scholarly journals Electric Motors for Variable-Speed Drive of Lock Valves

2021 ◽  
Author(s):  
Aleksey V. Udovichenko ◽  
Dmitri Kaluzhskij ◽  
Nikita Uvarov ◽  
Ali Mekhtiyev
Keyword(s):  
Nuclear Power ◽  
Power Plants ◽  
Oil And Gas ◽  
Theoretical Data ◽  
Operational Reliability ◽  
Variable Speed ◽  
Variable Speed Drive ◽  
Technical Requirements ◽  
Priority Task ◽  
Selection Of

Improving the operational reliability of nuclear power plants, combined heat and power plants (CHP), as well as oil and gas pipelines is a priority task in the development of a variable-speed drive for lock valves used at these facilities. The paper analyzes technical requirements for such devices; the motor has been selected, its electrical equilibrium and moment equations have been obtained; recommendations for the selection of the kinematic drive scheme have been formulated. Based on the theoretical data obtained, a prototype has been developed, manufactured and tested.

scholarly journals Electric Motors for Variable-Speed Drive of Lock Valves

Electronics ◽  
2021 ◽  
Vol 10 (21) ◽  
pp. 2727
Author(s):  
Aleksey V. Udovichenko ◽  
Dmitri Kaluzhskij ◽  
Nikita Uvarov ◽  
Ali Mekhtiyev
Keyword(s):  
Nuclear Power ◽  
Power Plants ◽  
Oil And Gas ◽  
Theoretical Data ◽  
Operational Reliability ◽  
Variable Speed ◽  
Variable Speed Drive ◽  
Technical Requirements ◽  
Priority Task ◽  
Selection Of

Improving the operational reliability of nuclear power plants, combined heat and power plants (CHP), as well as oil and gas pipelines is a priority task in the development of a variable-speed drive for lock valves used at these facilities. This paper analyzes the technical requirements for such devices: the motor has been selected, its electrical equilibrium and moment equations have been obtained; recommendations for the selection of the kinematic drive scheme have been formulated. Based on the theoretical data obtained, a prototype has been developed, manufactured, and tested.

DESIGN, SIMULATION AND IMPLEMENTATION MONITORING SYSTEM FOR SYSTEM CONTROL C4 FEEDING PUMP FOR FEED VAPORIZATION IN THE BUTADIENE PLANT

2020 ◽  
Vol 1 (1) ◽  
pp. 31-35
Author(s):  
Fahmi Yunistyawan ◽  
Yunistyawan J Berchmans ◽  
Gembong Baskoro
Keyword(s):  
Motor Control ◽  
Control System ◽  
Field Operator ◽  
System Control ◽  
Variable Speed ◽  
Variable Speed Drive ◽  
Software And Hardware ◽  
Discharge Pressure ◽  
Selection Of

This study implements the auto start control system on an electric motor 3 phase C4Feeding pump when the discharge pressure is low-low (4.3 kg /cm²). The C4 feeding pumpmotor was initially manually operated from the local control station, this was very ineffectiveand inefficient because it still relied on the field operator to operate the pump motor and whenthe plant was in normal operating it is very risk if the field operator late to operate motor then itwill impact to quality of the product, and if the delay time to operate motor is too long then planthave to shut down, therefore improvement is needed in the C4 feeding pump motor controlsystem. In this paper, various types of 3-phase motor control are explained which allow it to beapplied to the C4 feeding pump motor that are on-off, inverter, and variable speed drive andefficient selection of the three systems control of the motor. Software and hardware used in thisthesis work are DCS CENTUM VP Yokogawa.

Experimental Study of Selected Properties of Heavyweight Concrete Based on Analysis of Chemical Composition and Radioactive Elements of its Components

2021 ◽  
Vol 321 ◽  
pp. 113-118
Author(s):  
Janette Dragomirová ◽  
Martin T. Palou ◽  
Katalin Gméling ◽  
Veronika Szilágyi ◽  
Ildikó Harsányi ◽  
...  
Keyword(s):  
Bulk Density ◽  
Nuclear Power ◽  
Power Plants ◽  
Concrete Strength ◽  
Prompt Gamma ◽  
Longitudinal Deformation ◽  
Heavyweight Concrete ◽  
Furnace Slag ◽  
Selection Of

Heavyweight concrete is mostly used for its shielding properties in the nuclear power plants. These properties can already be influenced by the selection of the input materials. In the present study, concrete samples comprised of four-component binders based on CEM I 42.5 R, blast furnace slag, metakaolin and limestone and a mixture of barite and magnetite aggregate, were investigated. Based on Energy Dispersive X-ray Fluorescence, Neutron Activation, and Prompt-Gamma Activation analyses, three concrete designs were prepared and tested. Mechanical, physical (namely cubic compressive strength, bulk density, longitudinal deformation, and dynamic modulus of elasticity) and thermal properties (thermal conductivity coefficient, specific heat capacity, and thermal diffusivity), which should be influenced by the long-term exposure to irradiation were investigated. Presented results confirmed that the prepared samples are heavyweight concrete with bulk density higher than 3400 kg.m-3 with a low level of longitudinal deformation (between 0.265 ‰ and 0.352 ‰). All the prepared samples belong to the C 35/45 concrete strength class.

