Journal of Nuclear Engineering and Radiation Science: Recent submissions
Now showing items 461-480 of 913
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Experimental and Numerical Analysis of Mixing Process of Two Component Gases in a Vertical Fluid Layer in a VHTR
(American Society of Mechanical Engineers (ASME), 2019)When a depressurization accident of a very-high-temperature reactor (VHTR) occurs, air is expected to enter into the reactor pressure vessel from the breach and oxidize in-core graphite structures. Therefore, in order to ... -
Spatial Spectrum From Particle Image Velocimetry Data
(American Society of Mechanical Engineers (ASME), 2019)We present a simple method of obtaining the turbulence kinetic energy spectrum from spatially resolved particle image velocimetry (PIV) data without need of use of Taylor hypothesis of frozen turbulence. Additionally, this ... -
Research on a Transonic Supercritical Carbon Dioxide Centrifugal Turbine
(American Society of Mechanical Engineers (ASME), 2019)Recently, the supercritical carbon dioxide Brayton (SCO2) cycle gained a lot of attention for its application to next-generation nuclear reactors. Turbine is the key component of the energy conversion in the thermodynamic ... -
A Study of Transverse Buckling Effect on the Characteristics of Nuclides Burnup Wave in a Fast Neutron Multiplying Media
(American Society of Mechanical Engineers (ASME), 2019)A study of transverse buckling effect on the characteristics of nuclides burnup wave in multiplying media (cylindrical geometry) has been carried out. The burnup wave is characterized in terms of velocity of propagation, ... -
Micro-Calorimetric Study on the Thermal Stability of N, N-Dimethylhydroxylamine in the APOR Process
(American Society of Mechanical Engineers (ASME), 2019)The thermal stability of N, N-dimethylhydroxylamine (DMHAN) in the HNO3 solution was studied using microcalorimeter. The influence of concentration of HNO3, DMHAN, methylhydrazine (MH), atmosphere (air and nitrogen), and ... -
Use of Irradiated Fracture Toughness Values in Nuclear Vessel and Component Design Specifications for Fitness-For-Service Analysis Using the Unified Curve Method
(American Society of Mechanical Engineers (ASME), 2019)The American Society of Mechanical Engineers (ASME) Section III Rules for Construction of Nuclear Facility Components subsection NB-2331 Material for Vessels requires that the effects of irradiation shall be considered on ... -
Glasses for Nuclear Waste Immobilization. Effect of Lutetium Addition on Yttrium Aluminosilicate Glass Crystallization Kinetics
(American Society of Mechanical Engineers (ASME), 2019)Glasses have emerged as alternative materials that can be used for long-term treatment and management of radioactive waste. Specifically, glasses can be used as a matrix to immobilize the radioactive material. Within the ... -
Preliminary Experiments While Designing a Cold Crucible for Metal Melting
(American Society of Mechanical Engineers (ASME), 2019)This article deals with issues arising during the design and production of a cold crucible (CC) for melting metals and alloys using electromagnetic induction. The article deals particularly with the results from tests and ... -
Experimental Demonstration of Safety During Extended Station Blackout in an Integral Test Loop of a Natural Circulation Boiling Water Reactor
(American Society of Mechanical Engineers (ASME), 2019)Decay heat removal for prolonged period of station blackout (SBO) is a safety concern of the nuclear reactors. Aftermath of Fukushima, safety evaluation (performance under severe conditions: stress test) of the reactors ... -
Testing of Scintillation Detectors in Quasi-Monoenergetic Neutron Spectra in a Silicon Filtered Neutron Beam at the LVR-15 Research Reactor
(American Society of Mechanical Engineers (ASME), 2019)With increasing needs of neutron detection in energy and homeland security sectors, there is an aim in the development of new suitable detection materials with possible n/g separation and also satisfactory resolution. This ... -
Corrosion Experiments on Ceramic Samples Within Molten Salts
(American Society of Mechanical Engineers (ASME), 2019)The molten salts can provide many possibilities for their use, e.g., an electrolyte in fuel cells or as a heat transfer medium and an oxygen transporter for flameless oxidation in molten salt oxidation (MSO) technology. ... -
Effect of the Surface Grinding on the Environmentally Assisted Crack Initiation of 316 L Steel in Simulated Pressurized Water Reactor Water
(American Society of Mechanical Engineers (ASME), 2019)This paper presents results on the effect of a surface treatment on the environmentally assisted corrosion cracking in a pressurized water reactor chemistry. Slow strain rate testing of 316 L austenitic steel with selected ... -
Verification and Validation of SuperMC3.2 Using VENUS-3 Benchmark Experiments
(American Society of Mechanical Engineers (ASME), 2019)Methodological processes for nuclear power plant (NPP) pressure vessels' (PV) neutron fluence rate determination take the form of experimental measurement or theoretical calculations. However, the process of experimental ... -
Measuring System for Recuperation Units
(American Society of Mechanical Engineers (ASME), 2019)The article is primarily concerned with the measurement of heat recovery units for different work environments. At present, great emphasis is placed on indoor air quality. The quality of the indoor environment greatly ... -
Experimental Investigation of Melt Coolability and Ablation Behavior of Oxidic Sacrificial Material at Prototypic Conditions in Scaled Down Core Catcher
(American Society of Mechanical Engineers (ASME), 2019)To minimize the potential risk of design extension conditions (DEC) with core meltdown, some advanced reactors employ ex-vessel core catchers which stabilize and cool the corium for prolonged period by strategically flooding ... -
Improvement of Corrosion Resistance of Dissimilar Welded Joints in VVER Secondary Circuit
(American Society of Mechanical Engineers (ASME), 2019)This article presents experimental program, focused on extending lifetime and operation reliability of dissimilar welded joints of austenitic and perlite steel in conditions of secondary circuit media of water–water power ... -
Numerical Analysis of Slotted Airfoil Fins for Printed Circuit Heat Exchanger in S-CO2 Brayton Cycle
(American Society of Mechanical Engineers (ASME), 2019)Recuperator is one of the most important components in supercritical carbon dioxide (S-CO2) Brayton cycle, and the printed circuit heat exchanger (PCHE) has been considered as a promising candidate due to its high efficiency ... -
Evaluation of Dump Tank Coolability in PHWRs During Late-Phase Severe Accident
(American Society of Mechanical Engineers (ASME), 2019)In some of the older design of pressurized heavy water reactors (PHWRs), such as in Rajasthan Atomic Power Station (RAPS) and Madras Atomic Power Station (MAPS), in case of a severe accident, the debris/corium may cause ... -
Qualification Requirements Design for Neutron Absorber Plate for Spent Fuel Racks in Domestic Nuclear Power Plants
(American Society of Mechanical Engineers (ASME), 2019)Boron carbide (B4C) particle-reinforced aluminum matrix composite is the key material for use as neutron absorber plate in fuel storage applications for Generation III advanced passive nuclear power plants in China. This ... -
Preparation of UF4 by Carbochlorination of U3O8 and Solid-State Halogen Exchange Reaction
(American Society of Mechanical Engineers (ASME), 2019)Uranium tetrafluoride was synthesized using a novel method, which consists of a combination of carbochlorination reaction between a mixture of U3O8 and sucrose carbon with chlorine, and a solid-state halogen exchange ...