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Modeling of Proposed Changes to SIUC Central Heating, Air-Conditioning, and Power Plant Incorporating Variable Frequency Drive (VFD) and High Efficiency TurbineSu, Heyin 01 August 2011 (has links)
Currently, the Southern Illinois University Carbondale (SIUC) power plant produces steam at high pressure to drive a high pressure (HP) turbine to make a portion of the electrical power needed by campus, then using 969 kPa (125 psig) steam to provide hot water all year, heat buildings, and to operate a low pressure (LP) turbine that powers the compressor of the central air conditioning (A/C) system. In the proposed system, the HP turbine is replaced by a much higher efficiency, multi-level turbine, the LP turbine is replaced with a motor and Variable Frequency Drive (VFD), and a cooling tower is added to condense more possible steam. This thesis has provided computer models to evaluate the economical feasibility of the proposed system, which are written by using Engineering Equation Solver (EES) software. The results of the study are presented in two cases. Case 1 examines the same amount of coal use between current and proposed systems, while Case 2 exames operating the high pressure boiler at the maximum rate. The results are a cost savings of $1,921,000 and $3,604,000 with payback periods of 4 and 2.2 years for Case 1 and Case 2, respectively. The annual primary energy saved and CO2 reduction from this modification was 200,000 GJ and 564,814 moles, respectively.
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Thermal–hydraulics simulation of a benchmark case for a typical Materials Test Reactor using Flownex / Slabbert R.Slabbert, Rohan January 2011 (has links)
The purpose of this study was to serve as a starting point in gaining understanding and experience of simulating a typical Pool Type Research Reactor with the thermal hydraulic software code Flownex®. During the study the following evaluations of Flownex® were done:
* Assessment of the simplifying assumptions and possible shortcomings built into the software.
* Definition of the applicable modelling methodology and further simplifying assumptions that have to be made by the user.
* Evaluation of the accuracy and compatibility with the Pool Type Research Reactor.
* Comparing the results of this study with similar studies found in the open literature.
For the study the IAEA MTR 10 MW benchmark reactor (IAEA, 1992a) was used. A steady state simulation using Flownex® was done on a single fuel assembly, and this was compared with a model that was developed using the software package EES (Engineering Equation Solver). The results have shown good agreement between the different packages. After this verification, a steady state simulation of the entire core was done to obtain the characteristics of the reactor operating under normal condition. Finally, transient simulations were done on various LOFAs (Loss of Flow Accidents). The results of the various LOFAs were compared with studies that were previously done on the IAEA MTR 10 MW reactor. / Thesis (M.Ing. (Nuclear Engineering))--North-West University, Potchefstroom Campus, 2012.
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Thermal–hydraulics simulation of a benchmark case for a typical Materials Test Reactor using Flownex / Slabbert R.Slabbert, Rohan January 2011 (has links)
The purpose of this study was to serve as a starting point in gaining understanding and experience of simulating a typical Pool Type Research Reactor with the thermal hydraulic software code Flownex®. During the study the following evaluations of Flownex® were done:
* Assessment of the simplifying assumptions and possible shortcomings built into the software.
* Definition of the applicable modelling methodology and further simplifying assumptions that have to be made by the user.
* Evaluation of the accuracy and compatibility with the Pool Type Research Reactor.
* Comparing the results of this study with similar studies found in the open literature.
For the study the IAEA MTR 10 MW benchmark reactor (IAEA, 1992a) was used. A steady state simulation using Flownex® was done on a single fuel assembly, and this was compared with a model that was developed using the software package EES (Engineering Equation Solver). The results have shown good agreement between the different packages. After this verification, a steady state simulation of the entire core was done to obtain the characteristics of the reactor operating under normal condition. Finally, transient simulations were done on various LOFAs (Loss of Flow Accidents). The results of the various LOFAs were compared with studies that were previously done on the IAEA MTR 10 MW reactor. / Thesis (M.Ing. (Nuclear Engineering))--North-West University, Potchefstroom Campus, 2012.
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