Relevant bibliographies by topics / Hydraulic system validation

Contents

  1. Journal articles
  2. Dissertations / Theses
  3. Books
  4. Book chapters
  5. Conference papers
  6. Reports

Academic literature on the topic 'Hydraulic system validation'

Author: Grafiati
Published: 24 June 2021
Last updated: 13 February 2022

Create a spot-on reference in APA, MLA, Chicago, Harvard, and other styles

Select a source type:

Consult the lists of relevant articles, books, theses, conference reports, and other scholarly sources on the topic 'Hydraulic system validation.'

Next to every source in the list of references, there is an 'Add to bibliography' button. Press on it, and we will generate automatically the bibliographic reference to the chosen work in the citation style you need: APA, MLA, Harvard, Chicago, Vancouver, etc.

You can also download the full text of the academic publication as pdf and read online its abstract whenever available in the metadata.

Journal articles on the topic "Hydraulic system validation"

1

Noh, D. K., J. S. Jang, J. H. Seo, H. S. Kim, and S. H. Park. "Development of Drifter's Hydraulic System Model and Its Validation." Journal of The Korean Society for Fluid Power & Construction Equipments 11, no. 3 (September 1, 2014): 14–21. http://dx.doi.org/10.7839/ksfc.2014.11.3.014.

Full text
APA, Harvard, Vancouver, ISO, and other styles
2

HATTORI, Tomoya, Noboru KAWAGUCHI, Yutaka EZAKI, Junji TAKAKI, Masao SAITO, Masahiro SUGIMOTO, Satoshi SATOH, and Katsuhiko YAMADA. "Experimental validation of hydraulic support system for large structures." Transactions of the JSME (in Japanese) 87, no. 900 (2021): 21–00060. http://dx.doi.org/10.1299/transjsme.21-00060.

Full text
APA, Harvard, Vancouver, ISO, and other styles
3

Ketelsen, Søren, Sebastian Michel, Torben O. Andersen, Morten Kjeld Ebbesen, Jürgen Weber, and Lasse Schmidt. "Thermo-Hydraulic Modelling and Experimental Validation of an Electro-Hydraulic Compact Drive." Energies 14, no. 9 (April 22, 2021): 2375. http://dx.doi.org/10.3390/en14092375.

Full text
Abstract:
Electro-hydraulic compact drives (ECDs) are an emerging technology for linear actuation in a wide range of applications. Especially within the low power range of 5–10 kW, the plug-and-play capability, good energy efficiency and small space requirements of ECDs render this technology a promising alternative to replace conventional valve-controlled linear drive solutions. In this power range, ECDs generally rely on passive cooling to keep oil and system temperatures within the tolerated range. When expanding the application range to larger power classes, passive cooling may not be sufficient. Research investigating the thermal behaviour of ECDs is limited but indeed required for a successful expansion of the application range. In order to obtain valuable insights into the thermal behaviour of ECDs, thermo-hydraulic simulation is an important tool. This may enable system design engineers to simulate thermal behaviour and thus develop proper thermal designs during the early design phase, especially if such models contain few parameters that can be determined with limited information available. Our paper presents a lumped thermo-hydraulic model derived from the conservation of mass and energy. The derived model was experimentally validated based on experimental data from an ECD prototype. Results show good accuracy between measured and simulated temperatures. Even a simple thermal model containing only a few thermal resistances may be sufficient to predict steady-state and transient temperatures with reasonable accuracy. The presented model may be used for further investigations into the thermal behaviour of ECDs and thus toward proper thermal designs required to expand the application range.
APA, Harvard, Vancouver, ISO, and other styles
4

Osusky, Filip, Stefan Cerba, Jakub Luley, Branislav Vrban, and Jan Hascik. "COUPLED SIMULATION OF GAS COOLED FAST REACTOR FUEL ASSEMBLY WITH NESTLE CODE SYSTEM." Acta Polytechnica CTU Proceedings 14 (May 17, 2018): 34. http://dx.doi.org/10.14311/app.2018.14.0034.

Full text
Abstract:
The paper is focused on coupled calculation of the Gas Cooled Fast Reactor. The proper modelling of coupled neutronics and thermal-hydraulics is the corner stone for future safety assessment of the control and emergency systems. Nowadays, the system and channel thermal-hydraulic codes are accepted by the national regulatory authorities in European Union for license purposes, therefore the code NESTLE was used for the simulation. The NESTLE code is a coupled multigroup neutron diffusion code with thermal-hydraulic sub-channel code. In the paper, the validation of NESTLE code 5.2.1 installation is presented. The processing of fuel assembly homogeneous parametric cross-section library for NESTLE code simulation is made by the sequence TRITON of SCALE code package system. The simulated case in the NESTLE code is one fuel assembly of GFR2400 concept with reflective boundary condition in radial direction and zero flux boundary condition in axial direction. The results of coupled calculation are presented and are consistent with the GFR2400 study of the GoFastR project.
APA, Harvard, Vancouver, ISO, and other styles
5

Wiens, Travis, and Brendan Deibert. "A Low-Cost Miniature Electrohydrostatic Actuator System." Actuators 9, no. 4 (December 4, 2020): 130. http://dx.doi.org/10.3390/act9040130.

