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You searched for subject:(GT MHR). Showing records 1 – 2 of 2 total matches.

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The Ohio State University

1. Hawn, David Phillip. Development of a Dynamic Model of a Counterflow Compact Heat Exchanger for Simulation of the GT-MHR Recuperator using MATLAB and Simulink.

Degree: MS, Nuclear Engineering, 2009, The Ohio State University

A computational model was developed to determine the dynamic behavior of counter flow compact heat exchangers. This code was written with the intention of becoming a component of a larger system dynamics model of a Brayton cycle nuclear power plant. Several configurations for the GT-MHR recuperator were analyzed, but the code can easily be modified to analyze many types of compact heat exchangers with a variety of applications. Helium was the working fluid used in this project, but the code can be modified to use other gases. This code was written in Matlab and Simulink but the methods outlined in this report could be easily reapplied in other programming languages. This code is also useful for designing counter flow compact heat exchangers in general. In this model the heat exchanger is discretized in time and in space. The resolution of the discretization is defined by the user. Helium properties are reevaluated for each volume before each time step. The dynamic inputs to the model are the inlet temperature, mass flow rate and pressure for each side of the heat exchanger. This model assumes low Mach number flows and treats the propagation of pressure and mass flow rate changes as instantaneous. The outlet temperature and pressure drop for each side is determined. The results of the simulation were successfully validated against results available in the literature. Contact the author for a copy of this code. Advisors/Committee Members: Blue, Thomas (Committee Chair).

Subjects/Keywords: Mechanical Engineering; Nuclear Physics; compact heat exchanger; recuperator; system dynamics; GT-MHR; transient analysis

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APA (6th Edition):

Hawn, D. P. (2009). Development of a Dynamic Model of a Counterflow Compact Heat Exchanger for Simulation of the GT-MHR Recuperator using MATLAB and Simulink. (Masters Thesis). The Ohio State University. Retrieved from http://rave.ohiolink.edu/etdc/view?acc_num=osu1236091152

Chicago Manual of Style (16th Edition):

Hawn, David Phillip. “Development of a Dynamic Model of a Counterflow Compact Heat Exchanger for Simulation of the GT-MHR Recuperator using MATLAB and Simulink.” 2009. Masters Thesis, The Ohio State University. Accessed April 19, 2019. http://rave.ohiolink.edu/etdc/view?acc_num=osu1236091152.

MLA Handbook (7th Edition):

Hawn, David Phillip. “Development of a Dynamic Model of a Counterflow Compact Heat Exchanger for Simulation of the GT-MHR Recuperator using MATLAB and Simulink.” 2009. Web. 19 Apr 2019.

Vancouver:

Hawn DP. Development of a Dynamic Model of a Counterflow Compact Heat Exchanger for Simulation of the GT-MHR Recuperator using MATLAB and Simulink. [Internet] [Masters thesis]. The Ohio State University; 2009. [cited 2019 Apr 19]. Available from: http://rave.ohiolink.edu/etdc/view?acc_num=osu1236091152.

Council of Science Editors:

Hawn DP. Development of a Dynamic Model of a Counterflow Compact Heat Exchanger for Simulation of the GT-MHR Recuperator using MATLAB and Simulink. [Masters Thesis]. The Ohio State University; 2009. Available from: http://rave.ohiolink.edu/etdc/view?acc_num=osu1236091152


The Ohio State University

2. Khorsandi, Behrooz. Modeling of displacement damage in silicon carbide detectors resulting from neutron irradiation.

Degree: PhD, Nuclear Engineering, 2007, The Ohio State University

There is considerable interest in developing a power monitor system for Generation IV reactors (for instance GT-MHR). A new type of semiconductor radiation detector is under development based on silicon carbide (SiC) technology for these reactors. SiC has been selected as the semiconductor material due to its superior thermal-electrical-neutronic properties. Compared to Si, SiC is a radiation hard material; however, like Si, the properties of SiC are changed by irradiation by a large fluence of energetic neutrons, as a consequence of displacement damage, and that irradiation decreases the life-time of detectors. Predictions of displacement damage and the concomitant radiation effects are important for deciding where the SiC detectors should be placed. The purpose of this dissertation is to develop computer simulation methods to estimate the number of various defects created in SiC detectors, because of neutron irradiation, and predict at what positions of a reactor, SiC detectors could monitor the neutron flux with high reliability. The simulation modeling includes several well-known – and commercial – codes (MCNP5, TRIM, MARLOWE and VASP), and two kinetic Monte Carlo codes written by the author (MCASIC and DCRSIC). My dissertation will highlight the displacement damage that may happen in SiC detectors located in available positions in the OSURR, GT-MHR and IRIS. As extra modeling output data, the count rates of SiC for the specified locations are calculated. A conclusion of this thesis is SiC detectors that are placed in the thermal neutron region of a graphite moderator-reflector reactor have a chance to survive at least one reactor refueling cycle, while their count rates are acceptably high. Advisors/Committee Members: BLUE, Thomas (Advisor).

Subjects/Keywords: Engineering, Nuclear; Displacement damage; silicon carbide; Monte Carlo methids; count rate; GT-MHR; IRIS

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

APA (6th Edition):

Khorsandi, B. (2007). Modeling of displacement damage in silicon carbide detectors resulting from neutron irradiation. (Doctoral Dissertation). The Ohio State University. Retrieved from http://rave.ohiolink.edu/etdc/view?acc_num=osu1173103438

Chicago Manual of Style (16th Edition):

Khorsandi, Behrooz. “Modeling of displacement damage in silicon carbide detectors resulting from neutron irradiation.” 2007. Doctoral Dissertation, The Ohio State University. Accessed April 19, 2019. http://rave.ohiolink.edu/etdc/view?acc_num=osu1173103438.

MLA Handbook (7th Edition):

Khorsandi, Behrooz. “Modeling of displacement damage in silicon carbide detectors resulting from neutron irradiation.” 2007. Web. 19 Apr 2019.

Vancouver:

Khorsandi B. Modeling of displacement damage in silicon carbide detectors resulting from neutron irradiation. [Internet] [Doctoral dissertation]. The Ohio State University; 2007. [cited 2019 Apr 19]. Available from: http://rave.ohiolink.edu/etdc/view?acc_num=osu1173103438.

Council of Science Editors:

Khorsandi B. Modeling of displacement damage in silicon carbide detectors resulting from neutron irradiation. [Doctoral Dissertation]. The Ohio State University; 2007. Available from: http://rave.ohiolink.edu/etdc/view?acc_num=osu1173103438

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