Journal of Nuclear Engineering and Radiation Science: Recent submissions
Now showing items 501-520 of 913
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Computational Fluid Dynamics Simulation of Flow-Mixing and Heat Transfer in 4 × 4 Rod Bundle With a Twist-Vane Spacer Grid
(American Society of Mechanical Engineers (ASME), 2019)The clearance between fuel rods is maintained by spacer grid or helical wire wrap. Thermal-hydraulic characteristics inside fuel rod bundle are strongly influenced by the spacer grid geometry and the bundle pitch-to-diameter ... -
Improvement of Probabilistic Fracture Mechanics Analysis Code PASCAL-SP With Regard
(American Society of Mechanical Engineers (ASME), 2019)Probabilistic fracture mechanics (PFM) analysis is expected to be a rational method for structural integrity assessment because it can consider the uncertainties of various influence factors and evaluate the quantitative ... -
Thermomechanical Safety Analyses for a 238Pu Production Target at the HFIR
(American Society of Mechanical Engineers (ASME), 2019)Safety analyses at the high flux isotope reactor (HFIR) are required to qualify irradiation of production targets containing neptunium dioxide/aluminum cermet (NpO2/Al) pellets for the production of plutonium-238 (238Pu). ... -
An Analytical Solution for the Two-Group Diffusion Theory Analysis of Multiregion Source-Driven Systems
(American Society of Mechanical Engineers (ASME), 2019)An analytical solution of the two-group diffusion equations is derived for multiregion source-driven subcritical systems in spherical geometry. An analytical formulation for the calculation of the effective multiplication ... -
Study on Thallium Bromide Radioactive Detector
(American Society of Mechanical Engineers (ASME), 2019)Thallium bromide (TlBr) is a compound semiconductor material, which can be used for X-ray and gamma-ray detectors and can be used at room temperature. It has excellent physical properties, high atomic number and density, ... -
Development of Experimental Instrumentation for Measurement of Advection in Narrow Aperture in Granite Block
(American Society of Mechanical Engineers (ASME), 2019)A granite block, acquired from a quarry Panská Dubenka located in the Czech Republic and used in presented experiments, is part of the same bedrock that can be potentially used for a deep geological repository. It is ... -
Criticality Calculations and Basic Sensitivity/Uncertainty Investigation of LR-0 Benchmark Core
(American Society of Mechanical Engineers (ASME), 2019)Three-dimensional Monte Carlo code KENO-VI of SCALE-6.2.2 code system was applied for criticality calculation of the LR-0 reactor core. A central module placed in the center of the core was filled by graphite, lithium ... -
Laminar Natural Convection Heat Transfer From Vertical 7 × 7 Rod Bundles in Liquid Sodium
(American Society of Mechanical Engineers (ASME), 2019)Laminar natural convection heat transfer from vertical 7 × 7 rod bundle in liquid sodium was numerically analyzed to optimize the thermal–hydraulic design for the bundle geometry with equilateral square array (ESA). The ... -
Study of Crack Initiation of 15-15Ti Austenitic Steel in Liquid PbBi
(American Society of Mechanical Engineers (ASME), 2019)The austenitic steel 15-15Ti is being considered as one of the candidate materials for internal structural components of future heavy liquid metal (HLM) nuclear systems. This work studies the steel compatibility with liquid ... -
Rod Bow Ultrasonic Measurements Possibilities
(American Society of Mechanical Engineers (ASME), 2019)The ultrasonic (UT) measurements have a long history of utilization in the industry, also in the nuclear field. As the UT transducers are developing with the technology in their accuracy and radiation resistance, they could ... -
Corrosion Interaction of 9%Cr Ferritic/Martensitic Steels at 450 and 550 °C With Flowing Pb–Bi Eutectic Containing 10−7 Mass % Dissolved Oxygen
(American Society of Mechanical Engineers (ASME), 2019)Corrosion behavior of 9%Cr F/M P92, E911, and EUROFER steels was investigated in flowing (2 m/s) Pb–Bi with 10−7 mass % O at 450 and 550 °C for up to 8766 and 2011 h, respectively. The steels show mixed corrosion modes ... -
Investigation of 127I(n,2n)126I and 23Na(n,2n)22Na Reactions Using 252Cf Neutron Source
(American Society of Mechanical Engineers (ASME), 2019)This work deals with 23Na(n,2n)22Na and 127I(n,2n)126I reactions in the 252Cf spontaneous fission neutron source. 252Cf neutron source with approximate emission of 6·× 108 n/s was employed for the irradiation of sodium ... -
The Necessity to Reexamine Key Component Material With Spectrometry Analysis in the Nuclear Island
(American Society of Mechanical Engineers (ASME), 2019)In order to avoid the misuse of metal material in nuclear projects, typical cases happened in advanced passive pressurized water reactor (AP1000) nuclear power projects in China are analyzed. The analysis finding indicates ... -
Pyrolysis and High Performance Plasma Treatment Applied to Spent Ion Exchange Resins
(American Society of Mechanical Engineers (ASME), 2019)Treatment and conditioning of spent ion exchange resins from nuclear facilities is a complex process that not only should contemplate obtaining a stable product suitable for long-term storage and/or disposal, but also have ... -
Nuclear Communication Campaign in Spain: Basic Nuclear Fusion Course
(American Society of Mechanical Engineers (ASME), 2019)Nuclear energy has created controversy since its conception during the 1950s. Arguments against it have been constant through the years until the current state on which the majority of western societies are against it as ... -
Subchannel Analysis of Thermal-Hydraulics in a Fuel Assembly With Inner Duct Structure of a Sodium-Cooled Fast Reactor
(American Society of Mechanical Engineers (ASME), 2019)In the design study of advanced loop-type sodium-cooled fast reactor in Japan, a specific fuel assembly (FA) called FA with inner duct structure (FAIDUS) is expected to enhance reactor safety during a core-disruptive ... -
Technical Communication During Nuclear and Radiological Emergencies With the Tools to Support International Assessment and Prognosis
(American Society of Mechanical Engineers (ASME), 2019)The International Atomic Energy Agency's (IAEA) Incident and Emergency Centre (IEC) has custom designed software tools to support assessment and prognosis of nuclear and radiological emergency scenarios, aimed at ensuring ... -
Validation of Selected Cesar Friction Models of the ASTECV21 Code Based on Moby Dick Experiments
(American Society of Mechanical Engineers (ASME), 2019)In the event of a loss of integrity of the main coolant line, a large mass and energy release from the primary circuit to the containment is to be expected. The temporal evolution of such depressurization is mainly governed ... -
Implementation of Hydrogen Solid Solubility Data and Precipitation Threshold Stresses in the Fuel Rod Code TESPA-ROD
(American Society of Mechanical Engineers (ASME), 2019)During operation of light water reactors, the Zircaloy fuel rod cladding is susceptible for hydrogen uptake. When the local solubility limit of hydrogen in Zircaloy is reached, additional hydrogen precipitates as zirconium ... -
Evaluation of the Steam Generator Clogging Phenomena Kinetics by γ-Ray Counting
(American Society of Mechanical Engineers (ASME), 2019)