Journal of Nuclear Engineering and Radiation Science: Recent submissions
Now showing items 481-500 of 913
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Electrical Power System Modeling of Atucha II Nuclear Power Plant Using etap
(American Society of Mechanical Engineers (ASME), 2019)This work shows the introduction of the Electrical Power System Analysis (etap) software as a calculation and analysis tool for power electrical systems of the nuclear power plants (NPP) under the orbit of Nucleoeléctrica ... -
Thermal–Hydraulic Design in the Transition Laminar–to–Turbulent Flow Regime
(American Society of Mechanical Engineers (ASME), 2019)Difficulties are experienced during the thermal–hydraulic design of a nuclear reactor operating in the transition flow regime and are the result of the inability to accurately predict the heat transfer coefficient (HTC). ... -
The Risk of Extended Power Loss and the Probability of Emergency Restoration for Severe Events and Nuclear Accidents
(American Society of Mechanical Engineers (ASME), 2019)This paper gives a complete account of recent work on the prediction of power restoration in severe accidents and events, and quantifies the benefits and impact of deploying back-up or emergency power systems in nuclear ... -
Preliminary Investigations of the Feasibility of In-Vessel Melt Retention Strategies for a Small Modular Reactor Concept
(American Society of Mechanical Engineers (ASME), 2019)The study presented in this paper is part of the technological surveillance performed at the Electricité De France (EDF) Research and Development (R&D) Center, in the Pericles department, and investigates the feasibility ... -
Sensitivity Analysis of the Thermal Diffusion Coefficient Effect on the Departure From Nucleate Boiling Ratio With the VIPRE Code
(American Society of Mechanical Engineers (ASME), 2019)One of the limiting conditions during operation of a pressurized water reactor (PWR) is cladding integrity in class I (normal operations) or class II (most frequent). Cladding integrity is limited typically by the departure ... -
Measurement of Selected Differential Cross Sections in 235U Spectrum
(American Society of Mechanical Engineers (ASME), 2019)This paper describes the measurement of 55Mn(n,2n) and 127I(n,2n) reaction rates in a well-defined reactor field in a special core of LR-0 reactor. The reaction rates were derived using gamma-spectrometry by measuring gamma ... -
Experimental Demonstration of Decay Heat Removal by Submerged Feeders in a Full-Scale Test Facility of a Natural Circulation Boiling Water Reactor
(American Society of Mechanical Engineers (ASME), 2019)Removal of decay heat with nonavailability of active systems is a safety issue especially during station blackout (SBO) in a light water reactor. Passive systems are being incorporated in the new designs of nuclear reactors ... -
A Study on Onset of Liquid Entrainment in Low Pressure Depressurization System of Advanced Passive Pressurized Water Reactors
(American Society of Mechanical Engineers (ASME), 2019)The low-pressure depressurization system (LPDS) of advanced passive pressurized water reactors (PWRs) is designed to provide depressurization of the reactor coolant system during a small break loss-of-coolant accident ... -
Suite for Smooth Particle Hydrodynamic Code Relevant to Spherical Plasma Liner Formation and Implosion
(American Society of Mechanical Engineers (ASME), 2019)Three-dimensional (3D) modeling of magneto-inertial fusion (MIF) is at a nascent stage of development. A suite of test cases relevant to plasma liner formation and implosion is presented to present the community with some ... -
Analysis of Loss of Heat Sink for ITER Divertor Cooling System Using Modified RELAP/SCDAPSIM/MOD 4.0
(American Society of Mechanical Engineers (ASME), 2019)The present work includes thermal hydraulic modeling and analysis of loss of heat sink (LOHS) accident for the ITER divertor cooling system. The analysis is done for the new design of full tungsten divertor. The new design ... -
Safety Constraints of Instrumental and Control Algorithm Configuration Based on SCADE Platform
(American Society of Mechanical Engineers (ASME), 2019)Algorithm library plays an important role in digital instrument control system. In the design process, software testing and safety verification are focused on safety and reliability of the algorithm library. The configured ... -
Production of Realistic Flaws and Their Meaning for Ultrasonic Testing
(American Society of Mechanical Engineers (ASME), 2019)This work is designed to artificially create test specimens with flaws that behave the same way as real-function flaws when observed by nondestructive testing (NDT) technologies. Thus, the understanding of the detection ... -
Deceleration Performance and Parameter Influence Analysis of the Control Rod Hydraulic Deceleration Device for Control Rod Hydraulic Drive System
(American Society of Mechanical Engineers (ASME), 2019)Control rod hydraulic drive system (CRHDS), which is invented by INET, Tsinghua University, is a new type of internal control rod drive technology. Control rod hydraulic deceleration device (CRHDD), which consists of the ... -
Effect of Steam Temperature and Pressure on the Oxidation of Potential Coating Alloy FeCrAl for Supercritical Water-Cooled Reactor Application
(American Society of Mechanical Engineers (ASME), 2019)MCrAl (M = Fe, Ni, or Co) alloys have exceptional corrosion and oxidation resistance and can be used as both oxidation resistant structural materials and coatings. As coatings, they protect high temperature steels or Ni ... -
Large Scale Pressurized Water Reactor Passive Containment Cooling System Wind Tunnel Test
(American Society of Mechanical Engineers (ASME), 2019)The objective of the current work is to shed light on studying the air flow features of the air path which is part of the passive containment cooling system (PCS) in a pressurized water reactor design. A wind tunnel test ... -
Neutronic and Thermo-Hydraulic Analyses of Water-Cooled Blanket Based on Pressurized/Supercritical Water Conditions for CFETR
(American Society of Mechanical Engineers (ASME), 2019)China Fusion Engineering Test Reactor (CFETR) is a test tokamak reactor being designed in China to bridge the gap between International Thermonuclear Experimental Reactor (ITER) and future fusion power plant. As one of the ... -
The Behavior of Corundum Ceramic in Molten Salt
(American Society of Mechanical Engineers (ASME), 2019)The technology of molten salt oxidation (MSO) is a thermal treatment process mainly used for reprocessing of hazardous organic waste. This technology is considered as an alternative to the conventional incineration processes. ... -
Current Status and Future Developments in Nuclear-Power Industry of the World
(American Society of Mechanical Engineers (ASME), 2019)It is well known that electrical-power generation plays the key role in advances in industry, agriculture, technology, and standard of living. Also, strong power industry with diverse energy sources is very important for ... -
Analyses of the Associated Technical and Economic Risks of the Simple and Intercooled Brayton Helium Recuperated Gas Turbine Cycles for Generation IV Nuclear Power Plants
(American Society of Mechanical Engineers (ASME), 2019)The simple cycle recuperated (SCR) and intercooled cycle recuperated (ICR) are highly efficient Brayton helium gas turbine cycles, designed for the gas-cooled fast reactor (GFR) and very-high-temperature reactor (VHTR) ... -
On One Imperfection Estimation Method for Thin Shell Buckling in the Design Code RCC-MR
(American Society of Mechanical Engineers (ASME), 2019)The thin shell design code RCC-MR is used for sodium-cooled fast breeder reactor components operating at high temperatures. Thin shells from such applications can be designed using linear elastic buckling analysis, following ...