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Articles 1 - 13 of 13

Full-Text Articles in Nuclear Engineering

Ultrasonic Testing Of A Nuclear Fuel Cladding Pipe, Modelization With A Hybrid Method And Experiments, Florian Lyonnet, Didier Cassereau, Andmarie-Françoise Cugnet Jan 2016

Ultrasonic Testing Of A Nuclear Fuel Cladding Pipe, Modelization With A Hybrid Method And Experiments, Florian Lyonnet, Didier Cassereau, Andmarie-Françoise Cugnet

Review of Progress in Quantitative Nondestructive Evaluation

Nuclear Fuel cladding pipes are long and thin tubes made of zirconium-alloy whose purpose is to confine the fissile material in a nuclear reactor. During their 3 year cycle in the reactor's core they must maintain their integrity while enduring severe stresses (heat, corrosion and irradiation). Nondestructive evaluations are performed at several stages of the manufacturing process. ASTM International provides recommendations regarding the Ultrasonic Testing (UT) of zirconium cladding pipes at the end of the production line[1]. The recommended setup is a pulse-echo immersion testing at frequency higher than 5 MHz where transverse and longitudinal calibration notches are ...


Non Destructive Evaluation Of Containment Walls In Nuclear Power Plants, V. Garnier, C. Payan, Martin Lott, Nari Ranaivamonana, Jp Balayssac, E. Larose, Yuxiang Zhang, J. Saliba, A. Boniface, Z. M. Sbartai, Bogdan Piwakowski, Charles Ciccarone, Hamid Hafid, Jean Marie Henault, Florian Ouvrier Buffet Jan 2016

Non Destructive Evaluation Of Containment Walls In Nuclear Power Plants, V. Garnier, C. Payan, Martin Lott, Nari Ranaivamonana, Jp Balayssac, E. Larose, Yuxiang Zhang, J. Saliba, A. Boniface, Z. M. Sbartai, Bogdan Piwakowski, Charles Ciccarone, Hamid Hafid, Jean Marie Henault, Florian Ouvrier Buffet

Review of Progress in Quantitative Nondestructive Evaluation

Two functions are regularly tested on the containment walls in order to anticipate a possible accident. The first is mechanical to resist at a possible internal over-pressure and the second is to prevent leakage. The reference accident LLOCA (Large Loss of Coolant Accident) is the rupture of a pipe in the primary circuit of a nuclear plant. In this case, the pressure and temperature can reach 5 bar and 180°C in 20 seconds.

The national project ‘Non-destructive testing of the containment structures of nuclear plants’ aims at studying the non-destructive techniques capable to evaluate the concrete properties and its ...


Use Of Guided Wave Inspections To Monitor The Integrity Of Nuclear Power Station Boilers, P. Jackson, P. J. Mudge, K. J. Thornicroft, A. G. Haig, R. Sanderson, E. Hutchison, C. R. A. Scheider Jan 2016

Use Of Guided Wave Inspections To Monitor The Integrity Of Nuclear Power Station Boilers, P. Jackson, P. J. Mudge, K. J. Thornicroft, A. G. Haig, R. Sanderson, E. Hutchison, C. R. A. Scheider

Review of Progress in Quantitative Nondestructive Evaluation

This paper describes a ground-breaking application of guided wave testing for the nuclear power industry. Hartlepool and Heysham 1 power stations in the UK contain boilers of a unique ‘pod’ design in which the spiral boiler tubes are supported from above by a central vertical ‘spine’, which is a tubular component approximately 520mm in diameter and 21m long with complex changes in cross-section and attachments along its length. There are 32 boilers in the two stations. The gas which has passed through the reactor core flows down over the boiler tubes, heating the water inside. Only the top 2m of ...


Capacitive Sensing For Nuclear Power Plant Cable Insulation Assessment, Nicola Bowler, Shuaishuai Liu, Michael I. Byler, Leonard S. Fifield Jan 2016

Capacitive Sensing For Nuclear Power Plant Cable Insulation Assessment, Nicola Bowler, Shuaishuai Liu, Michael I. Byler, Leonard S. Fifield

Review of Progress in Quantitative Nondestructive Evaluation

The ability to evaluate, nondestructively, the material state of insulation polymers widely employed in aged control and power cables has been identified as important In the process of routine safety inspection and safety inspection for license renewal of aging Light Water Reactor Nuclear Power Plants (NPPs) in the United States [1]. The present industry standard is that the insulation polymer breaking strain (or elongation-at-break, EAB) should be no less than 50% of that value measured on the pristine material, for the aged insulation polymer to be fit for service. Measurement of EAB is destructive, the method requires a relatively large ...


