Journal of Nuclear Engineering and Radiation Science: Recent submissions
Now showing items 281-300 of 913
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Numerical Simulation of Container Breach and Airborne Release of Solids Due to Mechanical Insults
(The American Society of Mechanical Engineers (ASME), 2021)Throughout U.S. Department of Energy (DOE) complexes, safety engineers employ the five-factor formula to calculate the source term (ST) that includes parameters of airborne release fraction (ARF), respirable fraction (RF) ... -
Pressurized Water Reactor Mixed Oxide/UO2 Transient Benchmark Calculations Using Monte Carlo Serpent 2 Code and Open Nodal Core Simulator ADPRES
(The American Society of Mechanical Engineers (ASME), 2021)This paper presents static and transient solutions for the pressurized water reactor (PWR) MOX/UO2 transient benchmark by Serpent 2 Monte Carlo (MC) code and open nodal core simulator called Abu Dhabi Polytechnic Reactor ... -
Experimental and Numerical Investigation of Solidification of Gallium in an Initially Emptied Horizontal Pipe Flow
(The American Society of Mechanical Engineers (ASME), 2021)In a reactor core meltdown under postulated severe accidents, the molten material (corium) could be ejected or relocated through existing vessel penetrations (cooling pipe connections), thus potentially contaminating other ... -
Effect of Sequential Helium and Nickel Ion Implantation on the Nano-Indentation Hardness of X750 Alloy
(The American Society of Mechanical Engineers (ASME), 2021)Sequential He+ and Ni+ implantations were performed to investigate their combined effect on the indentation hardness of heat-treated X750 alloy. The microstructure of the ion-implanted region was also characterized with ... -
Canonical Implementation of Simplified Spherical Harmonics (SPL) in the Neutron Diffusion Code AZNHEX
(The American Society of Mechanical Engineers (ASME), 2021)The SPL approximation has been used to improve the accuracy of neutron transport solvers and has been widely used thanks to the diffusion like equations that can be solved with traditional diffusion codes. The objective ... -
Determination of CR-39 and LR-115 Type II Mean Critical Angle of Etching Using a New Monte Carlo Code
(The American Society of Mechanical Engineers (ASME), 2021)CR-39 and LR-115 type II solid state nuclear track detectors (SSNTDs) are used, in order to assess the concentration of nuclides belonging to 238U and 232Th series, and these ones can be also used to measure the contents ... -
Design of Condensation Heat Transfer Experiment to Evaluate Scaling Distortion in Small Modular Reactor Safety Analysis
(The American Society of Mechanical Engineers (ASME), 2021)Designing a novel scaled modular test facility as a part of an experiment for condensation heat transfer (CHT) in small modular reactors (SMRs) is the main focus of this study. This facility will provide data to evaluate ... -
Forced Convective Boiling in a Vertical Annular Test Section With Seawater Coolant
(The American Society of Mechanical Engineers (ASME), 2021)In case of some nuclear reactors, seawater is used as an emergency resource to remove the decay heat from the reactor core. This study aims to improve the understanding of boiling heat transfer with seawater coolants. Under ... -
Supercritical Water Choking Flow Experiments Through a Convergent-Divergent Test Section
(The American Society of Mechanical Engineers (ASME), 2021)The heat transport system of Gen-IV supercritical water-cooled reactors (SCWRs) will operate at pressures close to 25 MPa and outlet temperatures of up to 625 °C. The design and safety analyses of this type of reactors ... -
Optimization of the PGV-1000MKO Steam Generator Using Computation Fluid Dynamics
(The American Society of Mechanical Engineers (ASME), 2021)This paper presents the work carried out in Experimental and design organization OKB “GIDROPRESS” to justify the separation characteristics of VVER-TOI steam generator (SG) using the STAR-CCM+ CFD-code. In the VVER-TOI ... -
GTAW Welded Inconel 625 Alloy Fuel Cladding for the Canadian SCWR: Microstructure and Mechanical Property Characterization
(The American Society of Mechanical Engineers (ASME), 2021)Inconel 625 is considered one of the candidate materials for reactor fuel cladding in the Canadian supercritical water reactor (SCWR) design. Gas tungsten arc welding (GTAW) is being evaluated as a joining technique for ... -
Investigating Small Modular Reactor's Design Limits for Its Flexible Operation With Photovoltaic Generation in Microcommunities
(The American Society of Mechanical Engineers (ASME), 2021)Use of flexible and dispatchable generation from the small modular reactors (SMRs) in combination with the nondispatchable generation from renewable energy systems (RES) can be an effective alternative to pursue the mandate ... -
Passive and Walk-Away Safe Small and Microreactors for Electricity Generation and Production of Process Heat for Industrial Uses
(The American Society of Mechanical Engineers (ASME), 2021)This paper presents the passive design and safety features as well as the biological dose estimates for end-of-life handling of postoperation for the walk-away safe, scalable liquid metal-cooled small modular (SLIMM) and ... -
Techno-Economic Study on Implementation of Inventory Control Requirements for a Nuclear-Powered Closed-Cycle Gas Turbine Power Plant
(The American Society of Mechanical Engineers (ASME), 2021)The use of an inventory control system offers a unique benefit of stable cycle thermal efficiency during part-load operation. This article focuses on the influence of initial inventory tank pressure on the control level ... -
Heat Transfer in Supercritical Fluids: A Review
(The American Society of Mechanical Engineers (ASME), 2021)Supercritical fluids (SCF) find potential applications in the upcoming energy systems due to various advantages associated with them. One of such applications is nuclear reactor where supercritical water and carbon-dioxide, ... -
A Comparative Study on Severe Accident Phenomena Related to Melt Progression in Sodium Fast Reactors and Pressurized Water Reactors
(The American Society of Mechanical Engineers (ASME), 2020)The nuclear safety approach has to cover accident sequences involving core degradation in order to develop reliable mitigation strategies for both existing and future reactors. In particular, the long-term stabilization ... -
Detection of Neutrons Emitted From Reactor Primary Circuit Water by Discontinuing Flow Method
(The American Society of Mechanical Engineers (ASME), 2020)On-line activity measurement of fission products in a primary circuit water is often used for a fuel failure detection in research and power nuclear reactors. When gamma spectrometry is used for the activity measurement, ... -
Microstructural Evaluation of Alloy 800H After SCWL Exposure
(The American Society of Mechanical Engineers (ASME), 2021)Alloy 800H is a candidate material for supercritical water-cooled reactors (SCWR), specifically for in-core components in Canadian-type SCWR, that will operate at a pressure of 25 MPa and a core temperature from 350 °C to ... -
Mechanical Tests Results of Laser Shock Peening-Treated Austenitic Steel
(The American Society of Mechanical Engineers (ASME), 2020)The presented paper is focused on laser shock-peening technology for hardening the metallic material surface. The material surface hardening improve fatigue performance, static properties, and resistance to stress corrosion ... -
Basic Microstructural Characterization of Second Phases in Homogeneous Weld Joint Made of X6CrNiNbN25-20 Steel After Long-Term Exposure Time at 973 K
(The American Society of Mechanical Engineers (ASME), 2020)New blocks of fossil fuel power plants designed for steam temperatures above 873 K require advanced stainless steels as material for superheater or reheater systems. Weld joints are critical parts in fossil power units. ...