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You searched for +publisher:"University of Ontario Institute of Technology" +contributor:("Kaye, Matthew"). Showing records 1 – 3 of 3 total matches.

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University of Ontario Institute of Technology

1. Wang, Lian Cheng. Developing a thermodynamic model for the U-Pd-Rh-Ru quaternary system for use in the modelling of nuclear fuel.

Degree: 2018, University of Ontario Institute of Technology

Ruthenium, rhodium, and palladium are fission products in nuclear fuels. These elements and their compounds change the properties of fuel pellets. Phase diagrams involving uranium have been constructed experimentally to study fission product behaviour, specifically diagrams containing the very stable UMe3 (where Me = Ru, Rh, or Pd) compounds. Discrepancies such as enthalpies of formation of UxMey compounds exist in both experimental binary phase diagram constructions and thermodynamic property determinations. To model the behaviour of fission products in irradiated nuclear fuels, codes (e.g., BISON or RNFTT (RMC Nuclear Fuel Thermochemical Treatment) have been developed. For quantitative studies, existing experimental data are insufficient for such tasks because of difficulties determining data in ranges of composition and temperature. Experimental binary phase diagrams provide phase equilibrium information, yet if not thermodynamically evaluated, the data will be limited in application. Because industrial processes usually involve multicomponent systems that vary in wide ranges of composition and temperature. For some elements with potential catalytic functions (e.g., Pd), the U-Pd phase diagrams presented in the literature were inconsistent so it was a challenge to choose which experimental data should be used for a thermodynamic evaluation. Post irradiation examinations showed that the composition of irradiated nuclear fuels are complicated. For such complex systems, experimental determination of a full set of data is practically impossible. Nevertheless, the possibility of constructing such complex systems by means of thermodynamic evaluation exists. In this work, thermodynamic evaluations of the URu, U-Rh, and U-Pd binary phase diagrams were assessed or re-assessed (e.g., the U-Ru system). In combination with three binary systems previously assessed, a self-consistent quaternary system (U-Pd-Rh-Ru) was constructed. An alternative strategy in optimizing the Gibbs energy functions of various phases, capable of identifying experimental fallacies in hand drawn U-Rh and U-Pd phase diagrams, was proposed. With this quaternary model, two existing ternary experimental phase diagrams were critically evaluated. Results show that without thermodynamic evaluations some experimental data were wrongly interpreted. The establishment of the quaternary model enriches thermodynamic databases and will potentially improve the performance of the RNFTT treatment and codes such as BISON. Advisors/Committee Members: Kaye, Matthew.

Subjects/Keywords: Phase diagrams; Thermodynamic modelling; Nuclear fuel safety; Fission product inventory

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APA · Chicago · MLA · Vancouver · CSE | Export to Zotero / EndNote / Reference Manager

APA (6th Edition):

Wang, L. C. (2018). Developing a thermodynamic model for the U-Pd-Rh-Ru quaternary system for use in the modelling of nuclear fuel. (Thesis). University of Ontario Institute of Technology. Retrieved from http://hdl.handle.net/10155/1005

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Chicago Manual of Style (16th Edition):

Wang, Lian Cheng. “Developing a thermodynamic model for the U-Pd-Rh-Ru quaternary system for use in the modelling of nuclear fuel.” 2018. Thesis, University of Ontario Institute of Technology. Accessed October 20, 2019. http://hdl.handle.net/10155/1005.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

MLA Handbook (7th Edition):

Wang, Lian Cheng. “Developing a thermodynamic model for the U-Pd-Rh-Ru quaternary system for use in the modelling of nuclear fuel.” 2018. Web. 20 Oct 2019.

Vancouver:

Wang LC. Developing a thermodynamic model for the U-Pd-Rh-Ru quaternary system for use in the modelling of nuclear fuel. [Internet] [Thesis]. University of Ontario Institute of Technology; 2018. [cited 2019 Oct 20]. Available from: http://hdl.handle.net/10155/1005.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Council of Science Editors:

Wang LC. Developing a thermodynamic model for the U-Pd-Rh-Ru quaternary system for use in the modelling of nuclear fuel. [Thesis]. University of Ontario Institute of Technology; 2018. Available from: http://hdl.handle.net/10155/1005

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation


University of Ontario Institute of Technology

2. Palazhchenko, Olga. Pourbaix diagrams at elevated temperatures: a study of Zn and Sn.

Degree: 2012, University of Ontario Institute of Technology

Metals in industrial settings such as power plants are often subjected to high temperature and pressure aqueous environments, where failure to control corrosion compromises worker and environment safety. For instance, zircaloy (1.2-1.7 wt.% Sn) fuel rods are exposed to aqueous 250-310 °C coolant in CANDU reactors. The Pourbaix (EH-pH) diagram is a plot of electrochemical potential versus pH, which shows the domains of various metal species and by inference, corrosion susceptibility. Elevated temperature data for tin +II and tin +IV species were obtained using solid-aqueous phase equilibria with the respective oxides, in a batch vessel with in-situ pH measurement. Solubilities, determined via spectroscopic techniques, were used to calculate equilibrium constants and the Gibbs energies of Sn complexes for E-pH diagram construction. The SnOH3+ and Sn(OH) species were incorporated, for the first time, into the 298.15 K and 358.15 K diagrams, with novel G ?? values determined at 358.15 K. Advisors/Committee Members: Kaye, Matthew H..