Full text
Abstract:
Hydraulic linear actuators dominate in high power applications but are much less common in low power (<100 W) systems. One reason for this is the cost: electric actuators in this power range generally exhibit lower performance but are also much less expensive than hydraulic systems. However, in recent years, some miniature hydraulic components have been mass produced, driving down prices. This paper presents the application of these low-cost components, together with a novel very low-cost 3D-printed valve to create an electrohydrostatic actuator. Capable of very high power and force density, this system is competitive on cost with lower-performing electric actuators. This paper presents models for the system’s performance, as well as experimental validation data.
APA, Harvard, Vancouver, ISO, and other styles
6

Xu, Ming, and Hui Yuan Li. "Research on Constant Torque Control System Design for Hydraulic Retarder of Heavy Vehicle." Advanced Materials Research 538-541 (June 2012): 2493–99. http://dx.doi.org/10.4028/www.scientific.net/amr.538-541.2493.

Full text
Abstract:
The analysis of inner circulation circle flow characteristic of the partly filled hydraulic retarder during its braking course is carried out. a relation between the liquid filled ratio of the circulation circle in hydraulic retarder， the inner flow field pressure characteristic and the output torque characteristic of it is established, The control parameter token for the hydraulic retarder torque characteristic is acquired, then the Constant Torque Control System for Heavy Vehicle Hydraulic Retarder is formed. Through a test bed experiment of Constant Torque Control System for Heavy Vehicle Hydraulic Retarder, the validation of the Constant Torque Control System for Heavy Vehicle Hydraulic Retarder is verified，the whole system perfectly meet the design request.
APA, Harvard, Vancouver, ISO, and other styles
7

Wolfert, K., and I. Brittain. "CSNI validation matrix for PWR and BWR thermal-hydraulic system codes." Nuclear Engineering and Design 108, no. 1-2 (June 1988): 107–19. http://dx.doi.org/10.1016/0029-5493(88)90060-x.

Full text
APA, Harvard, Vancouver, ISO, and other styles
8

Takalo, Ville, Salvador Esque, Jouni Mattila, Matti Vilenius, Jorma Järvenpää, Mikko Siuko, Luigi Semeraro, Mike Irving, and Carlo Damiani. "Validation of Divertor Cassette locking system with a hydraulic jack tool." Fusion Engineering and Design 84, no. 7-11 (June 2009): 1808–12. http://dx.doi.org/10.1016/j.fusengdes.2008.11.039.

Full text
APA, Harvard, Vancouver, ISO, and other styles
9

Van Blaricum, Vicki L., and Vincent F. Hock. "Water Distribution System Modeling and Remote Monitoring." Advanced Materials Research 38 (March 2008): 132–42. http://dx.doi.org/10.4028/www.scientific.net/amr.38.132.

Full text
Abstract:
Localized internal corrosion of water distribution piping is difficult to detect, diagnose, and mitigate. This paper describes the demonstration and validation of multi-parameter water quality sensors and corrosion rate sensors that were permanently installed at a U. S. Army installation to detect corrosion problems and fine-tune the chemical treatment program. This paper will include results of the sensor demonstration and validation. Follow-on work includes the integration of the sensors with a dynamic real-time water distribution system chemical and hydraulic simulation. This work will also be described.
APA, Harvard, Vancouver, ISO, and other styles
10

Du, Heng, Qingming Zhang, Shumei Chen, and Jinhui Fang. "Modeling, simulation, and experimental validation of electro-hydraulic power steering system in multi-axle vehicles." Proceedings of the Institution of Mechanical Engineers, Part D: Journal of Automobile Engineering 233, no. 2 (December 19, 2017): 317–32. http://dx.doi.org/10.1177/0954407017743346.

Full text
Abstract:
An accurate electro-hydraulic power steering system (EHPSS) model is essential to analyze dynamic steering performance and advanced nonlinear control. The main obstacle to establish an accurate model is the complex structure, including steering mechanism, valve controlled dual hydraulic-actuator, and heavy duty tires. This paper constructs a suitable model incorporating these parts, based on a Lagrange equation describing the steering trapezoid mechanism and dual cylinder hydraulic dynamics, regarding steering resisting moment as an external load. A simplified tire model is used to represent the tire basic steering load characteristics. Due to the complexity of the kinematic relationship in the model, several expressions are fitted using back propagation neural networks to significantly reduce calculation difficulty. Experimental measurements and simulation using Matlab/Simulink and experiment are realized for the case of in situ steering, and the results validate the proposed model accuracy. Thus, the proposed model is suitable to analyze the system and design advanced controllers.
APA, Harvard, Vancouver, ISO, and other styles
More sources

Dissertations / Theses on the topic "Hydraulic system validation"

1

Berglund, David, and Niklas Larsson. "Controlling a Hydraulic System using Reinforcement Learning : Implementation and validation of a DQN-agent on a hydraulic Multi-Chamber cylinder system." Thesis, Linköpings universitet, Fluida och mekatroniska system, 2021. http://urn.kb.se/resolve?urn=urn:nbn:se:liu:diva-177216.

