Journal of Nuclear Engineering and Radiation Science: Recent submissions
Now showing items 621-640 of 913
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Investigation of Fuel Burnup Impacts on Nuclear Reactor Safety Parameters in the Canadian Pressure Tube Supercritical Water-Cool Reactor
(The American Society of Mechanical Engineers (ASME), 2018)The Canadian pressure-tube super critical water-cooled reactor (PT-SCWR) is an advanced generation IV reactor concept which is considered as an evolution of the conventional Canada Deuterium Uranium (CANDU) reactor that ... -
Anticipated Operational Occurrences That Could Develop into Serious Accidents
(The American Society of Mechanical Engineers (ASME), 2018)Nuclear safety analysis and licensing criteria are based upon the concept that plant situations that are expected to have a high frequency of occurrence must not pose a danger to the public, and that plant situations that ... -
Correlation of Interfacial Friction Coefficients for Predicting Countercurrent Flow Limitation at a Sharp-Edged Lower End of Vertical Pipes
(The American Society of Mechanical Engineers (ASME), 2018)One-region (1-R) sensitivity computations with the annular-flow model were carried out for countercurrent flow limitation (CCFL) at a sharp-edged lower end in vertical pipes to generalize the prediction method for CCFL ... -
Parallel Analysis of Linear Systems in CORTH and KYLIN2
(The American Society of Mechanical Engineers (ASME), 2018)Subchannel thermal-hydraulics program named CORe thermal-hydraulics (CORTH) and assembly lattice calculation program named KYLIN2 have been developed in Nuclear Power Institute of China (NPIC). For the sake of promoting ... -
The Influence of Crust Layer on Reactor Pressure Vessel Failure Under Pressurized Core Meltdown Accident
(The American Society of Mechanical Engineers (ASME), 2018)The so-called in-vessel retention (IVR) was considered as a severe accident management strategy and had been certified by Nuclear Regulatory Commission (NRC) in U.S. as a standard measure for severe accident management ... -
Probabilistic-Based Robotic Radiation Mapping Using Sparse Data
(The American Society of Mechanical Engineers (ASME), 2018)This paper presents a novel methodology for generating radiation intensity maps using a mobile robotic platform and an integrated radiation model. The radiation intensity mapping approach consists of two stages. First, ... -
Research on MMPA Algorithm for Solving Detailed Depletion Chain With the NUIT Code
(The American Society of Mechanical Engineers (ASME), 2018)In depletion and transmutation calculation, it is important to solve detailed burnup chains with high computational accuracy and efficiency. This requires the good performance of the burnup algorithms. Nuclide inventory ... -
Research on the Application of Fen for Environmentally Assisted Fatigue Evaluation of the Austenitic SS Pipe Under Combined Transient Loads
(The American Society of Mechanical Engineers (ASME), 2018)Accumulative test data indicate that the effects of the light water reactor (LWR) environment could cause the fatigue resistance of primary pressure boundary components materials to be significantly reduced. Environmentally ... -
Markov/CCMT Dynamic Reliability Analysis of the Main and Startup Feedwater Control System in Nuclear Power Plant
(The American Society of Mechanical Engineers (ASME), 2018)The dynamic reliability of the main and startup feedwater control system in nuclear power plant is evaluated by conducting the Markov cell-to-cell mapping technology (Markov/CCMT) methodology. All the equipment failure ... -
Low-Energy Ion Irradiated Silicon Nanowires: Anomalous Plastic Deformation
(The American Society of Mechanical Engineers (ASME), 2018)We adopted the verified transition state theory, which originates from the quantum chemistry approach to explain the anomalous plastic flow or plastic deformation for Si nanowires irradiated with 100 keV (at room temperature ... -
Editorial Greeting to Journal Readers 2018
(The American Society of Mechanical Engineers (ASME), 2018)ate Editors:Won-Phil Baek (Ph.D.), KAERI, Daejeon, South KoreaAndrey N. Churkin (Ph.D.), OKB «GIDROPRESS», Podolsk, RussiaLin-wen Hu (Ph.D.), MIT, Cambridge, MARafael Macian-Juan (Ph.D.), TUM, Munich, GermanyJoseph S. ... -
Thermal-Hydraulics Program in Support of Canadian SCWR Concept Development
(The American Society of Mechanical Engineers (ASME), 2018)The thermal-hydraulics program in support of the development of the Canadian supercritical water-cooled reactor (SCWR) concept has undergone several phases. It focused on key parameters such as heat transfer, critical flow, ... -
Design Verification for Control Logic in Nuclear Power Plant
(The American Society of Mechanical Engineers (ASME), 2018)The control function for process, heating, ventilation, and air conditioning, and electrical systems in nuclear power plant (NPP) are represented by control logic diagram. To develop distributed control system (DCS), the ... -
Effect of Lead-Bismuth Eutectic Oxygen Concentration on the Onset of Dissolution Corrosion in 316 L Austenitic Stainless Steel at 450 °C
(The American Society of Mechanical Engineers (ASME), 2018)This work focuses on the effect of dissolved oxygen concentration in liquid lead-bismuth eutectic (LBE) on the onset of dissolution corrosion in a solution-annealed 316 L austenitic stainless steel. Specimens made of the ... -
Experimental Demonstration of Safety of AHWR during Stagnation Channel Break Condition in an Integral Test Loop
(The American Society of Mechanical Engineers (ASME), 2018) -
Summary on the Results of Two Computational Fluid Dynamic Benchmarks of Tube and Different Channel Geometries
(The American Society of Mechanical Engineers (ASME), 2018)Two computational fluid dynamic (CFD) benchmarks have been performed to assess the prediction accuracy and sensitivity of CFD codes for heat transfer in different geometries. The first benchmark focused on heat transfer ... -
Mechanical Properties of Cubic (U,Zr)O2
(The American Society of Mechanical Engineers (ASME), 2018)Evaluation of fuel debris properties in the Fukushima Daiichi nuclear power plant (1F) is required to develop fuel debris removal tools. In the removal of debris resulting from the Three Mile Island unit 2 (TMI-2) accident, ... -
Numerical Investigation of Convective Heat Transfer to Supercritical Pressure Hydrogen in a Straight Tube
(The American Society of Mechanical Engineers (ASME), 2018)Hydrogen is adopted as coolant for regenerative cooling nozzle and reactor core in nuclear thermal propulsion (NTP), which is a promising technology for human space exploration in the near future due to its large thrust ... -
Nuclear Radiation Monitoring Using Plants
(The American Society of Mechanical Engineers (ASME), 2018)Plants exhibit complex responses to change in environmental conditions such as radiant heat flux, water quality, airborne pollutants, and soil contents. We seek to utilize natural chemical and electrophysiological response ... -
Precautions at Fukushima That Would Have Suppressed the Accident Severity
(The American Society of Mechanical Engineers (ASME), 2018)The Great East Japan Earthquake on Mar. 11, 2011 triggered huge tsunami waves that attacked Fukushima Daiichi Nuclear Power Plant (Fukushima-1). Units 1, 3, and 4 had hydrogen explosions. Units 1–3 had core meltdowns and ...