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You searched for +publisher:"Georgia Tech" +contributor:("Petrovic, Bojan"). Showing records 1 – 30 of 66 total matches.

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Georgia Tech

1. Ulmer, Richard Marion. Benchmark description of an advanced burner test reactor and verification of COMET for whole core criticality analysis in fast reactors.

Degree: MS, Mechanical Engineering, 2014, Georgia Tech

 This work developed a stylized three dimensional benchmark problem based on Argonne National Laboratory's conceptual Advanced Burner Test Reactor design. This reactor is a sodium… (more)

Subjects/Keywords: ABTR; Heterogeneous benchmark; Hexagonal geometry; Whole-core 3D benchmark problem; Coarse mesh

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APA (6th Edition):

Ulmer, R. M. (2014). Benchmark description of an advanced burner test reactor and verification of COMET for whole core criticality analysis in fast reactors. (Masters Thesis). Georgia Tech. Retrieved from http://hdl.handle.net/1853/52222

Chicago Manual of Style (16th Edition):

Ulmer, Richard Marion. “Benchmark description of an advanced burner test reactor and verification of COMET for whole core criticality analysis in fast reactors.” 2014. Masters Thesis, Georgia Tech. Accessed April 22, 2019. http://hdl.handle.net/1853/52222.

MLA Handbook (7th Edition):

Ulmer, Richard Marion. “Benchmark description of an advanced burner test reactor and verification of COMET for whole core criticality analysis in fast reactors.” 2014. Web. 22 Apr 2019.

Vancouver:

Ulmer RM. Benchmark description of an advanced burner test reactor and verification of COMET for whole core criticality analysis in fast reactors. [Internet] [Masters thesis]. Georgia Tech; 2014. [cited 2019 Apr 22]. Available from: http://hdl.handle.net/1853/52222.

Council of Science Editors:

Ulmer RM. Benchmark description of an advanced burner test reactor and verification of COMET for whole core criticality analysis in fast reactors. [Masters Thesis]. Georgia Tech; 2014. Available from: http://hdl.handle.net/1853/52222


Georgia Tech

2. Kingsbury, Christopher W. Fuel cycle cost and fabrication model for fluoride-salt high-temperature reactor (FHR) "Plank" fuel design optimization.

Degree: MS, Mechanical Engineering, 2015, Georgia Tech

 The fluoride-salt-cooled high-temperature reactor (FHR) is a novel reactor design benefitting from passive safety features, high operating temperatures with corresponding high conversion efficiency, to name… (more)

Subjects/Keywords: Nuclear fuel design; Fuel cycle cost; Advanced high temperature reactors

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APA (6th Edition):

Kingsbury, C. W. (2015). Fuel cycle cost and fabrication model for fluoride-salt high-temperature reactor (FHR) "Plank" fuel design optimization. (Masters Thesis). Georgia Tech. Retrieved from http://hdl.handle.net/1853/54337

Chicago Manual of Style (16th Edition):

Kingsbury, Christopher W. “Fuel cycle cost and fabrication model for fluoride-salt high-temperature reactor (FHR) "Plank" fuel design optimization.” 2015. Masters Thesis, Georgia Tech. Accessed April 22, 2019. http://hdl.handle.net/1853/54337.

MLA Handbook (7th Edition):

Kingsbury, Christopher W. “Fuel cycle cost and fabrication model for fluoride-salt high-temperature reactor (FHR) "Plank" fuel design optimization.” 2015. Web. 22 Apr 2019.

Vancouver:

Kingsbury CW. Fuel cycle cost and fabrication model for fluoride-salt high-temperature reactor (FHR) "Plank" fuel design optimization. [Internet] [Masters thesis]. Georgia Tech; 2015. [cited 2019 Apr 22]. Available from: http://hdl.handle.net/1853/54337.

Council of Science Editors:

Kingsbury CW. Fuel cycle cost and fabrication model for fluoride-salt high-temperature reactor (FHR) "Plank" fuel design optimization. [Masters Thesis]. Georgia Tech; 2015. Available from: http://hdl.handle.net/1853/54337


Georgia Tech

3. Conant, Andrew. Sensitivity and Uncertainty Analysis of Plutonium and Cesium Isotope Ratios in BR3 Core 4A/B Fuel Rod.

Degree: MS, Mechanical Engineering, 2015, Georgia Tech

 The purpose of this research is to examine the effects of systematic uncertainty of reactor operating parameters on isotope ratios in spent fuel rods, specifically… (more)

Subjects/Keywords: uncertainty; plutonium; cesium; reactor; spent fuel

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APA (6th Edition):

Conant, A. (2015). Sensitivity and Uncertainty Analysis of Plutonium and Cesium Isotope Ratios in BR3 Core 4A/B Fuel Rod. (Masters Thesis). Georgia Tech. Retrieved from http://hdl.handle.net/1853/56227

Chicago Manual of Style (16th Edition):

Conant, Andrew. “Sensitivity and Uncertainty Analysis of Plutonium and Cesium Isotope Ratios in BR3 Core 4A/B Fuel Rod.” 2015. Masters Thesis, Georgia Tech. Accessed April 22, 2019. http://hdl.handle.net/1853/56227.

MLA Handbook (7th Edition):

Conant, Andrew. “Sensitivity and Uncertainty Analysis of Plutonium and Cesium Isotope Ratios in BR3 Core 4A/B Fuel Rod.” 2015. Web. 22 Apr 2019.

Vancouver:

Conant A. Sensitivity and Uncertainty Analysis of Plutonium and Cesium Isotope Ratios in BR3 Core 4A/B Fuel Rod. [Internet] [Masters thesis]. Georgia Tech; 2015. [cited 2019 Apr 22]. Available from: http://hdl.handle.net/1853/56227.

Council of Science Editors:

Conant A. Sensitivity and Uncertainty Analysis of Plutonium and Cesium Isotope Ratios in BR3 Core 4A/B Fuel Rod. [Masters Thesis]. Georgia Tech; 2015. Available from: http://hdl.handle.net/1853/56227


Georgia Tech

4. Remley, Kyle E. An adaptive COMET method.

Degree: MS, Mechanical Engineering, 2015, Georgia Tech

 This thesis presents a formulation for an adaptive COMET method for solving whole reactor eigenvalue and flux distribution problems using a varying flux expansion at… (more)

Subjects/Keywords: Transport; Computational; COMET

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APA (6th Edition):

Remley, K. E. (2015). An adaptive COMET method. (Masters Thesis). Georgia Tech. Retrieved from http://hdl.handle.net/1853/60395

Chicago Manual of Style (16th Edition):

Remley, Kyle E. “An adaptive COMET method.” 2015. Masters Thesis, Georgia Tech. Accessed April 22, 2019. http://hdl.handle.net/1853/60395.

