Journal of Nuclear Engineering and Radiation Science: Recent submissions
Now showing items 861-880 of 913
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Erratum: “Numerical Simulation of Temperature Distribution in a Containment Vessel of an Operating PWR Plant†[Journal of Nuclear Engineering and Radiation Science, 2015, 1(1), p. 011002 4 011002 8, DOI: 10.1115/1.4026389]
(The American Society of Mechanical Engineers (ASME), 2015) -
A Review on Analysis of LWR Severe Accident
(The American Society of Mechanical Engineers (ASME), 2015)A severe accident (SA) is defined as an incident involving melting of the nuclear reactor core and the release of fission products (FP) from the fuel and their associated risks. In the SA, the containment may fail, causing ... -
Theoretical Investigations on Laser Assisted Depletion of Gd152 Isotope From Natural Gadolinium
(The American Society of Mechanical Engineers (ASME), 2015)We have proposed laserassisted depletion of Gd152 isotope from a natural isotopic mixture of Gd to enhance its functional efficiency as a burnable poison. Theoretical investigations on laserassisted depletion of Gd152 ... -
RELAP5/MOD3.3 Analyses for Prevention Strategy of Extended Station Blackout
(The American Society of Mechanical Engineers (ASME), 2015)The purpose of the study was to investigate the application of deterministic safety analysis for a prevention strategy of the extended station blackout (SBO). A method for the assessment of portable pump flow rates for a ... -
Experimental Study of the Characteristics of Heat Transfer in an HLMC Cross Flow around Tubes
(The American Society of Mechanical Engineers (ASME), 2015)The process of heat transfer in a heavy liquidmetal coolant (HLMC) crossflow around heattransfer tubes has not been thoroughly studied yet. Therefore, it is of great interest to carry out experimental studies for determining ... -
Investigation of Natural Convection Heat Transfer Phenomena in Packed Beds: Lead Way Toward New Nuclear Fuel Design
(The American Society of Mechanical Engineers (ASME), 2015)The ability of coated particles of enriched uranium dioxide fuel encased in graphite to discontinue nuclear fission reaction without human action in the case of complete loss of cooling is a vital safety measure over ... -
Numerical Analysis to Investigate the Effects of Thermal Hydraulic Instabilities on Deterioration Heat Transfer and Wall Temperature in the CANDU Supercritical Water Reactor
(The American Society of Mechanical Engineers (ASME), 2015)The present work analyzes the thermalhydraulic behavior of the CANDU supercritical water reactor (SCWR) using a 1D numerical model. The possibility of a static instability, the Ledinegg excursion, is investigated, which ... -
Thermal Predictions of the AGR 3/4 Experiment With Time Varying Gas Gaps
(The American Society of Mechanical Engineers (ASME), 2015)A thermal analysis was performed for the Advanced Gas Reactor test experiment (AGR3/4) with timevarying gas gaps. The experiment was irradiated at the Advanced Test Reactor (ATR) at the Idaho National Laboratory (INL). ... -
Thermal Hydraulics of Accelerator Driven System Using RELAP5 Code
(The American Society of Mechanical Engineers (ASME), 2015)A lead–bismuth eutectic (LBE)cooled acceleratordriven system (ADS) of 30آ MeV and 0.5آ mA proton beam has been simulated. The performance of this 15kW ADS has been analyzed for three coolants (LBE, air, and water), all ... -
Batch Scale Hydrofluorination of Li27BeF4 to Support Molten Salt Reactor Development
(The American Society of Mechanical Engineers (ASME), 2015)Li2BeF4, or flibe, is the primary candidate coolant for the fluoridesaltcooled hightemperature nuclear reactor (FHR). Kilogram quantities of pure flibe are required for repeatable corrosion tests of modern reactor materials. ... -
Influence of Sump on Containment Thermal Hydraulics: Synthesis of the TOSQAN Tests
(The American Society of Mechanical Engineers (ASME), 2015)During the course of a severe accident in a nuclear power plant, water can be collected in the sump containment through steam condensation on walls, cooling circuit leak, and by spray systems activation. Therefore, the ... -
Countercurrent Flow Limitation in Slightly Inclined Pipes With Elbows
(The American Society of Mechanical Engineers (ASME), 2015)Onedimensional (1D) sensitivity computations were carried out for air–water countercurrent flows in a 1/15scale model of the hot leg and a 1/10scale model of the pressurizer surge line in a pressurized water reactor (PWR) ... -
Validation Facility and Model Development for Nuclear Fuel Assembly Response to Seismic Loading
(The American Society of Mechanical Engineers (ASME), 2015)A joint experimental and numerical campaign is conducted to provide validation dataset of highfidelity fluid–structure interaction (FSI) models of nuclear fuel assemblies during seismic loading. A refractive indexmatched ... -
Fully Coupled Simulation of Oxygen and Heat Diffusion for (U,Pu)O2 Fuel in Both Fast Breeder Reactor and Light Water Reactor
(The American Society of Mechanical Engineers (ASME), 2015)Oxygen redistribution with a hightemperature gradient is an important fuel performance concern in fastbreeder reactor (FBR) and lightwater reactor (LWR) (U,Pu)O2 fuel under irradiation, and affects fuels properties, power ... -
Measured Biaxial Residual Stress Maps in a Stainless Steel Weld
(The American Society of Mechanical Engineers (ASME), 2015)This paper describes a sequence of residual stress measurements made to determine a twodimensional map of biaxial residual stress in a stainless steel weld. A long stainless steel (316L) plate with an eightpass groove weld ... -
Effects of the Foil Flatness on Irradiation Performance of U10Mo Monolithic Mini Plates
(The American Society of Mechanical Engineers (ASME), 2015)Monolithic platetype fuels comprise a highdensity, lowenrichment, U10Mo fuel foil encapsulated in a cladding material. This concept generates several fabrication challenges, including flatness, centering, or thickness ... -
Characterization and Optimization of a Tensioned Metastable Fluid Nuclear Particle Sensor Using Laser Based Profilometry
(The American Society of Mechanical Engineers (ASME), 2015)Stateoftheart neutron detectors lack capabilities required by the fields of homeland security, health physics, and even for direct incore nuclear power monitoring. A new system being developed at Purdue’s Metastable Fluid ... -
Quantitative and Qualitative Comparison of Light Water and Advanced Small Modular Reactors
(The American Society of Mechanical Engineers (ASME), 2015)In recent years, several small modular reactor (SMR) designs have been developed. These nuclear power plants (NPPs) not only offer a small power size (less than 300آ MWe), a reduced spatial footprint, and modularized compact ... -
Special Section: Selected Papers from the 2014 ASME IMECE in Montreal
(The American Society of Mechanical Engineers (ASME), 2015)Nuclear energy is faced with major challenges ranging from publicperception and acceptance to nonproliferation and continued operationand enhanced safety of existing fleet with lessons learned from recentFukushima Daiichi ... -
Dynamic Flowgraph Methodology Assessment of an FPGA Based Postaccident Monitoring System for Westinghouse AP1000 Nuclear Power Plants
(The American Society of Mechanical Engineers (ASME), 2015)A fieldprogrammable gate array (FPGA) is a type of integrated circuit that is programmed after being manufactured. These FPGAbased systems are considered to be viable alternatives to replace many obsolete instrumentation ...