Journal of Nuclear Engineering and Radiation Science: Recent submissions
Now showing items 341-360 of 913
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Toward a Mechanistic Model of Stress Corrosion Cracking in PHWR Fuel Sheaths
(The American Society of Mechanical Engineers (ASME), 2020)This work builds on the iodine-induced stress corrosion cracking (ISCC) model of Lewis and Kleczek by integrating the fuel performance model fuel and sheath modeling tool (FAST) to provide thermal and mechanical analysis ... -
Preparation and Characterization of Nb-1Zr-0.1C Alloy Suitable for Liquid Metal Coolant Channels of High Temperature Reactors
(The American Society of Mechanical Engineers (ASME), 2020)A novel process comprising of aluminothermic coreduction of mixed oxides followed by arc and electron beam melt refining was developed for preparation of Nb-1Zr-0.1C alloy. The parameters of the process were optimized by ... -
Ni+ and He+ Implantation Effects on the Hardness and Microstructure of Heat-Treated X750 Superalloy
(The American Society of Mechanical Engineers (ASME), 2020)Nickel and Helium ion implantation-induced hardening and microstructural evolution of X750 in the heat-treated (HT) and solution annealed (SA) conditions were investigated using nano-indentation hardness testing and electron ... -
The Other Metallic Phase in Spent Nuclear Fuel: A Complete Thermodynamic Evaluation of the U–Pd–Rh–Ru System
(The American Society of Mechanical Engineers (ASME), 2020)During burnup of nuclear fuel, fission products accumulate. Post-irradiation examination of burned up nuclear fuel has revealed the presence of several phases, namely, the fuel matrix of UO2, with dissolved oxides present; ... -
A Simplified Two-Group Multipoint Kinetics Model
(The American Society of Mechanical Engineers (ASME), 2020)Detailed multiphysics modeling of nuclear power plants has become a necessity in the era of best-estimate analysis. For a number of transients with strong coupling between the neutronics in the reactor core and the ... -
Total Cross Section Phenomenological Formulas for X-Ray and Gamma Radiation Interaction With Matter for Different Energies and Absorber Types
(The American Society of Mechanical Engineers (ASME), 2020)The in-function log-polynomial regression method for empirical approximations of physical relationships was presented and applied in practice. Thanks to that the single phenomenological equation for the total cross section ... -
Improved Computational Fluid Dynamics Framework for Reactor Core Baffle Swelling Assessment
(The American Society of Mechanical Engineers (ASME), 2020)This paper presents an improved estimation of reactor core baffle temperature distribution, during operation, at the nominal power level to address swelling problems of the reactor internals. Swelling is the main limiting ... -
Experimental Investigation of Flow Instability Between Two Vertical Parallel Channels Using Supercritical CO2
(The American Society of Mechanical Engineers (ASME), 2020)Supercritical flow experiments were conducted at University of Manitoba using supercritical flow facility-vertical (SFF-V), which is a two vertical parallel channel assembly. The working fluid was CO2 at supercritical ... -
Nonhyperbolicity of Conservation Equations of RELAP5 Two-Fluid Model in Nuclear Reactor Safety Results (Investigation and Eigenvalue Analysis)
(The American Society of Mechanical Engineers (ASME), 2020)The RELAP5 code simulates the thermal-hydraulic characteristics of nuclear reactors by the use of a two-fluid one-dimensional, nonequilibrium, nonhomogeneous two-phase flow model. This model consists of six governing ... -
Flow Instability Investigation at Supercritical Pressures in Parallel Channels by Computational Fluid Dynamics Adopting Low- and High-Power Boundaries
(The American Society of Mechanical Engineers (ASME), 2020)Supercritical water-cooled reactor (SCWR), which is considered as the logical extension of existing light water reactors (LWRs) (pressurized water reactor and boiling water reactor (BWR)), has the potential of increasing ... -
Study on Melt Coolability and Water Ingression Through Melt Pool in Scaled Down Core Catcher—The Influence of Vessel Angle
(The American Society of Mechanical Engineers (ASME), 2020)An ex-vessel core catcher is generally used in advanced reactors to mitigate core melt scenarios by stabilizing and cooling the corium for prolonged period by strategically flooding it. The side indirect cooling along with ... -
The Intersection of Advancing Technology and Human Performance
(The American Society of Mechanical Engineers (ASME), 2020)Today's sensory and processing technologies are perceptive and precise. They can discern the environment, solve complicated problems, make assessments, and learn from experience. Although they do not think the way humans ... -
Message From Shoujun Wang, Chinese Nuclear Society President
(The American Society of Mechanical Engineers (ASME), 2020)Lastly, I wish you all the best and stay in good health!Chinese Nuclear Society has established long-term and stable cooperation with ASME and JSME. Thanks to the joint efforts of the three parties, International Conference ... -
Greetings From JSME PESD
(The American Society of Mechanical Engineers (ASME), 2020)It is my pleasure to say New Year's greeting to readers, reviewers, and editors of the ASME Journal of Nuclear Engineering and Radiation Science (NERS) as a chair of the Power Energy Systems Division (PESD) of the Japan ... -
Reviewer's Recognition
(The American Society of Mechanical Engineers (ASME), 2020)The Reviewers of the Year Award is given to reviewers who have made an outstanding contribution to the journal in terms of the quantity, quality, and turnaround time of reviews completed during the past 12 months. The prize ... -
ASME Nuclear Engineering Division Chair's Message
(The American Society of Mechanical Engineers (ASME), 2020)As the NED chair, it is my highest honor to recognize the contributions and thank ASME Staff, the present and past NED members, especially the members and past chairs of the Executive Committee, for their foresight, prudence, ... -
Editorial
(The American Society of Mechanical Engineers (ASME), 2020)e-mail: igor.pioro@uoit.caOshawa, ON L1G 0C5, Canada2000 Simcoe Street North,University of Ontario Institute of Technology,Faculty of Energy Systems and Nuclear Science,Editor, Journal of Nuclear Engineering and Radiation Science -
Radiographic Nondestructive Testing Simulations Using gate Software Toolkit
(The American Society of Mechanical Engineers (ASME), 2020)A workspace is created within the geant4 Application for Tomographic Emission (gate) software toolkit for radiographic nondestructive testing (NDT) simulations. The workspace contains models for X-ray and gamma ray emissions, ... -
RELAP5-3D Three-Dimensional Analysis Based on PHÉNIX Dissymmetric Transient Test
(The American Society of Mechanical Engineers (ASME), 2020)Before the final shutdown of the PHÉNIX fast reactor, the CEA carried out a final set of experimental tests to gather data and additional knowledge on relevant sodium fast reactors (SFR) operation and safety aspects. One ... -
Simulation of the Performance of the Venturi Scrubber for an Advanced Reactor Containment Venting Conditions
(The American Society of Mechanical Engineers (ASME), 2020)Post Fukushima, nuclear plants are being retrofitted with severe accident mitigation measures. For attaining depressurization of the containment and mitigate the consequences of the release of the radioactivity to the ...