MLA Handbook (7th Edition):

Remley, Kyle E. “An adaptive COMET method.” 2015. Web. 22 Apr 2019.

Vancouver:

Remley KE. An adaptive COMET method. [Internet] [Masters thesis]. Georgia Tech; 2015. [cited 2019 Apr 22]. Available from: http://hdl.handle.net/1853/60395.

Council of Science Editors:

Remley KE. An adaptive COMET method. [Masters Thesis]. Georgia Tech; 2015. Available from: http://hdl.handle.net/1853/60395


Georgia Tech

5. Piper, Nicholas A. Changes in ion orbit loss, intrinsic rotation, and particle pinch across the L-H transition in DIII-D plasmas.

Degree: MS, Mechanical Engineering, 2018, Georgia Tech

 Some thermalized ions flowing slowly radially outward have sufficient energy to access loss orbits which allow them to free stream out of the confined plasma… (more)

Subjects/Keywords: Ion orbit loss; Plasma; DIII-D; Particle pinch; Intrinsic rotation; Pinch velocity; Fusion

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APA (6th Edition):

Piper, N. A. (2018). Changes in ion orbit loss, intrinsic rotation, and particle pinch across the L-H transition in DIII-D plasmas. (Masters Thesis). Georgia Tech. Retrieved from http://hdl.handle.net/1853/60201

Chicago Manual of Style (16th Edition):

Piper, Nicholas A. “Changes in ion orbit loss, intrinsic rotation, and particle pinch across the L-H transition in DIII-D plasmas.” 2018. Masters Thesis, Georgia Tech. Accessed April 22, 2019. http://hdl.handle.net/1853/60201.

MLA Handbook (7th Edition):

Piper, Nicholas A. “Changes in ion orbit loss, intrinsic rotation, and particle pinch across the L-H transition in DIII-D plasmas.” 2018. Web. 22 Apr 2019.

Vancouver:

Piper NA. Changes in ion orbit loss, intrinsic rotation, and particle pinch across the L-H transition in DIII-D plasmas. [Internet] [Masters thesis]. Georgia Tech; 2018. [cited 2019 Apr 22]. Available from: http://hdl.handle.net/1853/60201.

Council of Science Editors:

Piper NA. Changes in ion orbit loss, intrinsic rotation, and particle pinch across the L-H transition in DIII-D plasmas. [Masters Thesis]. Georgia Tech; 2018. Available from: http://hdl.handle.net/1853/60201

6. Marquez, Matias G. Silicide fuel swelling behavior and its performance in I2S-LWR.

Degree: MS, Mechanical Engineering, 2015, Georgia Tech

 The swelling mechanisms of U3Si2 under neutron irradiation in reactor conditions are not unequivocally known. The limited experimental evidence that is available suggests that the… (more)

Subjects/Keywords: Silicide fuels; Swelling; Recrystallization; Grain subdivision; Nuclear fuel; Accident tolerant fuel; Advanced fuels; Rim effect; High burnup structure; Fuel performance

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APA (6th Edition):

Marquez, M. G. (2015). Silicide fuel swelling behavior and its performance in I2S-LWR. (Masters Thesis). Georgia Tech. Retrieved from http://hdl.handle.net/1853/53970

Chicago Manual of Style (16th Edition):

Marquez, Matias G. “Silicide fuel swelling behavior and its performance in I2S-LWR.” 2015. Masters Thesis, Georgia Tech. Accessed April 22, 2019. http://hdl.handle.net/1853/53970.

MLA Handbook (7th Edition):

Marquez, Matias G. “Silicide fuel swelling behavior and its performance in I2S-LWR.” 2015. Web. 22 Apr 2019.

Vancouver:

Marquez MG. Silicide fuel swelling behavior and its performance in I2S-LWR. [Internet] [Masters thesis]. Georgia Tech; 2015. [cited 2019 Apr 22]. Available from: http://hdl.handle.net/1853/53970.

Council of Science Editors:

Marquez MG. Silicide fuel swelling behavior and its performance in I2S-LWR. [Masters Thesis]. Georgia Tech; 2015. Available from: http://hdl.handle.net/1853/53970

7. Pereira, Gustavo Sigwalt Horn. Applying a nodal diffusion-micro depletion sequence for high-fidelity analysis of sodium cooled fast reactors.

Degree: MS, Mechanical Engineering, 2018, Georgia Tech

 Recent developments in the global nuclear industry have led to the need of reactor designs that are not only safe, but also address the challenges… (more)

Subjects/Keywords: Nodal diffusion; Nuclear; Fast reactors; Sodium-cooled reactors; Monte Carlo; DYN3D

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APA (6th Edition):

Pereira, G. S. H. (2018). Applying a nodal diffusion-micro depletion sequence for high-fidelity analysis of sodium cooled fast reactors. (Masters Thesis). Georgia Tech. Retrieved from http://hdl.handle.net/1853/60820

Chicago Manual of Style (16th Edition):

Pereira, Gustavo Sigwalt Horn. “Applying a nodal diffusion-micro depletion sequence for high-fidelity analysis of sodium cooled fast reactors.” 2018. Masters Thesis, Georgia Tech. Accessed April 22, 2019. http://hdl.handle.net/1853/60820.

MLA Handbook (7th Edition):

Pereira, Gustavo Sigwalt Horn. “Applying a nodal diffusion-micro depletion sequence for high-fidelity analysis of sodium cooled fast reactors.” 2018. Web. 22 Apr 2019.

Vancouver:

Pereira GSH. Applying a nodal diffusion-micro depletion sequence for high-fidelity analysis of sodium cooled fast reactors. [Internet] [Masters thesis]. Georgia Tech; 2018. [cited 2019 Apr 22]. Available from: http://hdl.handle.net/1853/60820.

