{"id":{"repo_id":"ohiolink","oai_identifier":"oai:etd.ohiolink.edu:osu1357273230"},"canonical_url":"https://search.dev.ndltd.org/etd/ohiolink/oai:etd.ohiolink.edu:osu1357273230","repository":{"repo_id":"ohiolink","name":"OhioLINK","base_url":"https://etd.ohiolink.edu/acprod/odb_etd/ws/oai/oai"},"display":{"title":"Hardware-in-the-loop simulation of pressurized water reactor steam-generator water-level control, designed for use within physically distributed testing environments","abstract":"A hardware-in-the-loop model was developed to represent digital sensing and control of steam generator water-level. The model was created with an intention to serve as a component within a larger, distributed digital systems conceptual testing facility. In the present application, a software model simulates a nuclear pressurized water reactor core, and the core is cooled by a hardware and software model of a Westinghouse U-tube steam generator. The present application is configured using plant specifications consistent with “Plant X”.Software was written in C++¿¿, and hardware components include Phidgets and Measurement Computing digital input-output modules, proportional solenoid valves, a PC cooling pump, and gear pumps. This model assumes perfect implementation of sliding average-core-temperature control. During plant startup or normal operation, plant power precisely determines all steam flow characteristics. Liquid water simulates secondary coolant flow. Water pumped from a tank simulates steam, and recuperating feed water responds to subsequent level readings. Level readings as a function of plant power are measured and lie within the alarm-free region of the narrow range (+/-5% of the level set point). This design has been developed for incorporation within a distributed hardware/software component within a digital systems conceptual testing facility for digital systems testing by network-distributed control.","abstract_html":"A hardware-in-the-loop model was developed to represent digital sensing and control of steam generator water-level. The model was created with an intention to serve as a component within a larger, distributed digital systems conceptual testing facility. In the present application, a software model simulates a nuclear pressurized water reactor core, and the core is cooled by a hardware and software model of a Westinghouse U-tube steam generator. The present application is configured using plant specifications consistent with “Plant X”.Software was written in C++¿¿, and hardware components include Phidgets and Measurement Computing digital input-output modules, proportional solenoid valves, a PC cooling pump, and gear pumps. This model assumes perfect implementation of sliding average-core-temperature control. During plant startup or normal operation, plant power precisely determines all steam flow characteristics. Liquid water simulates secondary coolant flow. Water pumped from a tank simulates steam, and recuperating feed water responds to subsequent level readings. Level readings as a function of plant power are measured and lie within the alarm-free region of the narrow range (+/-5% of the level set point). This design has been developed for incorporation within a distributed hardware/software component within a digital systems conceptual testing facility for digital systems testing by network-distributed control.","abstract_has_math":false,"creators":["Brink, Michael Joseph"],"institution":"The Ohio State University","degree_name":"Master of Science","degree_level":"masters","degree_discipline":"Nuclear Engineering","degree_department":null,"school":null,"contributors":["Smidts, Carol"],"advisors":[],"committee_chairs":[],"committee_members":[],"year":2013,"date_issued":"2013-05-21","date_published":"2013-05-21","updated_at":"2026-07-24T03:36:08Z","subjects":["Engineering","Nuclear Engineering","Hardware-in-the-loop","PWR","steam generator","software simulation","nuclear power","pressurized water reactor","digital instrumentation and control","physically distributed testing"],"languages":["English"],"rights":["unrestricted","This thesis or dissertation is protected by copyright: all rights reserved. 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The present application is configured using plant specifications consistent with “Plant X”.Software was written in C++¿¿, and hardware components include Phidgets and Measurement Computing digital input-output modules, proportional solenoid valves, a PC cooling pump, and gear pumps. This model assumes perfect implementation of sliding average-core-temperature control. During plant startup or normal operation, plant power precisely determines all steam flow characteristics. Liquid water simulates secondary coolant flow. Water pumped from a tank simulates steam, and recuperating feed water responds to subsequent level readings. Level readings as a function of plant power are measured and lie within the alarm-free region of the narrow range (+/-5% of the level set point). This design has been developed for incorporation within a distributed hardware/software component within a digital systems conceptual testing facility for digital systems testing by network-distributed control."]},{"key":"dc:format","label":"Dc Format","values":["application/pdf","p.185","2.19 MB"]},{"key":"dc:title","label":"Title","values":["Hardware-in-the-loop simulation of pressurized water reactor steam-generator water-level control, designed for use within physically distributed testing environments"]}]}],"canonical_facts":{"dc:contributor":["Smidts, Carol"],"dc:creator":["Brink, Michael Joseph"],"dc:date":["2013-05-21"],"dc:description":["A hardware-in-the-loop model was developed to represent digital sensing and control of steam generator water-level. The model was created with an intention to serve as a component within a larger, distributed digital systems conceptual testing facility. In the present application, a software model simulates a nuclear pressurized water reactor core, and the core is cooled by a hardware and software model of a Westinghouse U-tube steam generator. The present application is configured using plant specifications consistent with “Plant X”.Software was written in C++¿¿, and hardware components include Phidgets and Measurement Computing digital input-output modules, proportional solenoid valves, a PC cooling pump, and gear pumps. This model assumes perfect implementation of sliding average-core-temperature control. During plant startup or normal operation, plant power precisely determines all steam flow characteristics. Liquid water simulates secondary coolant flow. Water pumped from a tank simulates steam, and recuperating feed water responds to subsequent level readings. Level readings as a function of plant power are measured and lie within the alarm-free region of the narrow range (+/-5% of the level set point). 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