Subjects/Keywords: Pourbaix diagrams; Corrosion; Elevated temperature; Solubility

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APA · Chicago · MLA · Vancouver · CSE | Export to Zotero / EndNote / Reference Manager

APA (6th Edition):

Palazhchenko, O. (2012). Pourbaix diagrams at elevated temperatures: a study of Zn and Sn. (Thesis). University of Ontario Institute of Technology. Retrieved from http://hdl.handle.net/10155/276

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Chicago Manual of Style (16th Edition):

Palazhchenko, Olga. “Pourbaix diagrams at elevated temperatures: a study of Zn and Sn.” 2012. Thesis, University of Ontario Institute of Technology. Accessed October 20, 2019. http://hdl.handle.net/10155/276.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

MLA Handbook (7th Edition):

Palazhchenko, Olga. “Pourbaix diagrams at elevated temperatures: a study of Zn and Sn.” 2012. Web. 20 Oct 2019.

Vancouver:

Palazhchenko O. Pourbaix diagrams at elevated temperatures: a study of Zn and Sn. [Internet] [Thesis]. University of Ontario Institute of Technology; 2012. [cited 2019 Oct 20]. Available from: http://hdl.handle.net/10155/276.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Council of Science Editors:

Palazhchenko O. Pourbaix diagrams at elevated temperatures: a study of Zn and Sn. [Thesis]. University of Ontario Institute of Technology; 2012. Available from: http://hdl.handle.net/10155/276

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation


University of Ontario Institute of Technology

3. Golesorkhi, Sourena. An evaluation of the net breeding capability of heterogeneously-fuelled pressure-tube heavy water reactors with the thorium fuel cycle.

Degree: 2015, University of Ontario Institute of Technology

The thorium fuel cycle is a promising future option for an alternative to uranium. The pressure tube heavy water reactor (PT-HWR) has for decades been considered capable of achieving net breeding on the thorium fuel cycle, but this capability has not been conclusively demonstrated. The goal of this work was to perform reactor physics modelling of the 380-channel, 700 MWe PT-HWR, attempting to achieve a self-sustaining equilibrium thorium cycle with specific focus on operational viability. The DRAGON neutron transport code was used to model ThO???/??????UO??? fuel lattice cells. Sensitivity analyses were performed for the fissile nuclide content, specific power, and average fuel temperature. Thorium-based fuels are found to have a strongly negative power coefficient of reactivity, leading to criticality concerns in the event of a prolonged shutdown. Several fuel bundle concepts were modelled in order to determine the most favourable assembly for breeding. The results showed no significant benefit to other concepts, therefore the standard 37-element bundle was selected due to its wealth of operational experience and well-known operating margins. Homogeneous fuelling was found to be impractical for breeding, and heterogeneous fuel bundles were found to not offer significant improvement while increasing complexity. As a result, heterogeneous core configurations using homogeneous bundles were investigated in full core calculations. The DONJON core physics code was used in conjunction with homogenized cross-sections calculated by DRAGON to model the complete reactor, including reactivity devices and supporting structures. Seven fuelling configurations were simulated and iteratively improved through an empirical process. Ultimately, none of the studied configurations could achieve net breeding. The most favourable configuration was found to be a heterogeneous seed and blanket core where the blanket (composed of 1.4 at% ??????U) was placed in the central region and the seed (composed of 1.6 at% ??????U) was placed in the periphery. Two variants of this configuration (differing on the refuelling scheme used in the blanket) were further investigated with instantaneous power simulations with 10 full power days of refuelling. Both variants were found to abide by the existing license limits on maximum bundle and channel power. The variant using 4-bundle shift in both blanket and seed could tolerate an increase in reactor power to 110% FP while maintaining a comfortable margin to safety. A number of postulated misfuelling events were simulated for both variants, and the responses were found to be controllable by the existing reactivity systems. It is noted that there are significant sources of error in the results of this work. Advances in computational methods as well as better nuclear data for the thorium fuel cycle are required for more accurate predictions. Overall, while the PT-HWR has great potential as a very high converting reactor, based on the results of this work, the existing design cannot operate as a net… Advisors/Committee Members: Kaye, Matthew Haigh.

Subjects/Keywords: Thorium; PT-HWR; Breeder reactor; SSET; CANDU

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APA · Chicago · MLA · Vancouver · CSE | Export to Zotero / EndNote / Reference Manager

APA (6th Edition):

Golesorkhi, S. (2015). An evaluation of the net breeding capability of heterogeneously-fuelled pressure-tube heavy water reactors with the thorium fuel cycle. (Thesis). University of Ontario Institute of Technology. Retrieved from http://hdl.handle.net/10155/617

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Chicago Manual of Style (16th Edition):

Golesorkhi, Sourena. “An evaluation of the net breeding capability of heterogeneously-fuelled pressure-tube heavy water reactors with the thorium fuel cycle.” 2015. Thesis, University of Ontario Institute of Technology. Accessed October 20, 2019. http://hdl.handle.net/10155/617.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

MLA Handbook (7th Edition):

Golesorkhi, Sourena. “An evaluation of the net breeding capability of heterogeneously-fuelled pressure-tube heavy water reactors with the thorium fuel cycle.” 2015. Web. 20 Oct 2019.

Vancouver:

Golesorkhi S. An evaluation of the net breeding capability of heterogeneously-fuelled pressure-tube heavy water reactors with the thorium fuel cycle. [Internet] [Thesis]. University of Ontario Institute of Technology; 2015. [cited 2019 Oct 20]. Available from: http://hdl.handle.net/10155/617.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Council of Science Editors:

Golesorkhi S. An evaluation of the net breeding capability of heterogeneously-fuelled pressure-tube heavy water reactors with the thorium fuel cycle. [Thesis]. University of Ontario Institute of Technology; 2015. Available from: http://hdl.handle.net/10155/617

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

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