Council of Science Editors:

Pereira GSH. Applying a nodal diffusion-micro depletion sequence for high-fidelity analysis of sodium cooled fast reactors. [Masters Thesis]. Georgia Tech; 2018. Available from: http://hdl.handle.net/1853/60820


Georgia Tech

8. Fehr, Brandon M. Detailed study of the transient rod pneumatic system on the annular core research reactor.

Degree: MS, Mechanical Engineering, 2016, Georgia Tech

 Throughout the history of the Annular Core Research Reactor (ACRR), Transient Rod (TR) A has experienced an increased rate of failure versus the other two… (more)

Subjects/Keywords: ACRR; Sandia National Laboratories; SNL; Transient rod; TRIGA

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APA (6th Edition):

Fehr, B. M. (2016). Detailed study of the transient rod pneumatic system on the annular core research reactor. (Masters Thesis). Georgia Tech. Retrieved from http://hdl.handle.net/1853/55032

Chicago Manual of Style (16th Edition):

Fehr, Brandon M. “Detailed study of the transient rod pneumatic system on the annular core research reactor.” 2016. Masters Thesis, Georgia Tech. Accessed April 22, 2019. http://hdl.handle.net/1853/55032.

MLA Handbook (7th Edition):

Fehr, Brandon M. “Detailed study of the transient rod pneumatic system on the annular core research reactor.” 2016. Web. 22 Apr 2019.

Vancouver:

Fehr BM. Detailed study of the transient rod pneumatic system on the annular core research reactor. [Internet] [Masters thesis]. Georgia Tech; 2016. [cited 2019 Apr 22]. Available from: http://hdl.handle.net/1853/55032.

Council of Science Editors:

Fehr BM. Detailed study of the transient rod pneumatic system on the annular core research reactor. [Masters Thesis]. Georgia Tech; 2016. Available from: http://hdl.handle.net/1853/55032


Georgia Tech

9. Burns, Joseph R. Reactivity control of a PWR 19x19 uranium silicide fuel assembly.

Degree: MS, Mechanical Engineering, 2015, Georgia Tech

 The Integral Inherently Safe Light Water Reactor (I2S-LWR) is a novel reactor concept which aims to apply safety-promoting features typical of small modular reactors (SMRs)… (more)

Subjects/Keywords: Reactivity control; Uranium silicide

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APA (6th Edition):

Burns, J. R. (2015). Reactivity control of a PWR 19x19 uranium silicide fuel assembly. (Masters Thesis). Georgia Tech. Retrieved from http://hdl.handle.net/1853/53975

Chicago Manual of Style (16th Edition):

Burns, Joseph R. “Reactivity control of a PWR 19x19 uranium silicide fuel assembly.” 2015. Masters Thesis, Georgia Tech. Accessed April 22, 2019. http://hdl.handle.net/1853/53975.

MLA Handbook (7th Edition):

Burns, Joseph R. “Reactivity control of a PWR 19x19 uranium silicide fuel assembly.” 2015. Web. 22 Apr 2019.

Vancouver:

Burns JR. Reactivity control of a PWR 19x19 uranium silicide fuel assembly. [Internet] [Masters thesis]. Georgia Tech; 2015. [cited 2019 Apr 22]. Available from: http://hdl.handle.net/1853/53975.

Council of Science Editors:

Burns JR. Reactivity control of a PWR 19x19 uranium silicide fuel assembly. [Masters Thesis]. Georgia Tech; 2015. Available from: http://hdl.handle.net/1853/53975


Georgia Tech

10. Shi, Bo. Entropy-based diagnostics of criticality Monte Carlo simulation and higher eigenmode acceleration methodology.

Degree: MS, Nuclear and Radiological Engineering, 2010, Georgia Tech

 Because of the accuracy and ease of implementation, Monte Carlo methodology is widely used in analysis of nuclear systems. The obtained estimate of the multiplication… (more)

Subjects/Keywords: Monte Carlo; Convergence diagnositics; Eigenmode acceleration; Criticality (Nuclear engineering); Monte Carlo method; Convergence; Eigenfunctions

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APA (6th Edition):

Shi, B. (2010). Entropy-based diagnostics of criticality Monte Carlo simulation and higher eigenmode acceleration methodology. (Masters Thesis). Georgia Tech. Retrieved from http://hdl.handle.net/1853/34788

Chicago Manual of Style (16th Edition):

Shi, Bo. “Entropy-based diagnostics of criticality Monte Carlo simulation and higher eigenmode acceleration methodology.” 2010. Masters Thesis, Georgia Tech. Accessed April 22, 2019. http://hdl.handle.net/1853/34788.

MLA Handbook (7th Edition):

Shi, Bo. “Entropy-based diagnostics of criticality Monte Carlo simulation and higher eigenmode acceleration methodology.” 2010. Web. 22 Apr 2019.

Vancouver:

Shi B. Entropy-based diagnostics of criticality Monte Carlo simulation and higher eigenmode acceleration methodology. [Internet] [Masters thesis]. Georgia Tech; 2010. [cited 2019 Apr 22]. Available from: http://hdl.handle.net/1853/34788.

Council of Science Editors:

Shi B. Entropy-based diagnostics of criticality Monte Carlo simulation and higher eigenmode acceleration methodology. [Masters Thesis]. Georgia Tech; 2010. Available from: http://hdl.handle.net/1853/34788


Georgia Tech

11. McKillop, Jordan M. Reducing the activation of the IRIS reactor building using the SCALE/MAVRIC methodology.

Degree: MS, Nuclear and Radiological Engineering, 2009, Georgia Tech

 The main objective of this research is: (1) to develop a model and perform numerical simulations to evaluate the radiation field and the resulting dose… (more)

Subjects/Keywords: IRIS; Radiation protection and shielding; Nuclear power plants; Radiation Measurement; Nuclear power plants Decommissioning; Pressurized water reactors

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APA (6th Edition):

McKillop, J. M. (2009). Reducing the activation of the IRIS reactor building using the SCALE/MAVRIC methodology. (Masters Thesis). Georgia Tech. Retrieved from http://hdl.handle.net/1853/37209

Chicago Manual of Style (16th Edition):

McKillop, Jordan M. “Reducing the activation of the IRIS reactor building using the SCALE/MAVRIC methodology.” 2009. Masters Thesis, Georgia Tech. Accessed April 22, 2019. http://hdl.handle.net/1853/37209.

MLA Handbook (7th Edition):

McKillop, Jordan M. “Reducing the activation of the IRIS reactor building using the SCALE/MAVRIC methodology.” 2009. Web. 22 Apr 2019.

Vancouver:

McKillop JM. Reducing the activation of the IRIS reactor building using the SCALE/MAVRIC methodology. [Internet] [Masters thesis]. Georgia Tech; 2009. [cited 2019 Apr 22]. Available from: http://hdl.handle.net/1853/37209.

