Journal of Nuclear Engineering and Radiation Science: Recent submissions
Now showing items 521-540 of 913
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Special Section: Selected Papers From the 2018 International Youth Nuclear Congress
(American Society of Mechanical Engineers (ASME), 2019) -
Reviewer's Recognition
(American Society of Mechanical Engineers (ASME), 2019) -
Simulation of Nuclear Fuel Behavior in Accident Conditions With the DIONISIO Code
(American Society of Mechanical Engineers (ASME), 2019)DIONISIO is a computer code designed to simulate the behavior of one nuclear fuel rod during its permanence within the reactor. Starting from the power history and the external conditions to which the rod is subjected, the ... -
Thermomechanical Safety Analyses for a 238Pu Production Target at the HFIR
(The 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). ... -
Study on Thallium Bromide Radioactive Detector
(The 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, ... -
The Necessity to Reexamine Key Component Material With Spectrometry Analysis in the Nuclear Island
(The 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 ... -
Experimental and Numerical Analysis of Mixing Process of Two Component Gases in a Vertical Fluid Layer in a VHTR
(The 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 ... -
Subchannel Analysis of Thermal-Hydraulics in a Fuel Assembly With Inner Duct Structure of a Sodium-Cooled Fast Reactor
(The 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 ... -
Laminar Natural Convection Heat Transfer From Vertical 7 × 7 Rod Bundles in Liquid Sodium
(The 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 ... -
Micro-Calorimetric Study on the Thermal Stability of N, N-Dimethylhydroxylamine in the APOR Process
(The 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 ... -
Technical Communication During Nuclear and Radiological Emergencies With the Tools to Support International Assessment and Prognosis
(The 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 ... -
Electrical Power System Modeling of Atucha II Nuclear Power Plant Using etap
(The American Society of Mechanical Engineers (ASME), 2019)This work shows the introduction of the Electrical Power System Analysis (etap) software as a calculation and analysis tool for power electrical systems of the nuclear power plants (NPP) under the orbit of Nucleoeléctrica ... -
Evaluation of the Steam Generator Clogging Phenomena Kinetics by γ-Ray Counting
(The American Society of Mechanical Engineers (ASME), 2019) -
Sensitivity Analysis of the Thermal Diffusion Coefficient Effect on the Departure From Nucleate Boiling Ratio With the VIPRE Code
(The American Society of Mechanical Engineers (ASME), 2019)One of the limiting conditions during operation of a pressurized water reactor (PWR) is cladding integrity in class I (normal operations) or class II (most frequent). Cladding integrity is limited typically by the departure ... -
Use of Irradiated Fracture Toughness Values in Nuclear Vessel and Component Design Specifications for Fitness-For-Service Analysis Using the Unified Curve Method
(The 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 ... -
Preparation of UF4 by Carbochlorination of U3O8 and Solid-State Halogen Exchange Reaction
(The 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 ... -
Validation of Selected Cesar Friction Models of the ASTECV21 Code Based on Moby Dick Experiments
(The 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 ... -
Glasses for Nuclear Waste Immobilization. Effect of Lutetium Addition on Yttrium Aluminosilicate Glass Crystallization Kinetics
(The 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 ... -
Nuclear Communication Campaign in Spain: Basic Nuclear Fusion Course
(The 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 ... -
Preliminary Investigations of the Feasibility of In-Vessel Melt Retention Strategies for a Small Modular Reactor Concept
(The American Society of Mechanical Engineers (ASME), 2019)The study presented in this paper is part of the technological surveillance performed at the Electricité De France (EDF) Research and Development (R&D) Center, in the Pericles department, and investigates the feasibility ...