Verification And Validation Of Computational Models For Ultrasonic Testing, Gerges Dib, Michael R. Larche, Aaron A. Diaz, Susan L. Crawford, Michael T. Anderson Jan 2016

Verification And Validation Of Computational Models For Ultrasonic Testing, Gerges Dib, Michael R. Larche, Aaron A. Diaz, Susan L. Crawford, Michael T. Anderson

Review of Progress in Quantitative Nondestructive Evaluation

The Pacific Northwest National Laboratory (PNNL) is conducting confirmatory research for the U.S. Nuclear Regulatory Commission (NRC) for the verification and validation of computational models used in ultrasonic testing (UT). This paper discusses some of the findings obtained from simple geometrical reflectors in isotropic, fine-grained, homogeneous materials with conventional ultrasonic transducers. A total of 348 ultrasonic raster scans were acquired using pulse-echo conventional probes with different diameters, beam angles, wave modalities, and frequencies. The raster scans contained reflections from machined notches (flaws) of different sizes and orientations. High frequency pencil beam models, and flaw scattering models employing the Kirchhoff ...


A Hybrid Technique For Modelling The Ultrasonic Response From Surface-Breaking Defects, Richard Phillips, David Duxbury, Peter Huthwaite, Michael Lowe Jan 2016

A Hybrid Technique For Modelling The Ultrasonic Response From Surface-Breaking Defects, Richard Phillips, David Duxbury, Peter Huthwaite, Michael Lowe

Review of Progress in Quantitative Nondestructive Evaluation

Computational modelling is an efficient and cost effective alternative to experimental data collection for the design and justification of ultrasonic non-destructive inspections. Semi-analytical models are commonly used within the nuclear industry, however they place limitations on the size and geometrical complexity of the defect that can be modelled, as well as on inspection parameters such as mode and frequency. The inability to quantify the effect of increased complexity on an ultrasonic inspection regularly leads to a rise in the conservatism of the inspection sensitivity, which increases the probability of reporting innocuous defects.

The Finite Element Method (FEM) provides the capability ...


Characteristic Of Pulsed Eddy Current Signal Pattern To Detect Wall Thinning Of Carbon Steel Tube, D. G. Park, M. B. Kishore, D. H. Lee Jan 2016

Characteristic Of Pulsed Eddy Current Signal Pattern To Detect Wall Thinning Of Carbon Steel Tube, D. G. Park, M. B. Kishore, D. H. Lee

Review of Progress in Quantitative Nondestructive Evaluation

The pipelines used under high pressure and high temperatures in nuclear power plants, oil and gas, petrochemical and other energy related industries are made of ferromagnetic carbon steel. In order to increase the efficiency, the pipelines are always covered with low conductive thermal insulators to refrain from thermal emission and absorption and externally protected by cladding sheets made of aluminum alloy, stainless steel or galvanized steel. Non Destructive Technique (NDT) methods that are capable of detecting the wall thinning and defects without removing the insulation are necessary [1]. In this study we developed a Pulsed Eddy Current (PEC) system to ...


Through-Wall Phased Array Imaging Of Small Surface-Breaking Cracks, Chao Zhang, Peter Huthwaite, Michael J. S. Lowe Jan 2016

Through-Wall Phased Array Imaging Of Small Surface-Breaking Cracks, Chao Zhang, Peter Huthwaite, Michael J. S. Lowe

Review of Progress in Quantitative Nondestructive Evaluation

Accurate and reliable measurements of small surface-breaking cracks are becoming increasingly important in safety-critical components such as in nuclear power plants, because of the desire for increased operational lifetimes. With great coverage and low cost, the use of imaging to find and size surface-breaking cracks with data from ultrasonic phased arrays is becoming more attractive. For the phased array imaging, both the array configuration and the technique used to generate the images from the measurements are key factors in the image quality and sizing accuracy. Thus, the selection of a proper imaging technique is essential to ensure accurate results for ...


Testing Piezoelectric Sensors In A Nuclear Reactor Environment, Brian Reinhardt, Andy Suprock, Bernhard Tittmann Jan 2016

Testing Piezoelectric Sensors In A Nuclear Reactor Environment, Brian Reinhardt, Andy Suprock, Bernhard Tittmann

Review of Progress in Quantitative Nondestructive Evaluation

Several Department of Energy Office of Nuclear Energy (DOE-NE) programs, such as the Fuel Cycle Research and Development (FCRD), Advanced Reactor Concepts (ARC), Light Water Reactor Sustainability, and Next Generation Nuclear Power Plants (NGNP), are investigating new fuels, materials, and inspection paradigms for advanced and existing reactors. A key objective of such programs is to understand the performance of these fuels and materials during irradiation. In DOE-NE’s FCRD program, ultrasonic based technology was identified as a key approach that should be pursued to obtain the high-fidelity, high-accuracy data required to characterize the behavior and performance of new candidate fuels ...