Council of Science Editors:

McKillop JM. Reducing the activation of the IRIS reactor building using the SCALE/MAVRIC methodology. [Masters Thesis]. Georgia Tech; 2009. Available from: http://hdl.handle.net/1853/37209


Georgia Tech

12. Ryckman, Jeffrey M. Using MCNPX to calculate primary and secondary dose in proton therapy.

Degree: MS, Medical Physics, 2011, Georgia Tech

 Proton therapy is a relatively new treatment modality for cancer, having recently been incorporated into hospitals in the last two decades. Although proton therapy has… (more)

Subjects/Keywords: Proton therapy; MCNPX; Dose caculation; High performance computing; Medical physics; History of proton therapy; MIRD phantom; Neutron dose contamination; Secondary dose; Primary dose; CMPWG; Nozzle everything upstream; NEU; Mesh tally; Protons; Protons Scattering; Proton beams Therapeutic use; Cancer Research; Cancer Treatment Technological innovations

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APA (6th Edition):

Ryckman, J. M. (2011). Using MCNPX to calculate primary and secondary dose in proton therapy. (Masters Thesis). Georgia Tech. Retrieved from http://hdl.handle.net/1853/39499

Chicago Manual of Style (16th Edition):

Ryckman, Jeffrey M. “Using MCNPX to calculate primary and secondary dose in proton therapy.” 2011. Masters Thesis, Georgia Tech. Accessed April 22, 2019. http://hdl.handle.net/1853/39499.

MLA Handbook (7th Edition):

Ryckman, Jeffrey M. “Using MCNPX to calculate primary and secondary dose in proton therapy.” 2011. Web. 22 Apr 2019.

Vancouver:

Ryckman JM. Using MCNPX to calculate primary and secondary dose in proton therapy. [Internet] [Masters thesis]. Georgia Tech; 2011. [cited 2019 Apr 22]. Available from: http://hdl.handle.net/1853/39499.

Council of Science Editors:

Ryckman JM. Using MCNPX to calculate primary and secondary dose in proton therapy. [Masters Thesis]. Georgia Tech; 2011. Available from: http://hdl.handle.net/1853/39499


Georgia Tech

13. Zhang, Zhan. Neutron energy spectrum reconstruction method based for htr reactor calculations.

Degree: MS, Mechanical Engineering, 2011, Georgia Tech

 In the deep burn research of Very High Temperature Reactor (VHTR), it is desired to make an accurate estimation of absorption cross sections and absorption… (more)

Subjects/Keywords: Energy spectrum; Burnable poison; VHTR; Cross section; Fuel burnup (Nuclear engineering); Neutrons Spectra

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APA (6th Edition):

Zhang, Z. (2011). Neutron energy spectrum reconstruction method based for htr reactor calculations. (Masters Thesis). Georgia Tech. Retrieved from http://hdl.handle.net/1853/41195

Chicago Manual of Style (16th Edition):

Zhang, Zhan. “Neutron energy spectrum reconstruction method based for htr reactor calculations.” 2011. Masters Thesis, Georgia Tech. Accessed April 22, 2019. http://hdl.handle.net/1853/41195.

MLA Handbook (7th Edition):

Zhang, Zhan. “Neutron energy spectrum reconstruction method based for htr reactor calculations.” 2011. Web. 22 Apr 2019.

Vancouver:

Zhang Z. Neutron energy spectrum reconstruction method based for htr reactor calculations. [Internet] [Masters thesis]. Georgia Tech; 2011. [cited 2019 Apr 22]. Available from: http://hdl.handle.net/1853/41195.

Council of Science Editors:

Zhang Z. Neutron energy spectrum reconstruction method based for htr reactor calculations. [Masters Thesis]. Georgia Tech; 2011. Available from: http://hdl.handle.net/1853/41195


Georgia Tech

14. Remley, Kyle E. Development of methods for high performance computing applications of the deterministic stage of comet calculations.

Degree: PhD, Mechanical Engineering, 2016, Georgia Tech

 The Coarse Mesh Radiation Transport (COMET) method is a reactor physics method and code that has been used to solve whole core reactor eigenvalue and… (more)

Subjects/Keywords: Coarse mesh transport; Parallel computing; Reactor physics

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APA (6th Edition):

Remley, K. E. (2016). Development of methods for high performance computing applications of the deterministic stage of comet calculations. (Doctoral Dissertation). Georgia Tech. Retrieved from http://hdl.handle.net/1853/58610

Chicago Manual of Style (16th Edition):

Remley, Kyle E. “Development of methods for high performance computing applications of the deterministic stage of comet calculations.” 2016. Doctoral Dissertation, Georgia Tech. Accessed April 22, 2019. http://hdl.handle.net/1853/58610.

MLA Handbook (7th Edition):

Remley, Kyle E. “Development of methods for high performance computing applications of the deterministic stage of comet calculations.” 2016. Web. 22 Apr 2019.

Vancouver:

Remley KE. Development of methods for high performance computing applications of the deterministic stage of comet calculations. [Internet] [Doctoral dissertation]. Georgia Tech; 2016. [cited 2019 Apr 22]. Available from: http://hdl.handle.net/1853/58610.

Council of Science Editors:

Remley KE. Development of methods for high performance computing applications of the deterministic stage of comet calculations. [Doctoral Dissertation]. Georgia Tech; 2016. Available from: http://hdl.handle.net/1853/58610


Georgia Tech

15. Hon, Ryan Paul. Development of methods and tools for on-the-fly response function generation for criticality calculations.

Degree: PhD, Mechanical Engineering, 2016, Georgia Tech

 Stochastic Particle Response Calculator, SPaRC, is a new stochastic neutron transport code that has been developed and optimized for the computation of response functions for… (more)

Subjects/Keywords: Neutron transport

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APA (6th Edition):

Hon, R. P. (2016). Development of methods and tools for on-the-fly response function generation for criticality calculations. (Doctoral Dissertation). Georgia Tech. Retrieved from http://hdl.handle.net/1853/58184

Chicago Manual of Style (16th Edition):

Hon, Ryan Paul. “Development of methods and tools for on-the-fly response function generation for criticality calculations.” 2016. Doctoral Dissertation, Georgia Tech. Accessed April 22, 2019. http://hdl.handle.net/1853/58184.

MLA Handbook (7th Edition):

Hon, Ryan Paul. “Development of methods and tools for on-the-fly response function generation for criticality calculations.” 2016. Web. 22 Apr 2019.

Vancouver:

Hon RP. Development of methods and tools for on-the-fly response function generation for criticality calculations. [Internet] [Doctoral dissertation]. Georgia Tech; 2016. [cited 2019 Apr 22]. Available from: http://hdl.handle.net/1853/58184.