Full text
Abstract:
One of the largest energy losses in an excavator is the compensation loss. In a hydraulic load sensing system where one pump supplies multiple actuators, these compensation losses are inevitable. To minimize the compensation losses the use of a multi chamber cylinder can be used, which can control the load pressure by activate its chambers in different combinations and in turn minimize the compensation losses.  For this proposed architecture, the control of the multi chamber cylinder systems is not trivial. The possible states of the system, due to the number of combinations, makes conventional control, like a rule based strategy, unfeasible. Therefore, is the reinforcement learning a promising approach to find an optimal control.  A hydraulic system was modeled and validated against a physical one, as a base for the reinforcement learning to learn in simulation environment. A satisfactory model was achieved, accurately modeled the static behavior of the system but lacks some dynamics.  A Deep Q-Network agent was used which successfully managed to select optimal combinations for given loads when implemented in the physical test rig, even though the simulation model was not perfect.
APA, Harvard, Vancouver, ISO, and other styles
2

KOWTA, SRINIVAS. "ROBUST STABILITY ANALYSIS OF SERVO-HYDRAULIC SYSTEM IN PARAMETER SPACE." University of Cincinnati / OhioLINK, 2003. http://rave.ohiolink.edu/etdc/view?acc_num=ucin1060970575.

Full text
APA, Harvard, Vancouver, ISO, and other styles
3

Hartig, Jakob, Christian Schänzle, and Peter F. Pelz. "Validation of a soft sensor network for condition monitoring in hydraulic systems." Technische Universität Dresden, 2020. https://tud.qucosa.de/id/qucosa%3A71201.

Full text
Abstract:
With increasing digitization, models are more important than ever. Especially their use as soft sensors during operation offers opportunities in cost saving, easy data acquisition and therefore additional functionality of systems. In soft sensor networks there is redundant data acquisition and consequently the occurrence of inconsistent values from different soft sensors is encouraged. The resolution of these data-induced conflicts allows for the detection of changing components characteristics. Hence soft sensor networks can be used to detect wear in system components. In this paper this approach is validated on a test rig. It is found, that the soft sensor network is capable to determine wear and its extent in eccentric screw pumps and valves via data induced conflicts with relatively simple models.
APA, Harvard, Vancouver, ISO, and other styles
4

Jeltsov, Marti. "Application of CFD to Safety and Thermal-Hydraulic Analysis of Lead-Cooled Systems." Thesis, KTH, Fysik, 2011. http://urn.kb.se/resolve?urn=urn:nbn:se:kth:diva-37806.

Full text
Abstract:
Computational Fluid Dynamics (CFD) is increasingly being used in nuclear reactor safety analysis as a tool that enables safety related physical phenomena occurring in the reactor coolant system to be described in more detail and accuracy. Validation is a necessary step in improving predictive capability of a computationa code or coupled computational codes. Validation refers to the assessment of model accuracy incorporating any uncertainties (aleatory and epistemic) that may be of importance. The uncertainties must be identi ed, quanti ed and if possible, reduced. In the rst part of this thesis, a discussion on the development of an approach and experimental facility for the validation of coupled Computational Fluid Dynamics codes and System Thermal Hydraulics (STH) codes is given. The validation of a coupled code requires experiments which feature signi cant two-way feedbacks between the component (CFD sub-domain) and the system (STH sub-domain). Results of CFD analysis that are used in the development of a exible design of the TALL-3D experimental facility are presented. The facility consists of a lead-bismuth eutectic (LBE) thermal-hydraulic loop operating in forced and natural circulation regimes with a heated pool-type 3D test section. Transient analysis of the mixing and strati cation phenomena in the 3D test section under forced and natural circulation conditions in the loop show that the test section outlet temperature deviates from that predicted by analytical solution (which the 1D STH solution essentially is). Also an experimental validation test matrix according to the key physical phenomena of interest in the new experimental facility is developed. In the second part of the thesis we consider the risk related to steam generator tube leakage or rupture (SGTL/R) in a pool-type design of lead-cooled reactor (LFR). We demonstrate that there is a possibility that small steam bubbles leaking from the SGT will be dragged by the turbulent coolant ow into the core region. Voiding of the core might cause threats of reactivity insertion accident or local damage (burnout) of fuel rod cladding. Trajectories of the bubbles are determined by the bubble size and turbulent ow eld of lead coolant. The main objective of such study is to quantify likelihood of steam bubble transport to the core region in case of SGT leakage in the primary coolant system of the ELSY (European Lead-cooled SYstem) design. Coolant ow eld and bubble motion are simulated by CFD code Star-CCM+. First, we discuss drag correlations for a steam bubble moving in liquid lead. Thereafter the steady state liquid lead ow eld in the primary system is modeled according to the ELSY design parameters of nominal full power operation. Finally, the consequences of SGT leakage are modeled by injecting bubbles in the steam generator region. An assessment of the probability that bubbles can reach the core region and also accumulate in the primary system, is performed. The most dangerous leakage positions in the SG and bubble sizes are identi ed. Possible design solutions for prevention of core voiding in case of SGTL/R are discussed.
APA, Harvard, Vancouver, ISO, and other styles
5

Jäger, Wadim. "Validation and Application of the System Code TRACE for Safety Related Investigations of Innovative Nuclear Energy Systems." Doctoral thesis, Saechsische Landesbibliothek- Staats- und Universitaetsbibliothek Dresden, 2012. http://nbn-resolving.de/urn:nbn:de:bsz:14-qucosa-93747.

