Journal of Nuclear Engineering and Radiation Science: Recent submissions
Now showing items 441-460 of 913
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Performance Modeling and Analysis of a Single-Shaft Closed-Cycle Gas Turbine Using Different Operational Control Strategy
(The American Society of Mechanical Engineers (ASME), 2020)In the last few years, one considerable factor for the viability and interest in the closed-cycle gas turbine (GT) systems for nuclear or conventional power plant application is its potential to maintain high cycle performance ... -
A Study of the Reproducibility and Diversity of the Supply Chain in Manufacturing Hot Isostatically Pressed Type 316L Stainless Steel Components for the Civil Nuclear Sector
(The American Society of Mechanical Engineers (ASME), 2020)Hot isostatic pressing (HIP) of type 316 L stainless steel powder has been an established manufacturing practice for more than 25 years in the oil and gas sector and more recently in the naval defense sector. To demonstrate ... -
Evaluation of Radiation Effects on Residents Living Around the NSRR Under External Hazards
(The American Society of Mechanical Engineers (ASME), 2020)The nuclear safety research reactor (NSRR) is a research reactor of training research isotopes general atomics—annular core pulse reactor (TRIGA-ACPR) type, located in the Nuclear Science Research Institute (NSRI). The ... -
Angular Distribution of Neutrons Around Thick Beryllium Target of Accelerator-Based 9Be(d, n) Neutron Source
(The American Society of Mechanical Engineers (ASME), 2020)An experimental work and simulations were carried out to determine the angular distributions of neutrons and yields of the 9Be(d, n) reaction over all angular range (360 deg) on a thick beryllium target as an accelerator-based ... -
Analyses of Gas Stratification Erosion by a Vertical Jet in Presence of an Obstacle Using the GOTHIC Code
(The American Society of Mechanical Engineers (ASME), 2020)The GOTHIC code was validated using three experiments carried out in the PANDA facility in the framework of the OECD/NEA HYMERES project. These tests addressed the mixing of an initially stratified atmosphere by means of ... -
A New Approach to Generalization of Experimental Data on Heat Transfer to Fluids in Supercritical Region
(The American Society of Mechanical Engineers (ASME), 2020)The paper contains the results of analysis of heat transfer regimes in the case of forced turbulent flow of water and modeling fluids in channels of various configurations at supercritical pressures. Two new complex criteria ... -
Statistical Burnup Distribution of Moving Pebbles in the High-Temperature Reactor HTR-PM
(The American Society of Mechanical Engineers (ASME), 2020)In the pebble-bed high-temperature reactor under construction in China, called the HTR-PM, the spherical fuel elements continuously flow downward in the cylindrical core. The burnup of each pebble is checked at the core ... -
External Hazard Coinciding With Small Break LOCA—Thermohydraulic Calculation With System Code ATHLET
(The American Society of Mechanical Engineers (ASME), 2020)The safety behaviors of a nuclear power plant (NPP) after an external hazard-initiated event, as well as after a small break (SB) loss of coolant accident (LOCA), are already well known as part of the analyses made for ... -
A Study on Sodium–Concrete Reaction in Presence of Internal Heating
(The American Society of Mechanical Engineers (ASME), 2020)The sodium–concrete reaction (SCR) is an important phenomenon during severe accidents in sodium-cooled fast reactors (SFRs), as it generates large volumes of hydrogen and aerosols in the containment vessel along with ... -
An Experimental and Numerical Study of Wall Effect on Freeze Valve Performance in a Molten Salt Reactor
(The American Society of Mechanical Engineers (ASME), 2020)Freeze valve is an important passive safety system used in the molten salt reactor (MSR). In the freeze valve, salt is frozen by external cooling in the pipe connecting the reactor core and drain tanks. On the occasion of ... -
Experimental Validation of ANSYS CFX for Transient Flows With Heat Transfer in a Tubular Heat Exchanger
(The American Society of Mechanical Engineers (ASME), 2020)Within the European SESAME project, extensive experimental work was performed and complemented by the development, application, and validation activities of thermal-hydraulic simulation tools for different scales. The ... -
Advanced Natural Circulation Reduced-Order Model With Inclined Channel for Low Pressure Conditions
(The American Society of Mechanical Engineers (ASME), 2020)Natural circulation with two-phase flow is a nonlinear dynamical systems, which can show a very complex and strange behavior under specific conditions. The application of stability analysis requires a large computational ... -
Performance Analyses and Evaluation of Co2 and N2 as Coolants in a Recuperated Brayton Gas Turbine Cycle for a Generation IV Nuclear Reactor Power Plant
(The American Society of Mechanical Engineers (ASME), 2020)As demands for clean and sustainable energy renew interests in nuclear power to meet future energy demands, generation IV nuclear reactors are seen as having the potential to provide the improvements required for nuclear ... -
Performance Simulation to Understand the Effects of Multifluid Scaling of Gas Turbine Components for Generation IV Nuclear Power Plants
(The American Society of Mechanical Engineers (ASME), 2020)A significant hurdle in the development of performance simulation tools to analyze and evaluate nuclear power plants (NPP) is finding data relating to component performance maps. As a result, engineers often rely on an ... -
Special Section: ICONE-26
(The American Society of Mechanical Engineers (ASME), 2020)This Special Section in this issue of the ASME Journal of Nuclear Engineering and Radiation Science is dedicated to selected papers from the 26th International Conference on Nuclear Engineering (ICONE-26) held in London, ... -
From Micro to Nano: Material Characterization Methods for Testing of Nuclear Core and Structural Materials
(American Society of Mechanical Engineers (ASME), 2019)Nuclear grade fuel claddings act as a barrier against release of fuel particles into the coolant water during nuclear power plant operation, handling, and wet or dry storage of the spent fuel rods. The integrity of claddings ... -
VVER 1000 Severe Accident Analyses Using MELCOR Code
(American Society of Mechanical Engineers (ASME), 2019)This work describes the computer model development of the water–water energetic reactor (VVER) 1000 nuclear power plant (NPP) in the methods for estimation of leakages and consequences of releases (MELCOR) 1.8.6 code and ... -
Estimation of Tritium and Dust Source Term in European DEMOnstration Fusion Reactor During Accident Scenarios
(American Society of Mechanical Engineers (ASME), 2019)The safety features of the future nuclear fusion reactors are one of the key issues for their attractiveness if compared with the fission plants. In fusion devices, accidents with high release of radioactive materials have ... -
Guest Editorial: Special Section on Research Center Řež: Nuclear-Engineering Activities in 2018
(American Society of Mechanical Engineers (ASME), 2019) -
Assessment of the TRACE Code for the He-Cooled Systems Simulation Capability Against Some He-FUS3 Experimental Measurements
(American Society of Mechanical Engineers (ASME), 2019)This paper focuses on the TRACE code assessment for helium-cooled systems thermal-hydraulic analysis. In the frame of the GoFastR (gas cooled fast reactor) European Collaborative Project, ENEA has offered some selected ...