Council of Science Editors:

Hon RP. Development of methods and tools for on-the-fly response function generation for criticality calculations. [Doctoral Dissertation]. Georgia Tech; 2016. Available from: http://hdl.handle.net/1853/58184


Georgia Tech

16. Blaylock, Dwayne Patrick. Measurement of spallation residuals in mercury for accelerator facility targets.

Degree: PhD, Mechanical Engineering, 2016, Georgia Tech

 A benchmark experiment was designed and conducted that irradiated two small volume mercury targets at the Weapon Neutron Research facility at the Los Alamos Neutron… (more)

Subjects/Keywords: Spallation; Production cross-section; MCNPX; Mercury

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APA (6th Edition):

Blaylock, D. P. (2016). Measurement of spallation residuals in mercury for accelerator facility targets. (Doctoral Dissertation). Georgia Tech. Retrieved from http://hdl.handle.net/1853/54977

Chicago Manual of Style (16th Edition):

Blaylock, Dwayne Patrick. “Measurement of spallation residuals in mercury for accelerator facility targets.” 2016. Doctoral Dissertation, Georgia Tech. Accessed April 22, 2019. http://hdl.handle.net/1853/54977.

MLA Handbook (7th Edition):

Blaylock, Dwayne Patrick. “Measurement of spallation residuals in mercury for accelerator facility targets.” 2016. Web. 22 Apr 2019.

Vancouver:

Blaylock DP. Measurement of spallation residuals in mercury for accelerator facility targets. [Internet] [Doctoral dissertation]. Georgia Tech; 2016. [cited 2019 Apr 22]. Available from: http://hdl.handle.net/1853/54977.

Council of Science Editors:

Blaylock DP. Measurement of spallation residuals in mercury for accelerator facility targets. [Doctoral Dissertation]. Georgia Tech; 2016. Available from: http://hdl.handle.net/1853/54977


Georgia Tech

17. Wilks, Theresa M. Calculation of the radial electric field in the DIII-D tokamak edge plasma.

Degree: PhD, Mechanical Engineering, 2016, Georgia Tech

 The application of a theoretical framework for calculating the radial electric field in the DIII-D tokamak edge plasma is discussed. Changes in the radial electric… (more)

Subjects/Keywords: Fusion; Plasma physics; Edge pedestal; Radial electric field; Ion orbit loss

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APA (6th Edition):

Wilks, T. M. (2016). Calculation of the radial electric field in the DIII-D tokamak edge plasma. (Doctoral Dissertation). Georgia Tech. Retrieved from http://hdl.handle.net/1853/54988

Chicago Manual of Style (16th Edition):

Wilks, Theresa M. “Calculation of the radial electric field in the DIII-D tokamak edge plasma.” 2016. Doctoral Dissertation, Georgia Tech. Accessed April 22, 2019. http://hdl.handle.net/1853/54988.

MLA Handbook (7th Edition):

Wilks, Theresa M. “Calculation of the radial electric field in the DIII-D tokamak edge plasma.” 2016. Web. 22 Apr 2019.

Vancouver:

Wilks TM. Calculation of the radial electric field in the DIII-D tokamak edge plasma. [Internet] [Doctoral dissertation]. Georgia Tech; 2016. [cited 2019 Apr 22]. Available from: http://hdl.handle.net/1853/54988.

Council of Science Editors:

Wilks TM. Calculation of the radial electric field in the DIII-D tokamak edge plasma. [Doctoral Dissertation]. Georgia Tech; 2016. Available from: http://hdl.handle.net/1853/54988


Georgia Tech

18. Douglass, Steven James. Consistent energy treatment for radiation transport methods.

Degree: PhD, Nuclear Engineering, 2012, Georgia Tech

 A condensed multigroup formulation is developed which maintains direct consistency with the continuous energy or fine-group structure, exhibiting the accuracy of the detailed energy spectrum… (more)

Subjects/Keywords: Neutron transport theory; Subgroup decomposition; Cross section condensation; Consistent multigroup method; Radiative transfer; Transport theory

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APA (6th Edition):

Douglass, S. J. (2012). Consistent energy treatment for radiation transport methods. (Doctoral Dissertation). Georgia Tech. Retrieved from http://hdl.handle.net/1853/47612

Chicago Manual of Style (16th Edition):

Douglass, Steven James. “Consistent energy treatment for radiation transport methods.” 2012. Doctoral Dissertation, Georgia Tech. Accessed April 22, 2019. http://hdl.handle.net/1853/47612.

MLA Handbook (7th Edition):

Douglass, Steven James. “Consistent energy treatment for radiation transport methods.” 2012. Web. 22 Apr 2019.

Vancouver:

Douglass SJ. Consistent energy treatment for radiation transport methods. [Internet] [Doctoral dissertation]. Georgia Tech; 2012. [cited 2019 Apr 22]. Available from: http://hdl.handle.net/1853/47612.

Council of Science Editors:

Douglass SJ. Consistent energy treatment for radiation transport methods. [Doctoral Dissertation]. Georgia Tech; 2012. Available from: http://hdl.handle.net/1853/47612


Georgia Tech

19. Yasseri, Saam. Generalized spatial homogenization method in transport theory and high order diffusion theory energy recondensation methods.

Degree: PhD, Nuclear and Radiological Engineering, 2013, Georgia Tech

 In this dissertation, three different methods for solving the Boltzmann neutron transport equation (and its low-order approximations) are developed in general geometry and implemented in… (more)

Subjects/Keywords: High-order diffusion theory; Transport spatial homogenization; Energy condensation; Neutron transport theory; Diffusion

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APA (6th Edition):

Yasseri, S. (2013). Generalized spatial homogenization method in transport theory and high order diffusion theory energy recondensation methods. (Doctoral Dissertation). Georgia Tech. Retrieved from http://hdl.handle.net/1853/51727

Chicago Manual of Style (16th Edition):

Yasseri, Saam. “Generalized spatial homogenization method in transport theory and high order diffusion theory energy recondensation methods.” 2013. Doctoral Dissertation, Georgia Tech. Accessed April 22, 2019. http://hdl.handle.net/1853/51727.

MLA Handbook (7th Edition):

Yasseri, Saam. “Generalized spatial homogenization method in transport theory and high order diffusion theory energy recondensation methods.” 2013. Web. 22 Apr 2019.