Full text
Abstract:
The system code TRACE is the latest development of the U.S. Nuclear Regulatory Commission (US NRC). TRACE, developed for the analysis of operational conditions, transients and accidents of light water reactors (LWR), is a best-estimate code with two fluid, six equation models for mass, energy, and momentum conservation, and related closure models. Since TRACE is mainly applied to LWR specific issues, the validation process related to innovative nuclear systems (liquid metal cooled systems, systems operated with supercritical water, etc.) is very limited, almost not existing. In this work, essential contribution to the validation of TRACE related to lead and lead alloy cooled systems as well as systems operated with supercritical water is provided in a consistent and corporate way. In a first step, model discrepancies of the TRACE source code were removed. This inconsistencies caused the wrong prediction of the thermo physical properties of supercritical water and lead bismuth eutectic, and hence the incorrect prediction of heat transfer relevant characteristic numbers like Reynolds or Prandtl number. In addition to the correction of the models to predict these quantities, models describing the thermo physical properties of lead and Diphyl THT (synthetic heat transfer medium) were implemented. Several experiments and numerical benchmarks were used to validate the modified TRACE version. These experiments, mainly focused on wall-to-fluid heat transfer, revealed that not only the thermo physical properties are afflicted with inconsistencies but also the heat transfer models. The models for the heat transfer to liquid metals were enhanced in a way that the code can now distinguish between pipe and bundle flow by using the right correlation. The heat transfer to supercritical water was not existing in TRACE up to now. Completely new routines were implemented to overcome that issue. The comparison of the calculations to the experiments showed, on one hand, the necessity of these changes and, on the other hand, the success of the new implemented routines and functions. The predictions using the modified TRACE version were close to the experimental data. After validating the modified TRACE version, two design studies related to the Generation IV International Forum (GIF) were investigated. In the first one, a core of a lead-cooled fast reactor (LFR) was analyzed. To include the interaction between the thermal hydraulic and the neutron kinetic due to temperature and density changes, the TRACE code was coupled to the program system ERANOS2.1. The results gained with that coupled system are in accordance with theory and helped to identify sub-assemblies with the highest loads concerning fuel and cladding temperature. The second design which was investigated was the High Performance Light Water Reactor (HPLWR). Since the design of the HPLWR is not finalized, optimization of vital parameters (power, mass flow rate, etc.) are still ongoing. Since most of the parameters are affecting each other, an uncertainty and sensitivity analysis was performed. The uncertainty analysis showed the upper and lower boundaries of selected parameters, which are of importance from the safety point of view (e.g., fuel and cladding temperature, moderator temperature). The sensitivity study identified the most relevant parameters and their influence on the whole system.
APA, Harvard, Vancouver, ISO, and other styles
6

Earnhart, Nicholas Edmond. "Modeling and validation of a syntactic foam lining for noise control devices for fluid power systems." Diss., Georgia Institute of Technology, 2012. http://hdl.handle.net/1853/50151.

Full text
Abstract:
Excessive fluid-borne noise in hydraulic systems is a problem the fluid power industry has long struggled to address. Traditional noise control devices such as Helmholtz resonators, tuning coils, and Herschel-Quincke tubes are generally too large for fluid power systems unless the speed of sound in the device can be reduced. A compliant lining can achieve this effect, but compliance (and lossy compliance) has had little attention in noise control in general, and in fluid power in particular. One means to achieve compliance in these devices, especially at elevated pressures, is through a liner made of syntactic foam, which in this case is a urethane host matrix with embedded hollow, polymer microspheres. The material properties at elevated pressure are unknown by the liner manufacturer, but are known to be pressure- and temperature-dependent. Therefore, the effect of hydrostatic pressures from 2.1-21 MPa and temperatures from 20-45 C on the liner properties, thus the device performance, are studied. For a Helmholtz resonator, a theoretical model is fit to experimentally-measured transmission loss of the device using a least-squares routine, which solves the inverse problem for the complex bulk modulus of the liner. These material properties are used to compare a predictive model of a tuning coil to experimental data, and in a parameter study of a Herschel-Quincke tube. The compliance of the liner is found to lower the effective sound speed by an order of magnitude and decrease the volume of the cavity of a Helmholtz resonator by up to two orders of magnitude. This work is expected to result is more compact noise control devices for fluid power systems.
APA, Harvard, Vancouver, ISO, and other styles
7

Saulich, Sven. "Generic design and investigation of solar cooling systems." Thesis, Loughborough University, 2013. https://dspace.lboro.ac.uk/2134/13627.

Full text
Abstract:
This thesis presents work on a holistic approach for improving the overall design of solar cooling systems driven by solar thermal collectors. Newly developed methods for thermodynamic optimization of hydraulics and control were used to redesign an existing pilot plant. Measurements taken from the newly developed system show an 81% increase of the Solar Cooling Efficiency (SCEth) factor compared to the original pilot system. In addition to the improvements in system design, new efficiency factors for benchmarking solar cooling systems are presented. The Solar Supply Efficiency (SSEth) factor provides a means of quantifying the quality of solar thermal charging systems relative to the usable heat to drive the sorption process. The product of the SSEth with the already established COPth of the chiller, leads to the SCEth factor which, for the first time, provides a clear and concise benchmarking method for the overall design of solar cooling systems. Furthermore, the definition of a coefficient of performance, including irreversibilities from energy conversion (COPcon), enables a direct comparison of compression and sorption chiller technology. This new performance metric is applicable to all low-temperature heat-supply machines for direct comparison of different types or technologies. The achieved findings of this work led to an optimized generic design for solar cooling systems, which was successfully transferred to the market.
APA, Harvard, Vancouver, ISO, and other styles
8

Jäger, Wadim. "Validation and Application of the System Code TRACE for Safety Related Investigations of Innovative Nuclear Energy Systems." Doctoral thesis, 2011. https://tud.qucosa.de/id/qucosa%3A26116.

