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dc.contributor.authorCasey, William Emerson
dc.date.accessioned2013-02-15T23:34:21Z
dc.date.available2013-02-15T23:34:21Z
dc.date.issued1990
dc.identifier.urihttp://hdl.handle.net/10945/28606
dc.descriptionTitle as it appears in the M.I.T. Graduate List, Jun. 4, 1990: Transient thermal-hydraulic analysis of a packed particle bed reactor fuel elementen_US
dc.description.abstractA model which describes the thermal-hydraulic behavior of a packed particle bed reactor fuel element is developed and compared to a reference standard. The model represents a step toward a thermal-hydraulic module for a real-time, autonomous reactor powder controller. The general configuration of the fuel element is a bed of small (diameter about 500 microns) fuel particles are packed between concentrically mounted retention cylinders referred to as frits. The momentum integral approach used in the MINET code is applied ot this model to balance the fundamental mass, energy and momentum conservation relationships. The element is divided into only three control volumes: the inlet plenum and cold frit define the first control volume, the fuel particle bed defines a second control volume, and the outlet plenum and hot frit define the third control volume. The solid phase of the particle bed is represented by a single node. This simple model was validated against the reference standard and compared favorably. As a demonstration of the model's flexibility, a number of variations were analyzed. These included variations in fuel element geometry and the initial and final values of inlet temperature, inlet pressure, and outlet pressure. As a final demonstration a cluster of nineteen, 1 meter long fuel elements, arranged to form a core, were analyzed for an up-power transient from 0 MWt to approximately 18 MWt. The simple model significantly decreases the time necessary to perform a single analysis. A transient of 10s with a timestep of 10 ms, for example, takes approximately 45s of computation on a desktop computer equipped with an 80386 microprocessoren_US
dc.description.urihttp://archive.org/details/thermalhydraulic00case
dc.format.extent146 leaves: ill. 28 cm.en_US
dc.language.isoen_US
dc.rightsThis publication is a work of the U.S. Government as defined in Title 17, United States Code, Section 101. As such, it is in the public domain, and under the provisions of Title 17, United States Code, Section 105, may not be copyrighted.en_US
dc.titleThermal-hydraulic transient analysis of a packed particle bed reactor fuel elementen_US
dc.title.alternativeTitle as it appears in the M.I.T. Graduate List, Jun. 4, 1990: Transient thermal-hydraulic analysis of a packed particle bed reactor fuel elementen_US
dc.typeThesisen_US
dc.contributor.departmentNaval Engineering
dc.contributor.departmentNuclear Engineering
dc.contributor.departmentOcean Engineering
dc.subject.authorTitle as it appears in the M.I.T. Graduate List, Jun. 4, 1990: Transient thermal-hydraulic analysis of a packed particle bed reactor fuel element.;"May 1990."en_US
dc.description.serviceU.S. Navy (U.S.N.) author.en_US
dc.identifier.oclcocm23735539
etd.thesisdegree.nameDegree of Naval Engineeringen_US
etd.thesisdegree.nameM.S. in Nuclear Engineeringen_US
etd.thesisdegree.levelMastersen_US
etd.thesisdegree.levelProfessional Degreeen_US
etd.thesisdegree.disciplineNaval Engineeringen_US
etd.thesisdegree.disciplineNuclear Engineeringen_US
etd.thesisdegree.grantorMassachusetts Institute of Technologyen_US


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