Vancouver:

Yasseri S. Generalized spatial homogenization method in transport theory and high order diffusion theory energy recondensation methods. [Internet] [Doctoral dissertation]. Georgia Tech; 2013. [cited 2019 Apr 22]. Available from: http://hdl.handle.net/1853/51727.

Council of Science Editors:

Yasseri S. Generalized spatial homogenization method in transport theory and high order diffusion theory energy recondensation methods. [Doctoral Dissertation]. Georgia Tech; 2013. Available from: http://hdl.handle.net/1853/51727


Georgia Tech

20. Griffin, Daniel J. A framework for understanding and controlling batch cooling crystallization.

Degree: PhD, Chemical and Biomolecular Engineering, 2016, Georgia Tech

 In taking a different view of crystallization dynamics, this thesis reveals a new framework for addressing a prevalent process engineering challenge: control over the size… (more)

Subjects/Keywords: Batch cooling crystallization; Crystal size control; Process analytical technology; Mass-count plot; Focused beam reflectance measurements; FBRM; Attenuated total reflectance Fourier transform infrared; ATR-FTIRpopulation balance; Population balance; Dynamic programming; Optimal control; Model predictive control; Machine learning; Learning from datadata-driven learning; Data-driven learning; Feedback control

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APA (6th Edition):

Griffin, D. J. (2016). A framework for understanding and controlling batch cooling crystallization. (Doctoral Dissertation). Georgia Tech. Retrieved from http://hdl.handle.net/1853/55619

Chicago Manual of Style (16th Edition):

Griffin, Daniel J. “A framework for understanding and controlling batch cooling crystallization.” 2016. Doctoral Dissertation, Georgia Tech. Accessed April 22, 2019. http://hdl.handle.net/1853/55619.

MLA Handbook (7th Edition):

Griffin, Daniel J. “A framework for understanding and controlling batch cooling crystallization.” 2016. Web. 22 Apr 2019.

Vancouver:

Griffin DJ. A framework for understanding and controlling batch cooling crystallization. [Internet] [Doctoral dissertation]. Georgia Tech; 2016. [cited 2019 Apr 22]. Available from: http://hdl.handle.net/1853/55619.

Council of Science Editors:

Griffin DJ. A framework for understanding and controlling batch cooling crystallization. [Doctoral Dissertation]. Georgia Tech; 2016. Available from: http://hdl.handle.net/1853/55619


Georgia Tech

21. Abou Jaoude, Abdalla. Design of a mixed-spectrum long-lived reactor with improved proliferation resistance.

Degree: PhD, Mechanical Engineering, 2017, Georgia Tech

 Long-lived fast reactors have been suggested as an effective way of spreading nuclear energy to new countries. These small reactors can be produced at centralized… (more)

Subjects/Keywords: Reactor physics; Proliferation resistance; Mixed-spectrum reactors; Reactor design; Safety evaluation

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APA (6th Edition):

Abou Jaoude, A. (2017). Design of a mixed-spectrum long-lived reactor with improved proliferation resistance. (Doctoral Dissertation). Georgia Tech. Retrieved from http://hdl.handle.net/1853/59275

Chicago Manual of Style (16th Edition):

Abou Jaoude, Abdalla. “Design of a mixed-spectrum long-lived reactor with improved proliferation resistance.” 2017. Doctoral Dissertation, Georgia Tech. Accessed April 22, 2019. http://hdl.handle.net/1853/59275.

MLA Handbook (7th Edition):

Abou Jaoude, Abdalla. “Design of a mixed-spectrum long-lived reactor with improved proliferation resistance.” 2017. Web. 22 Apr 2019.

Vancouver:

Abou Jaoude A. Design of a mixed-spectrum long-lived reactor with improved proliferation resistance. [Internet] [Doctoral dissertation]. Georgia Tech; 2017. [cited 2019 Apr 22]. Available from: http://hdl.handle.net/1853/59275.

Council of Science Editors:

Abou Jaoude A. Design of a mixed-spectrum long-lived reactor with improved proliferation resistance. [Doctoral Dissertation]. Georgia Tech; 2017. Available from: http://hdl.handle.net/1853/59275


Georgia Tech

22. Hoffman, Richard. Kinetic Monte Carlo simulations of defect evolution in materials under irradiation by energetic particles.

Degree: PhD, Mechanical Engineering, 2016, Georgia Tech

 Five KMC models are created using the SPPARKS code in order to examine the behavior of materials related to nuclear applications on the mesoscale. In… (more)

Subjects/Keywords: Kinetic Monte Carlo; Nuclear materials

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APA (6th Edition):

Hoffman, R. (2016). Kinetic Monte Carlo simulations of defect evolution in materials under irradiation by energetic particles. (Doctoral Dissertation). Georgia Tech. Retrieved from http://hdl.handle.net/1853/59158

Chicago Manual of Style (16th Edition):

Hoffman, Richard. “Kinetic Monte Carlo simulations of defect evolution in materials under irradiation by energetic particles.” 2016. Doctoral Dissertation, Georgia Tech. Accessed April 22, 2019. http://hdl.handle.net/1853/59158.

MLA Handbook (7th Edition):

Hoffman, Richard. “Kinetic Monte Carlo simulations of defect evolution in materials under irradiation by energetic particles.” 2016. Web. 22 Apr 2019.

Vancouver:

Hoffman R. Kinetic Monte Carlo simulations of defect evolution in materials under irradiation by energetic particles. [Internet] [Doctoral dissertation]. Georgia Tech; 2016. [cited 2019 Apr 22]. Available from: http://hdl.handle.net/1853/59158.

Council of Science Editors:

Hoffman R. Kinetic Monte Carlo simulations of defect evolution in materials under irradiation by energetic particles. [Doctoral Dissertation]. Georgia Tech; 2016. Available from: http://hdl.handle.net/1853/59158


Georgia Tech

23. Kooreman, Gabriel. Iterative homogenization method for improving computational efficiency in solving eigenvalue problems in neutron transport.

Degree: PhD, Mechanical Engineering, 2016, Georgia Tech

 The neutron transport equation often is homogenized in order to simplify its solution procedure in some manner or another. There exist many methods for homogenizing… (more)

Subjects/Keywords: Neutron transport; Homogenization; Diffusion; Eigenvalue calculation; Reactor physics

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APA (6th Edition):

Kooreman, G. (2016). Iterative homogenization method for improving computational efficiency in solving eigenvalue problems in neutron transport. (Doctoral Dissertation). Georgia Tech. Retrieved from http://hdl.handle.net/1853/59134

Chicago Manual of Style (16th Edition):

Kooreman, Gabriel. “Iterative homogenization method for improving computational efficiency in solving eigenvalue problems in neutron transport.” 2016. Doctoral Dissertation, Georgia Tech. Accessed April 22, 2019. http://hdl.handle.net/1853/59134.