Full text
Abstract:
The system code TRACE is the latest development of the U.S. Nuclear Regulatory Commission (US NRC). TRACE, developed for the analysis of operational conditions, transients and accidents of light water reactors (LWR), is a best-estimate code with two fluid, six equation models for mass, energy, and momentum conservation, and related closure models. Since TRACE is mainly applied to LWR specific issues, the validation process related to innovative nuclear systems (liquid metal cooled systems, systems operated with supercritical water, etc.) is very limited, almost not existing. In this work, essential contribution to the validation of TRACE related to lead and lead alloy cooled systems as well as systems operated with supercritical water is provided in a consistent and corporate way. In a first step, model discrepancies of the TRACE source code were removed. This inconsistencies caused the wrong prediction of the thermo physical properties of supercritical water and lead bismuth eutectic, and hence the incorrect prediction of heat transfer relevant characteristic numbers like Reynolds or Prandtl number. In addition to the correction of the models to predict these quantities, models describing the thermo physical properties of lead and Diphyl THT (synthetic heat transfer medium) were implemented. Several experiments and numerical benchmarks were used to validate the modified TRACE version. These experiments, mainly focused on wall-to-fluid heat transfer, revealed that not only the thermo physical properties are afflicted with inconsistencies but also the heat transfer models. The models for the heat transfer to liquid metals were enhanced in a way that the code can now distinguish between pipe and bundle flow by using the right correlation. The heat transfer to supercritical water was not existing in TRACE up to now. Completely new routines were implemented to overcome that issue. The comparison of the calculations to the experiments showed, on one hand, the necessity of these changes and, on the other hand, the success of the new implemented routines and functions. The predictions using the modified TRACE version were close to the experimental data. After validating the modified TRACE version, two design studies related to the Generation IV International Forum (GIF) were investigated. In the first one, a core of a lead-cooled fast reactor (LFR) was analyzed. To include the interaction between the thermal hydraulic and the neutron kinetic due to temperature and density changes, the TRACE code was coupled to the program system ERANOS2.1. The results gained with that coupled system are in accordance with theory and helped to identify sub-assemblies with the highest loads concerning fuel and cladding temperature. The second design which was investigated was the High Performance Light Water Reactor (HPLWR). Since the design of the HPLWR is not finalized, optimization of vital parameters (power, mass flow rate, etc.) are still ongoing. Since most of the parameters are affecting each other, an uncertainty and sensitivity analysis was performed. The uncertainty analysis showed the upper and lower boundaries of selected parameters, which are of importance from the safety point of view (e.g., fuel and cladding temperature, moderator temperature). The sensitivity study identified the most relevant parameters and their influence on the whole system.
APA, Harvard, Vancouver, ISO, and other styles
9

"Investigation of Acceleration Dependent Nonlinear Lubricated Friction in Hydraulic Actuation Systems." Thesis, 2016. http://hdl.handle.net/10388/ETD-2016-01-2395.

Full text
Abstract:
Lubricated friction issues are central to all hydraulic actuation systems undergoing motion and any in-depth understanding of the nature of lubricated friction will advance future component design. The classic friction models of hydraulic actuation systems under steady state conditions and their dependency on velocity and temperature have been studied extensively over the past years. A model which is commonly employed to represent the characteristics of friction is that of Stribeck in which the dependency of the friction force is based on velocity alone. However, experimentally, it has been found that lubricated friction is dependent on acceleration. Thus, the Stribeck model can be considered as a subset of a dynamic friction model in which acceleration is zero. Thus, it can be concluded that the Stribeck model is best applied to cases when the change rate of the velocities is very small. This thesis considers the dependency of lubricated friction on acceleration when pressure and temperature changes are relatively constant. As such, the basic hypothesis for this study was proposed as follows: “Lubricated friction in hydraulic actuation systems is not only a function of velocity, but is also a function of both velocity and acceleration”. In this thesis several terms are defined which facilitate the description under which friction models are developed. For example, the term non-steady state friction is used to account for the effect of acceleration on lubricated friction force while in motion. Further, the lubricated friction models are divided into two groups: steady state friction models and non-steady state friction models. Nonlinear friction modeling and measuring methods are reviewed in this dissertation. This review also includes nonlinear lubricated friction modeling in hydraulic actuation systems. A conclusion from this review was that limited research has been done in documenting and explicitly demonstrating the role of acceleration on lubricated friction. The research first introduced a methodology to experimentally measure friction as a function of acceleration and to demonstrate this dependency in the form of a three dimensional graph. A novel technique to experimentally obtain data for the lubricated friction model was introduced. This allowed the lubricated friction forces to be measured as a function of velocity in a continuous manner, but with acceleration being held constant as a family parameter. Two different valve controlled hydraulic actuation systems (VCHAS) were studied under a wide variety of accelerations at constant temperature and pressure. To enable repeatable data collection for the different friction conditions and to accommodate for the effect of hysteresis, a periodic parabolic displacement waveform was chosen which enabled the acceleration to be a family parameter. The second phase of the research introduced a method of representing the data (lubricated friction model) in a lookup table form. The relationship of lubricated friction (in this work, pressure differential, ΔP across the actuator) as a function of velocity and acceleration was presented in a unique semi-empirical 2D lookup table (2D LUT). Limitations of this experimental approach were identified, but the dependency on acceleration was clearly established. The last phase of the study implemented this 2D LUT model into a practical software model of an actuator and demonstrated its accuracy when compared to its experimental counterpart. The semi-empirical model (2D LUT) was experimentally verified by implementing the semi-empirical and Stribeck models into a real time simulation of an actuator and by comparing the experimental outputs against simulated outputs for a common sinusoidal input. A sinusoidal actuator displacement input was chosen to test the simulations as it was not used in the collection of the original data. The output of the simulation was compared to the experimental results and it was evident that for the range in which data could be collected in developing the model, the proposed 2D LUT model predicted an output that was superior to a model which used a standard Stribeck model. It was concluded that the semi-empirical model could be integrated into a simulation environment and predict outputs in a superior fashion when compared to the Stribeck friction model. Thus it was concluded that the stated hypothesis is consistent with the experimental evidence shown by all hydraulic actuators considered. Further, it was also observed that the traditional Stribeck form (steady state dynamic friction) does change with increasing acceleration to the point that the standard breakaway friction almost disappears. It is evident that the 2D LUT is a viable tool for modeling the non-steady state friction of hydraulic actuation systems. The semi-empirical 2D LUT model so developed is a more global representation of hydraulic actuator lubricated friction. In this research, only linear hydraulic actuators were considered; however, the novel nonlinear semi-empirical 2D LUT lubricated friction model can be applied to any actuator (linear and rotary) and provides a new way in which the dynamic friction can be viewed and modeled.
APA, Harvard, Vancouver, ISO, and other styles

