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Fuel and Core Physics Considerations for a Pressure Tube Supercritical Water Cooled Reactor

dc.contributor.advisorNovog, D. R.en_US
dc.contributor.authorMcDonald, Michael H.en_US
dc.contributor.departmentEngineering Physics and Nuclear Engineeringen_US
dc.date.accessioned2014-06-18T16:53:58Z
dc.date.available2014-06-18T16:53:58Z
dc.date.created2011-09-20en_US
dc.date.issued2011-10en_US
dc.description.abstract<p>The supercritical water cooled reactor (SCWR) is a Generation IV reactor concept that features light water coolant in a supercritical state. Canada is developing a pressure tube variant of the supercritical water reactor as an evolution of the CANDU reactor. The main advantages of the pressure tube SCWR are an improved thermal efficiency over current reactors, enhanced safety through passive safety features, and plant simplifications. The objective of this thesis was to investigate current fuel and core designs for the Canadian SCWR concept.</p> <p>Simulations of 2-D lattice cells for fuel assemblies containing 43 and 54 fuel elements were performed using the neutron transport code WIMS-AECL. Safety parameters and fuel burnup performance were investigated here. Three dimensional full core simulations were performed using the diffusion code RFSP. These studies examined batch fueling, cycle length, radial and axial power profiles, linear element ratings, and reduction of axial power peaking through graded enrichment along the fuel channel. Finally, a study of reactivity transients was performed using the FUELPIN heat transfer/point kinetics code.</p> <p>The main results of the studies show that the coolant density change that occurs as water passes through the pseudocritical point strongly affects fuel performance. It is concluded that the 54 element assembly design is acceptable in terms of coolant void reactivity performance with lattice pitch smaller than 26 cm. To meet the burnup target, a fuel enrichment of about 5% is required. From the RFSP studies, this level of fuel enrichment will provide an operating period of 370 days between refueling. Relatively high axial power peaking is observed at the beginning of cycle conditions. A main finding is that the proposed reactor power level of 2540 MWth produces unacceptably high linear element ratings. This is confirmed using the FUELPIN code. A reduction in linear element rating is suggested for consideration.</p>en_US
dc.description.degreeMaster of Applied Science (MASc)en_US
dc.identifier.otheropendissertations/6207en_US
dc.identifier.other7216en_US
dc.identifier.other2247591en_US
dc.identifier.urihttp://hdl.handle.net/11375/11223
dc.subjectReactor physicsen_US
dc.subjectsupercritical water cooled reactoren_US
dc.subjectfuelen_US
dc.subjectNuclear Engineeringen_US
dc.subjectNuclear Engineeringen_US
dc.titleFuel and Core Physics Considerations for a Pressure Tube Supercritical Water Cooled Reactoren_US
dc.typethesisen_US

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