MLA Handbook (7th Edition):

Kooreman, Gabriel. “Iterative homogenization method for improving computational efficiency in solving eigenvalue problems in neutron transport.” 2016. Web. 22 Apr 2019.

Vancouver:

Kooreman G. Iterative homogenization method for improving computational efficiency in solving eigenvalue problems in neutron transport. [Internet] [Doctoral dissertation]. Georgia Tech; 2016. [cited 2019 Apr 22]. Available from: http://hdl.handle.net/1853/59134.

Council of Science Editors:

Kooreman G. Iterative homogenization method for improving computational efficiency in solving eigenvalue problems in neutron transport. [Doctoral Dissertation]. Georgia Tech; 2016. Available from: http://hdl.handle.net/1853/59134

24. Winter, Thomas Christopher. Comparison of fission gas swelling models for amorphous u₃si₂ and crystalline uo₂.

Degree: MS, Mechanical Engineering, 2016, Georgia Tech

 Theoretical models are used in support of the I2S-LWR (Integral Inherently Safe LWR) project for a direct comparison of fuel swelling and fission gas bubble… (more)

Subjects/Keywords: Fission gas swelling; Fuel swelling; Uranium silicide; Nuclear fuel swelling; Fission gas evolution; Swelling model; Nuclear fuel

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APA (6th Edition):

Winter, T. C. (2016). Comparison of fission gas swelling models for amorphous u₃si₂ and crystalline uo₂. (Masters Thesis). Georgia Tech. Retrieved from http://hdl.handle.net/1853/54991

Chicago Manual of Style (16th Edition):

Winter, Thomas Christopher. “Comparison of fission gas swelling models for amorphous u₃si₂ and crystalline uo₂.” 2016. Masters Thesis, Georgia Tech. Accessed April 22, 2019. http://hdl.handle.net/1853/54991.

MLA Handbook (7th Edition):

Winter, Thomas Christopher. “Comparison of fission gas swelling models for amorphous u₃si₂ and crystalline uo₂.” 2016. Web. 22 Apr 2019.

Vancouver:

Winter TC. Comparison of fission gas swelling models for amorphous u₃si₂ and crystalline uo₂. [Internet] [Masters thesis]. Georgia Tech; 2016. [cited 2019 Apr 22]. Available from: http://hdl.handle.net/1853/54991.

Council of Science Editors:

Winter TC. Comparison of fission gas swelling models for amorphous u₃si₂ and crystalline uo₂. [Masters Thesis]. Georgia Tech; 2016. Available from: http://hdl.handle.net/1853/54991

25. Collart, Timothy Gerard. Comparison of the effects of realistic flux surface models on calculations of plasma asymmetries in DIII-D.

Degree: MS, Mechanical Engineering, 2015, Georgia Tech

 Several methods are presented for improving upon the traditional analytic “circular” method for constructing a flux-surface aligned curvilinear coordinate system representation of equilibrium plasma geometry… (more)

Subjects/Keywords: Curvilinear coordinate systems; Plasma; Tokamak; DIII-D; Neoclassical; Flux-surface; Curvilinear coordinate systems

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APA (6th Edition):

Collart, T. G. (2015). Comparison of the effects of realistic flux surface models on calculations of plasma asymmetries in DIII-D. (Masters Thesis). Georgia Tech. Retrieved from http://hdl.handle.net/1853/54351

Chicago Manual of Style (16th Edition):

Collart, Timothy Gerard. “Comparison of the effects of realistic flux surface models on calculations of plasma asymmetries in DIII-D.” 2015. Masters Thesis, Georgia Tech. Accessed April 22, 2019. http://hdl.handle.net/1853/54351.

MLA Handbook (7th Edition):

Collart, Timothy Gerard. “Comparison of the effects of realistic flux surface models on calculations of plasma asymmetries in DIII-D.” 2015. Web. 22 Apr 2019.

Vancouver:

Collart TG. Comparison of the effects of realistic flux surface models on calculations of plasma asymmetries in DIII-D. [Internet] [Masters thesis]. Georgia Tech; 2015. [cited 2019 Apr 22]. Available from: http://hdl.handle.net/1853/54351.

Council of Science Editors:

Collart TG. Comparison of the effects of realistic flux surface models on calculations of plasma asymmetries in DIII-D. [Masters Thesis]. Georgia Tech; 2015. Available from: http://hdl.handle.net/1853/54351

26. Koch, David. Investigation and improvement of criticality calculations in MCNP5 involving Shannon entropy convergence.

Degree: MS, Mechanical Engineering, 2014, Georgia Tech

 Criticality calculations are often performed in MCNP5 using the Shannon entropy as an indicator of source convergence for the given neutron transport problem. The Shannon… (more)

Subjects/Keywords: Monte Carlo; MCNP5; Shannon entropy; Criticality calculations; K-eff; Conergence criteria

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APA (6th Edition):

Koch, D. (2014). Investigation and improvement of criticality calculations in MCNP5 involving Shannon entropy convergence. (Masters Thesis). Georgia Tech. Retrieved from http://hdl.handle.net/1853/53484

Chicago Manual of Style (16th Edition):

Koch, David. “Investigation and improvement of criticality calculations in MCNP5 involving Shannon entropy convergence.” 2014. Masters Thesis, Georgia Tech. Accessed April 22, 2019. http://hdl.handle.net/1853/53484.

MLA Handbook (7th Edition):

Koch, David. “Investigation and improvement of criticality calculations in MCNP5 involving Shannon entropy convergence.” 2014. Web. 22 Apr 2019.

Vancouver:

Koch D. Investigation and improvement of criticality calculations in MCNP5 involving Shannon entropy convergence. [Internet] [Masters thesis]. Georgia Tech; 2014. [cited 2019 Apr 22]. Available from: http://hdl.handle.net/1853/53484.