Books on the topic "Hydraulic system validation"

1

Vyas, J. Jaidev, Balamurugan Gopalsamy, and Harshavardhan Joshi. Electro-Hydraulic Actuation Systems: Design, Testing, Identification and Validation. Springer, 2018.

Find full text
APA, Harvard, Vancouver, ISO, and other styles

Book chapters on the topic "Hydraulic system validation"

1

Romli, M., J. Keller, P. L. Lee, and P. F. Greenfield. "The Effect of Concentration and Hydraulic Shock Loads on the Performance of a Two-Stage High-Rate Anaerobic Wastewater Treatment System: Prediction and Validation." In Advances in Bioprocess Engineering, 379–84. Dordrecht: Springer Netherlands, 1994. http://dx.doi.org/10.1007/978-94-017-0641-4_50.

Full text
APA, Harvard, Vancouver, ISO, and other styles
2

Boström, Pontus, Mikko Heikkilä, Mikko Huova, Marina Waldén, and Matti Linjama. "Verification and Validation of a Pressure Control Unit for Hydraulic Systems." In Lecture Notes in Computer Science, 101–15. Cham: Springer International Publishing, 2014. http://dx.doi.org/10.1007/978-3-319-12241-0_8.

Full text
APA, Harvard, Vancouver, ISO, and other styles
3

Glaeser, H. "Verification and validation of system thermal-hydraulic computer codes, scaling and uncertainty evaluation of calculated code results." In Thermal-Hydraulics of Water Cooled Nuclear Reactors, 831–903. Elsevier, 2017. http://dx.doi.org/10.1016/b978-0-08-100662-7.00013-0.

Full text
APA, Harvard, Vancouver, ISO, and other styles
4

Zang, Jinguang, Xiao Yan, and Yanping Huang. "The Basic Thermal Hydraulic Issues of Applying Supercritical Fluid to Nuclear Reactors." In Handbook of Research on Advancements in Supercritical Fluids Applications for Sustainable Energy Systems, 682–716. IGI Global, 2021. http://dx.doi.org/10.4018/978-1-7998-5796-9.ch019.

Full text
Abstract:
This chapter is mainly focused on illustrating some introductory progress on thermal hydraulic issues of supercritical water, including heat transfer characteristics, pressure loss characteristics, flow stability issues, and numerical method. These works are mainly to give a basic idea of elementary but important topics in this area. An analytical method was proposed up to predict the heat transfer coefficient and friction coefficient based on the two-layer wall function. Flow instability experiments have been carried out in a two-parallel-channel system with supercritical water, aiming to provide an up-to-date knowledge of supercritical flow instability phenomena and initial validation data for numerical analysis. The natural circulation instability of supercritical water was also investigated in the experiments.
APA, Harvard, Vancouver, ISO, and other styles
5

Yan, Xiao, Jinguang Zang, Ting Xiong, Xi Sui, Yanping Huang, and Zejun Xiao. "The Basic Thermal Hydraulic Issues of Applying Supercritical Fluid to Nuclear Reactors." In Advanced Applications of Supercritical Fluids in Energy Systems, 481–553. IGI Global, 2017. http://dx.doi.org/10.4018/978-1-5225-2047-4.ch015.

Full text
Abstract:
This chapter is mainly focused on illustrating some introductory progress on thermal hydraulic issues of supercritical water, including heat transfer characteristics, pressure loss characteristics, flow stability issues and numerical method. These works are mainly performed in Nuclear Power Institute of China (NPIC) these years, to give a basic idea of elementary but important topics in this area. An analytical method was proposed up to predict the heat transfer coefficient and friction coefficient based on the two-layer wall function. Flow instability experiments have been carried out in a two-parallel-channel system with supercritical water, aiming to provide an up-to-date knowledge of supercritical flow instability phenomena and initial validation data for numerical analysis. An in-house code has been developed in NPIC in order to better utilize and further expand the experimental results on supercritical flow instability. At last, some future research directions are suggested for reference.
APA, Harvard, Vancouver, ISO, and other styles

Conference papers on the topic "Hydraulic system validation"

1

Shimizu, J., T. Otani, H. Mizukami, K. Hashimoto, and A. Takanishi. "Experimental Validation of Hydraulic Interlocking Drive System for Biped Humanoid Robot." In 2019 IEEE/RSJ International Conference on Intelligent Robots and Systems (IROS). IEEE, 2019. http://dx.doi.org/10.1109/iros40897.2019.8968253.