Results Of Using Frequency Banded Saft For Examining Three Types Of Defects, Dwight Clayton, Alan Barker, Hector Santos-Villalobos Jan 2016

Results Of Using Frequency Banded Saft For Examining Three Types Of Defects, Dwight Clayton, Alan Barker, Hector Santos-Villalobos

Review of Progress in Quantitative Nondestructive Evaluation

A multitude of concrete-based structures are typically part of a light water reactor (LWR) plant to provide the foundation, support, shielding, and containment functions. Concrete has been used in the construction of nuclear power plants (NPPs) because of three primary properties; its inexpensiveness, structural strength, and ability to shield radiation. Examples of concrete structures important to the safety of LWR plants include the containment building, spent fuel pool, and cooling towers. This use has made concrete’s long-term performance crucial for the safe operation of commercial NPPs. Extending reactor life to 60 years and beyond will likely increase susceptibility and ...


Crack Detection And Localization Inweld Structure Using The Topological Energy Method, Emma Lubeigt, Serge Mensah, Jean-François Chaix, Sandrine Rakotonarivo, Gilles Gobillot, François Baqué Jan 2016

Crack Detection And Localization Inweld Structure Using The Topological Energy Method, Emma Lubeigt, Serge Mensah, Jean-François Chaix, Sandrine Rakotonarivo, Gilles Gobillot, François Baqué

Review of Progress in Quantitative Nondestructive Evaluation

Due to both significant primary loads (weight, pressure) and thermal transients, important supporting structures (bedspring, deck…) subjected to thermo-mechanical fatigues require that periodical inspections are carried out in nuclear power plant.


The bedspring and the deck are complex welded structures of very restricted access; the ability to reliably detect and locate defects like cracks is therefore a difficult challenge. Ultrasonic testing is a well-recognized non-invasive technic which exhibits high characterization performances in homogeneous media (steel). However, its capabilities are hampered when operating in heterogeneous and anisotropic austenitic welds because of deviation and splitting of the ultrasonic beam.


In order to ...


Frequency Domain Reflectometry Nde For Aging Cables In Nuclear Power Plants, S. W. Glass, A. M. Jones, L. S. Fifield, T. S. Hartman Jan 2016

Frequency Domain Reflectometry Nde For Aging Cables In Nuclear Power Plants, S. W. Glass, A. M. Jones, L. S. Fifield, T. S. Hartman

Review of Progress in Quantitative Nondestructive Evaluation

Degradation of the cable jacket, electrical insulation, and other cable components of installed cables within nuclear power plants (NPPs) is known to occur as a function of age, temperature, radiation, and other environmental factors. System tests verify cable function under normal loads; however, demonstration of some cable’s ability to perform under exceptional loads associated with design-basis events is essential to assuring plant integrity. The cable’s ability to perform safely over the initial 40-year planned and licensed life has generally been demonstrated and there have been very few age-related cable failures.With greater than 1000 km of power, control ...


Feasibility Tests Of Ranging Inspection Of Sodium-Cooled Fast Reactor Using A Plate-Type Ultrasonic Waveguide Sensor, Young-Sang Joo, Hoe-Woong Kim, Sang-Jin Park, Sung-Kyun Kim, Jong-Bum Kim, Duck-Gun Park Jan 2016

Feasibility Tests Of Ranging Inspection Of Sodium-Cooled Fast Reactor Using A Plate-Type Ultrasonic Waveguide Sensor, Young-Sang Joo, Hoe-Woong Kim, Sang-Jin Park, Sung-Kyun Kim, Jong-Bum Kim, Duck-Gun Park

Review of Progress in Quantitative Nondestructive Evaluation

In the sodium-cooled fast reactor (SFR), conventional optical visual inspections cannot be applied due to the opacity of sodium coolant. An inspection technique based on the ultrasound should be employed because the opacity of sodium prevents any conventional techniques using optical devices from being applied for under-sodium viewing of SFR [1]. Recently, the 10 m long plate-type ultrasonic waveguide sensor has been developed for the under-sodium viewing of SFR [2]. In the plate-type ultrasonic waveguide sensor, an ultrasonic transducer installs above reactor head which is in a relatively cold condition, A0 mode Lamb wave is propagated in a plate waveguide ...