Council of Science Editors:

Koch D. Investigation and improvement of criticality calculations in MCNP5 involving Shannon entropy convergence. [Masters Thesis]. Georgia Tech; 2014. Available from: http://hdl.handle.net/1853/53484

27. Kooreman, Gabriel. Consistent hybrid diffusion-transport spatial homogenization method.

Degree: MS, Mechanical Engineering, 2013, Georgia Tech

 Recent work by Yasseri and Rahnema has introduced a consistent spatial homogenization (CSH) method completely in transport theory. The CSH method can very accurately reproduce… (more)

Subjects/Keywords: Reactor physics; Neutronics; Neutron transport; Diffusion; Homogenization

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APA (6th Edition):

Kooreman, G. (2013). Consistent hybrid diffusion-transport spatial homogenization method. (Masters Thesis). Georgia Tech. Retrieved from http://hdl.handle.net/1853/52950

Chicago Manual of Style (16th Edition):

Kooreman, Gabriel. “Consistent hybrid diffusion-transport spatial homogenization method.” 2013. Masters Thesis, Georgia Tech. Accessed April 22, 2019. http://hdl.handle.net/1853/52950.

MLA Handbook (7th Edition):

Kooreman, Gabriel. “Consistent hybrid diffusion-transport spatial homogenization method.” 2013. Web. 22 Apr 2019.

Vancouver:

Kooreman G. Consistent hybrid diffusion-transport spatial homogenization method. [Internet] [Masters thesis]. Georgia Tech; 2013. [cited 2019 Apr 22]. Available from: http://hdl.handle.net/1853/52950.

Council of Science Editors:

Kooreman G. Consistent hybrid diffusion-transport spatial homogenization method. [Masters Thesis]. Georgia Tech; 2013. Available from: http://hdl.handle.net/1853/52950

28. Holcomb, Andrew M. Development of a graphical user interface for the coarse mesh radiation transport code COMET and cross section generation with HELIOS.

Degree: MS, Mechanical Engineering, 2013, Georgia Tech

 The coarse mesh radiation transport (COMET) code uses response functions to solve the neutron transport equation. Most nuclear codes used today have a very steep… (more)

Subjects/Keywords: Cross section generation; HELIOS; Graphical user interface

…Modular High Temperature Gas Reactor) benchmark problem under development at Georgia Tech… 

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APA (6th Edition):

Holcomb, A. M. (2013). Development of a graphical user interface for the coarse mesh radiation transport code COMET and cross section generation with HELIOS. (Masters Thesis). Georgia Tech. Retrieved from http://hdl.handle.net/1853/52952

Chicago Manual of Style (16th Edition):

Holcomb, Andrew M. “Development of a graphical user interface for the coarse mesh radiation transport code COMET and cross section generation with HELIOS.” 2013. Masters Thesis, Georgia Tech. Accessed April 22, 2019. http://hdl.handle.net/1853/52952.

MLA Handbook (7th Edition):

Holcomb, Andrew M. “Development of a graphical user interface for the coarse mesh radiation transport code COMET and cross section generation with HELIOS.” 2013. Web. 22 Apr 2019.

Vancouver:

Holcomb AM. Development of a graphical user interface for the coarse mesh radiation transport code COMET and cross section generation with HELIOS. [Internet] [Masters thesis]. Georgia Tech; 2013. [cited 2019 Apr 22]. Available from: http://hdl.handle.net/1853/52952.

Council of Science Editors:

Holcomb AM. Development of a graphical user interface for the coarse mesh radiation transport code COMET and cross section generation with HELIOS. [Masters Thesis]. Georgia Tech; 2013. Available from: http://hdl.handle.net/1853/52952

29. Chapman, Christopher Weeks. The MANE process of generating continuous energy hot-operating temperature cross sections.

Degree: MS, Mechanical Engineering, 2014, Georgia Tech

 MANE (MCNP ACE from NJOY & ENDF), a code for generating continuous energy cross sections at arbitrary temperatures, was created. Cross sections were evaluated using… (more)

Subjects/Keywords: Cross section generation; NJOY; Whole core calculations

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APA (6th Edition):

Chapman, C. W. (2014). The MANE process of generating continuous energy hot-operating temperature cross sections. (Masters Thesis). Georgia Tech. Retrieved from http://hdl.handle.net/1853/53037

Chicago Manual of Style (16th Edition):

Chapman, Christopher Weeks. “The MANE process of generating continuous energy hot-operating temperature cross sections.” 2014. Masters Thesis, Georgia Tech. Accessed April 22, 2019. http://hdl.handle.net/1853/53037.

MLA Handbook (7th Edition):

Chapman, Christopher Weeks. “The MANE process of generating continuous energy hot-operating temperature cross sections.” 2014. Web. 22 Apr 2019.

Vancouver:

Chapman CW. The MANE process of generating continuous energy hot-operating temperature cross sections. [Internet] [Masters thesis]. Georgia Tech; 2014. [cited 2019 Apr 22]. Available from: http://hdl.handle.net/1853/53037.

Council of Science Editors:

Chapman CW. The MANE process of generating continuous energy hot-operating temperature cross sections. [Masters Thesis]. Georgia Tech; 2014. Available from: http://hdl.handle.net/1853/53037

30. Stewart, Christopher L. Investigation of fuel cycle for a sub-critical fusion-fission hybrid breeder reactor.

Degree: MS, Mechanical Engineering, 2013, Georgia Tech

 The SABR fusion-fission hybrid concept for a fast burner reactor, which combines the IFR-PRISM fast reactor technology and the ITER tokamak physics and fusion technology,… (more)

Subjects/Keywords: Fast breeder reactor; Fusion-fission hybrid; Fuel cycle; Breeder reactors; Fusion reactors; Tokamaks; Nuclear reactors

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APA (6th Edition):

Stewart, C. L. (2013). Investigation of fuel cycle for a sub-critical fusion-fission hybrid breeder reactor. (Masters Thesis). Georgia Tech. Retrieved from http://hdl.handle.net/1853/50407

Chicago Manual of Style (16th Edition):

Stewart, Christopher L. “Investigation of fuel cycle for a sub-critical fusion-fission hybrid breeder reactor.” 2013. Masters Thesis, Georgia Tech. Accessed April 22, 2019. http://hdl.handle.net/1853/50407.

MLA Handbook (7th Edition):

Stewart, Christopher L. “Investigation of fuel cycle for a sub-critical fusion-fission hybrid breeder reactor.” 2013. Web. 22 Apr 2019.

Vancouver:

Stewart CL. Investigation of fuel cycle for a sub-critical fusion-fission hybrid breeder reactor. [Internet] [Masters thesis]. Georgia Tech; 2013. [cited 2019 Apr 22]. Available from: http://hdl.handle.net/1853/50407.

Council of Science Editors:

Stewart CL. Investigation of fuel cycle for a sub-critical fusion-fission hybrid breeder reactor. [Masters Thesis]. Georgia Tech; 2013. Available from: http://hdl.handle.net/1853/50407

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