Full text
APA, Harvard, Vancouver, ISO, and other styles
2

Niedzwiedzka, A., S. Lipinski, and W. Sobieski. "Validation of numerical simulations of cavitating flow in hydraulic system using an optoelectronic system." In THMT-15. Proceedings of the Eighth International Symposium On Turbulence Heat and Mass Transfer. Connecticut: Begellhouse, 2015. http://dx.doi.org/10.1615/ichmt.2015.thmt-15.350.

Full text
APA, Harvard, Vancouver, ISO, and other styles
3

Chung, Young-Jong, Won Jae Lee, and Jaejoo Ha. "Experimental Validation for Specific Thermal Hydraulic Phenomena of SMART." In 2013 21st International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2013. http://dx.doi.org/10.1115/icone21-15172.

Full text
Abstract:
SMART (System-integrated Modular Advanced ReacTor) is an integral light water reactor developed by KAERI for both electricity generation and various applications. SMART can produce 90MWe of electricity and 40,000 tons/day of sea-water desalination, which is deemed suitable for a city population of 100,000. The SMART project aims at standard design approval. The experimental validation for SMART specific thermal hydraulic phenomena is to generate background information required for SMART licensing. The objective of the experimental validation is to demonstrate the safety and performance of the SMART-specific system and component designs, and to provide a database for the validation of the design tools, such as a system analysis code. From the experimental results, it is proved that SMART was designed properly and the data are used to approve the validation of the system analysis code. Also, the experimental results were submitted to a regulatory body as technical background information of the SMART standard design, and they enhance the licensing possibility of this design.
APA, Harvard, Vancouver, ISO, and other styles
4

Raqué, Manuel, Heiko Herbell, and Thomas Schulenberg. "Validation of the System Code APROS for Fast Transients." In 2013 21st International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2013. http://dx.doi.org/10.1115/icone21-16746.

Full text
Abstract:
The thermal-hydraulic system code APROS Version 5.09 [1] is being applied in the European project SCWR-FQT to evaluate the performance of the safety systems for a nuclear test facility operated with supercritical water. In order to validate the commercial code for predictions of transient phenomena, two adequate hydraulic experiments from literature have been simulated. The experiment of Fujii and Akagawa [2] investigated hydraulic shocks as they will occur in case a pipe, which is stationary passed through by water, is abruptly closed. A simple numerical model with adapted time and space nodalization was able to reproduce the observed physical phenomena, such as the magnitude of the initial pressure wave and reflection time, in detail. In a second experiment, a test series was performed by Becker et al. [3] and Mathisen [4] in order to examine the natural circulation in a closed loop for different heating rates and system pressures. For a stepwise power increase, the typical mass flow characteristic for boiling channels was recorded until the onset of flow oscillations. In further runs, the effect of different initial conditions on the flow stability was analyzed. This paper compares the numerical predictions with both experimental results. The numerical models could describe the physical phenomena with appropriate accuracy.
APA, Harvard, Vancouver, ISO, and other styles
5

Thomas, A. Tony, S. K. Thangarasu, and T. Sowmithra. "Simulation and experimental validation of electro hydraulic servo system using fuzzy logic controller." In INTERNATIONAL CONFERENCE ON COMPUTATIONAL SCIENCES-MODELLING, COMPUTING AND SOFT COMPUTING (CSMCS 2020). AIP Publishing, 2021. http://dx.doi.org/10.1063/5.0045724.

Full text
APA, Harvard, Vancouver, ISO, and other styles
6

Righettini, Paolo, Roberto Strada, Shirin Valilou, and Ehsan Khademolama. "Nonlinear Modeling and Experimental Validation of Uni-Axial Servo-Hydraulic Shaking Table." In BATH/ASME 2016 Symposium on Fluid Power and Motion Control. American Society of Mechanical Engineers, 2016. http://dx.doi.org/10.1115/fpmc2016-1773.

Full text
Abstract:
An effective way for the testing of a large number of systems is using single and multi-axis shaking tables. Among the possible applications, the civil engineering field stands out for the testing of structures, or part of them, both on a reduced and on a full scale. However, design a high performance controller for a servo-hydraulic shaking table is a difficult problem due to its non-linarites and large friction forces. The goal of this paper is to develop and experimentally validate a robust numerical model that simulates the acceleration behavior of a uni-axial servo-hydraulic shaking table system with considering three friction models, the LuGre model, the modified LuGre model and the new modified LuGre model. First, a full system model of servo-hydraulic system is developed based on fluid mechanical expressions and then the friction force of hydraulic cylinder is modeled and validated on the real shaking table. Data of the experiment are gathered from input command valve, and the output acceleration and position of the table. All models are simulated by using MATLAB and SIMULINK computer program. The parameters of the system and the friction models are estimated by using least square method (LSM). Finally, the comparisons of simulated results with experimental ones show that the model of the system with considering third model of the friction can predict accurately the shaking table’s behaviors.
APA, Harvard, Vancouver, ISO, and other styles
7

Pulido, Ramon J. M., Eric R. Lindgren, Samuel G. Durbin, and Alex Salazar. "Thermal-Hydraulic Investigations of a Horizontal Dry Cask Simulator." In 2020 International Conference on Nuclear Engineering collocated with the ASME 2020 Power Conference. American Society of Mechanical Engineers, 2020. http://dx.doi.org/10.1115/icone2020-16598.

