fuel Reprocessing Plant
(The American Society of Mechanical Engineers (ASME), 2018)From 1953 to now, it has happened six times so-called red oil explosion accidents worldwide, resulting in different degrees of equipment and construction damage and environmental contamination. And research related to red ... -
Assessment of Convective Heat Transfer Correlations Against an Expanded Database for Different Fluids at Supercritical Pressures
(The American Society of Mechanical Engineers (ASME), 2018)Canadian Nuclear Laboratories (CNL) has recently expanded the supercritical heat transfer (SCHT) databank with additional data provided by the Nuclear Power Institute of China (NPIC). These additional data cover flow ... -
Discussion of Tag Gas Method Using in China Experimental Fast Reactor for Failed Fuel Assembly Location
(The American Society of Mechanical Engineers (ASME), 2018)As the first fast reactor of China, the safety of China Experimental Fast Reactor (CEFR) is extremely important, and will decide the future of Chinese fast reactor project. The fuel failure detection system of CEFR provides ...