INTERCOMPARISON ON INTERNAL DOSE ASSESSMENT FOR NUCLEAR POWER PLANTS IN KOREA

2019 ◽  
Vol 186 (4) ◽  
pp. 524-529
Author(s):  
Si Young Kim
Keyword(s):  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Evaluation Method ◽  
Dose Assessment ◽  
Assessment Procedure ◽  
Internal Dose ◽  
Nuclear Facilities ◽  
International Intercomparison ◽  
Selection Of

Abstract The intercomparison test is a quality assurance activity performed for internal dose assessment. In Korea, the intercomparison test on internal dose assessment was carried out for nuclear facilities in May 2018. The test involved four nuclear facilities in Korea, and seven exposure scenarios were applied. These scenarios cover the intake of 131I, a uranium mixture, 60Co and tritium under various conditions. This paper only reviews the participant results of three scenarios pertinent to the operation of nuclear power plants and adopts the statistical evaluation method, used in international intercomparison tests, to determine the significance values of the results. Although no outliers were established in the test, improvements in the internal dose assessment procedure were derived. These included the selection of intake time, selection of lung absorption type according to the chemical form and consideration of the contribution of previous intake.

Blowout preventer (BOP) risk model to assist critical decisions in offshore drilling

2013 ◽  
Vol 53 (1) ◽  
pp. 209
Author(s):  
Inge Alme ◽  
Angel Casal ◽  
Trygve Leinum ◽  
Helge Flesland
Keyword(s):  
Nuclear Power ◽  
Power Plants ◽  
Oil And Gas ◽  
Risk Model ◽  
Oil And Gas Industry ◽  
Third Party ◽  
Risk Level ◽  
Main Task ◽  
Offshore Drilling ◽  
Drilling Rig

The BOP is a critical safety system of an offshore drilling rig, as shown in the 2010 Macondo accident. A challenge for the oil and gas industry is to decide what to do when the BOP is failing. Pulling the BOP to the surface during operations for inspection and testing is a costly and timely operation. Many of the potential failures are not critical to overall safety as multiple levels of redundancy are often available. Scandpower and Moduspec, both subsidiaries of Lloyd’s Register, have developed a BOP risk model that will assist the industry make the pull or no pull decisions. Scandpower’s proprietary software RiskSpectrum is used for the modelling. This software is used for equivalent decision support in the nuclear power industry, where the risk levels of total nuclear power plants are monitored live by operators in the control rooms. By modelling existing BOPs and their submerged control systems, and using risk monitor software for keeping track on the status of the BOP subsystems and components, the industry is able to define the real-time operational risk level the BOP is operating at. It, therefore, allows the inclusion for sensitivity modelling with possible faulty components factored in the model. The main task of the risk model is to guide and support energy companies and regulators in the decision process when considering whether to pull the BOP for repairs. Moreover, it will help the communication with the regulators, since the basis for the decisions are more traceable and easier to follow for a third party.

Nuclear Power Plant Decommissioning in Germany: Projects, Regulation and Experience

2009 ◽  
Author(s):  
Leopold Weil ◽  
Bernd Rehs
Keyword(s):  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Energy ◽  
Radioactive Decay ◽  
Federal State ◽  
Regulatory Body ◽  
Nuclear Facilities ◽  
Interim Storage ◽  
Near Future ◽  
Selection Of

In Germany, altogether 19 nuclear power plants (NPPs) and prototype reactors have been permanently shut down. For 15 NPPs the dismantling is in progress with “green-field conditions” as planning target. Two units were completely dismantled and two are in safe enclosure. The main legal provision for all aspects of the peaceful use of nuclear energy in Germany is the Atomic Energy Act (AtG), which also contains the basic legal conditions for the decommissioning of nuclear facilities. It stipulates that decommissioning is subject to a licence by the regulatory body of the respective Federal State (Land). An emerging decommissioning practice in Germany is the removal of complete undismantled large components and their transport to interim storage facilities. During the period of storage, the radionuclide inventory of the components will decrease due to radioactive decay and the subsequent segmentation of the components can be done with less radiation protection effort. The commissioning of the Konrad repository in the near future might have consequences on planning of decommissioning, regarding the selection of a decommissioning strategy and the waste management.

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