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Simulation of condensation in the presence of noncondensible gases using the French Thermal Hydraulic computer code CATHARE
dc.creator | Reyes, Joseph Patrick | |
dc.date.accessioned | 2012-06-07T22:46:32Z | |
dc.date.available | 2012-06-07T22:46:32Z | |
dc.date.created | 1996 | |
dc.date.issued | 1996 | |
dc.identifier.uri | https://hdl.handle.net/1969.1/ETD-TAMU-1996-THESIS-R49 | |
dc.description | Due to the character of the original source materials and the nature of batch digitization, quality control issues may be present in this document. Please report any quality issues you encounter to digital@library.tamu.edu, referencing the URI of the item. | en |
dc.description | Includes bibliographical references. | en |
dc.description | Issued also on microfiche from Lange Micrographics. | en |
dc.description.abstract | The modeling of the complex thermal hydraulics of reactor systems involves the use of experimental test systems as well as numerical codes. A simulation of the phenomena of condensation in the presence of noncondensible gas was performed using the CATHARE thermal hydraulic code. The experiments were conducted at the University of California, Berkeley, and at the Energy Research Laboratory in Japan; supervised by Hitachi, Ltd.. The experiments involved the condensation of a steam/air mixture in downward flow through pipes. The test sections approximate the design of isolation condensers included in the passive containment cooling system in the new generation of nuclear reactors. Both the University of California at Berkeley and Hitachi test sections consisted of a stainless steel pipe connected to an upper and lower plenum. An annulus containing cooling water was present in both experiments. The steam/air mixture was introduced into the test section by means of mixers connected to the upper plenum. The transient runs were conducted on two separate platforms. The University of California at Berkeley simulation was conducted on a HP 9000/720 Workstation at Texas A&M University. The Hitachi simulation was performed on the "ventoux" branch of the HP network located at the Centre D'Etudes Nucleaires de Grenoble, located in Grenoble, France. The position in which condensation began to occur was overpredicted in the Berkeley simulation, but was accurate in the Hitachi simulation. The liquid heat flux was heavily underpredicted in both the Berkeley and Hitachi simulation. As a result of the underprediction in the heat flux profile, the condensing tube wall temperature and the local overall temperature coefficients were underpredicted in comparison to the experimental data. Secondary side cooling water temperature was also underpredicted as a result of the underprediction of the primary side heat flux. Overall, the CATHARE simulation were in reasonable agreement with both the low and high pressure cases. | en |
dc.format.medium | electronic | en |
dc.format.mimetype | application/pdf | |
dc.language.iso | en_US | |
dc.publisher | Texas A&M University | |
dc.rights | This thesis was part of a retrospective digitization project authorized by the Texas A&M University Libraries in 2008. Copyright remains vested with the author(s). It is the user's responsibility to secure permission from the copyright holder(s) for re-use of the work beyond the provision of Fair Use. | en |
dc.subject | nuclear engineering. | en |
dc.subject | Major nuclear engineering. | en |
dc.title | Simulation of condensation in the presence of noncondensible gases using the French Thermal Hydraulic computer code CATHARE | en |
dc.type | Thesis | en |
thesis.degree.discipline | nuclear engineering | en |
thesis.degree.name | M.S. | en |
thesis.degree.level | Masters | en |
dc.type.genre | thesis | en |
dc.type.material | text | en |
dc.format.digitalOrigin | reformatted digital | en |
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