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dc.contributor.advisorHassan, Yassin A.
dc.creatorVaghetto, Rodolfo
dc.date.accessioned2014-05-13T17:21:41Z
dc.date.available2015-12-01T06:31:12Z
dc.date.created2013-12
dc.date.issued2013-11-25
dc.date.submittedDecember 2013
dc.identifier.urihttp://hdl.handle.net/1969.1/151742
dc.description.abstractThe Very High Temperature Gas-Cooled Reactor (VHTR) is one of the next generation nuclear reactors designed to achieve high temperatures to support industrial applications and power generation. The Reactor Cavity Cooling System (RCCS) is a passive safety system that will be incorporated in the VTHR, designed to remove the heat from the reactor cavity and maintain the temperature of structures and concrete walls under desired limits during normal operation and accident scenarios. A small scale (1:23) water-cooled experimental facility was scaled, designed, and constructed in order to study the complex thermohydraulic phenomena taking place in the RCCS during steady-state and transient conditions. The facility represents a portion of the reactor vessel with nine stainless steel coolant risers and utilizes water as coolant. The facility was equipped with instrumentation to measure temperatures and flow rates and a general verification was completed during the shakedown. A model of the experimental facility was prepared using RELAP5-3D and simulations were performed to validate the scaling procedure. The overall behavior of the facility met the expectations. The steady-state condition was achieved and the facility capabilities were confirmed to be very promising in performing additional experimental tests, including flow visualization, and produce data for code validation. The experimental data produced during the steady-state run were successfully compared with the simulation results obtained using RELAP5-3D, confirming the capabilities of the system code of simulating the thermal-hydraulic phenomena occurring in the reactor cavity.en
dc.format.mimetypeapplication/pdf
dc.language.isoen
dc.subjectPassive safetyen
dc.subjectnatural circulationen
dc.subjectRCCSen
dc.subjectcode validationen
dc.titleExperimental and Computational Study of a Scaled Reactor Cavity Cooling System
dc.typeThesisen
thesis.degree.departmentNuclear Engineeringen
thesis.degree.disciplineNuclear Engineeringen
thesis.degree.grantorTexas A & M Universityen
thesis.degree.nameDoctor of Philosophyen
thesis.degree.levelDoctoralen
dc.contributor.committeeMemberAnnamalai, Kalyan
dc.contributor.committeeMemberKing, Maria D.
dc.contributor.committeeMemberMarlow, William H.
dc.type.materialtexten
dc.date.updated2014-05-13T17:21:41Z
local.embargo.terms2015-12-01


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