Full text
Abstract:
Abstract Recent advances in horizontal cask designs for commercial spent nuclear fuel have significantly increased maximum thermal loading. This is due in part to greater efficiency in internal conduction pathways. Carefully measured data sets generated from testing of full-sized casks or smaller cask analogs are widely recognized as vital for validating thermal-hydraulic models of these storage cask designs. While several testing programs have been previously conducted, these earlier validation studies did not integrate all the physics or components important in a modern, horizontal dry cask system. The purpose of this investigation is to produce data sets that can be used to benchmark the codes and best practices presently used to calculate cladding temperatures and induced cooling air flows in modern, horizontal dry storage systems. The horizontal dry cask simulator (HDCS) has been designed to generate this benchmark data and complement the existing knowledge base. Transverse and axial temperature profiles along with induced-cooling air flow are measured using various backfills of gases for a wide range of decay powers and canister pressures. The data from the HDCS tests will be used to host a blind model validation effort.
APA, Harvard, Vancouver, ISO, and other styles
8

Nikonov, S., M. Lizorkin, S. Langenbuch, and K. Velkov. "Validation of the Coupled System Code ATHLET/BIPR-VVER on Local Core Measured Data." In 16th International Conference on Nuclear Engineering. ASMEDC, 2008. http://dx.doi.org/10.1115/icone16-48604.

Full text
Abstract:
The modern coupled thermal-hydraulics neutron–kinetics code systems require validation by comparison with measured local core data. Measured assembly coolant temperatures at core outlet are applied for this purpose in this study. Experimental data have been collected during the commissioning phase of the NPP Kalinin-3. One of the experimental data sets is selected to be used for international benchmark purposes (1). The new modelling capabilities of the ATHLET/BIPR-VVER code as well as the validation on plant measurements are discussed in the paper. The detailed modelling features of the reactor core allow to predict the coolant temperature at the assembly outlet within a rather high accuracy even though ATHLET code is based on one dimensional thermal-hydraulic pipe models.
APA, Harvard, Vancouver, ISO, and other styles
9

Abbott, R. D., and T. W. McLain. "Validation of a synthesis technique for the optimal control of an electro-hydraulic positioning system." In Proceedings of 2000 American Control Conference (ACC 2000). IEEE, 2000. http://dx.doi.org/10.1109/acc.2000.876996.

Full text
APA, Harvard, Vancouver, ISO, and other styles
10

Zhao, Jian, Jun Huang, and Bing Zhu. "Modelling and Validation for an Electro-Hydraulic Braking System Equipped with the Electro-Mechanical Booster." In WCX World Congress Experience. 400 Commonwealth Drive, Warrendale, PA, United States: SAE International, 2018. http://dx.doi.org/10.4271/2018-01-0828.

Full text
APA, Harvard, Vancouver, ISO, and other styles

Reports on the topic "Hydraulic system validation"

1

Torres, Marissa, Norberto Nadal-Caraballo, and Alexandros Taflanidis. Rapid tidal reconstruction for the Coastal Hazards System and StormSim part II : Puerto Rico and U.S. Virgin Islands. Engineer Research and Development Center (U.S.), August 2021. http://dx.doi.org/10.21079/11681/41482.

Full text
Abstract:
This Coastal and Hydraulics Engineering Technical Note (CHETN) describes the continuing efforts towards incorporating rapid tidal time-series reconstruction and prediction capabilities into the Coastal Hazards System (CHS) and the Stochastic Storm Simulation System (StormSim). The CHS (Nadal-Caraballo et al. 2020) is a national effort for the quantification of coastal storm hazards, including a database and web tool (https://chs.erdc.dren.mil) for the deployment of results from the Probabilistic Coastal Hazard Analysis (PCHA) framework. These PCHA products are developed from regional studies such as the North Atlantic Coast Comprehensive Study (NACCS) (Nadal-Caraballo et al. 2015; Cialone et al. 2015) and the ongoing South Atlantic Coast Study (SACS). The PCHA framework considers hazards due to both tropical and extratropical cyclones, depending on the storm climatology of the region of interest. The CHS supports feasibility studies, probabilistic design of coastal structures, and flood risk management for coastal communities and critical infrastructure. StormSim (https://stormsim.erdc.dren.mil) is a suite of tools used for statistical analysis and probabilistic modeling of historical and synthetic storms and for stochastic design and other engineering applications. One of these tools, the Coastal Hazards Rapid Prediction System (CHRPS) (Torres et al. 2020), can perform rapid prediction of coastal storm hazards, including real-time hurricane-induced flooding. This CHETN discusses the quantification and validation of the Advanced Circulation (ADCIRC) tidal constituent database (Szpilka et al. 2016) and the tidal reconstruction program Unified Tidal analysis (UTide) (Codiga 2011) in the Puerto Rico and U.S. Virgin Islands (PR/USVI) coastal regions. The new methodology discussed herein will be further developed into the Rapid Tidal Reconstruction (RTR) tool within the StormSim and CHS frameworks.
APA, Harvard, Vancouver, ISO, and other styles
You might also be interested in the extended bibliographies on the topic 'Hydraulic system validation' for particular source types:
Journal articles
We offer discounts on all premium plans for authors whose works are included in thematic literature selections. Contact us to get a unique promo code!

To the bibliography