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You searched for subject:(Nuclear Engineering). Showing records 1 – 30 of 5110 total matches.

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Universidad Andrés Bello

1. Hernandez Meruane, Nicolás Alonso. Evaluación sísmica y analisis de envejecimiento de la estructura del block de piscina del reactor nuclear Rech-1 .

Degree: 2015, Universidad Andrés Bello

 El Reactor Experimental Chileno uno. Fue diseñado a finales de la década de los 60’ y su construcción comenzó a principio de los 70’, el… (more)

Subjects/Keywords: Ingenieria Sismica; Reactores Nucleares; Fusión Nuclear

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APA (6th Edition):

Hernandez Meruane, N. A. (2015). Evaluación sísmica y analisis de envejecimiento de la estructura del block de piscina del reactor nuclear Rech-1 . (Thesis). Universidad Andrés Bello. Retrieved from http://repositorio.unab.cl/xmlui/handle/ria/2677

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):

Hernandez Meruane, Nicolás Alonso. “Evaluación sísmica y analisis de envejecimiento de la estructura del block de piscina del reactor nuclear Rech-1 .” 2015. Thesis, Universidad Andrés Bello. Accessed January 23, 2019. http://repositorio.unab.cl/xmlui/handle/ria/2677.

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

MLA Handbook (7th Edition):

Hernandez Meruane, Nicolás Alonso. “Evaluación sísmica y analisis de envejecimiento de la estructura del block de piscina del reactor nuclear Rech-1 .” 2015. Web. 23 Jan 2019.

Vancouver:

Hernandez Meruane NA. Evaluación sísmica y analisis de envejecimiento de la estructura del block de piscina del reactor nuclear Rech-1 . [Internet] [Thesis]. Universidad Andrés Bello; 2015. [cited 2019 Jan 23]. Available from: http://repositorio.unab.cl/xmlui/handle/ria/2677.

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

Council of Science Editors:

Hernandez Meruane NA. Evaluación sísmica y analisis de envejecimiento de la estructura del block de piscina del reactor nuclear Rech-1 . [Thesis]. Universidad Andrés Bello; 2015. Available from: http://repositorio.unab.cl/xmlui/handle/ria/2677

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


University of Tennessee – Knoxville

2. Griswold, Justin Reed. Thick Target Yield of Th-229 via Low Energy Proton Bombardment of Th-232.

Degree: MS, Nuclear Engineering, 2014, University of Tennessee – Knoxville

  Actinium-225 is one of the more effective radioisotopes used in alpha radioimmunotherapy. Due to its ten-day half-life, it is more efficient to create its… (more)

Subjects/Keywords: Nuclear; Nuclear Engineering

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APA (6th Edition):

Griswold, J. R. (2014). Thick Target Yield of Th-229 via Low Energy Proton Bombardment of Th-232. (Thesis). University of Tennessee – Knoxville. Retrieved from http://trace.tennessee.edu/utk_gradthes/2820

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):

Griswold, Justin Reed. “Thick Target Yield of Th-229 via Low Energy Proton Bombardment of Th-232.” 2014. Thesis, University of Tennessee – Knoxville. Accessed January 23, 2019. http://trace.tennessee.edu/utk_gradthes/2820.

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

MLA Handbook (7th Edition):

Griswold, Justin Reed. “Thick Target Yield of Th-229 via Low Energy Proton Bombardment of Th-232.” 2014. Web. 23 Jan 2019.

Vancouver:

Griswold JR. Thick Target Yield of Th-229 via Low Energy Proton Bombardment of Th-232. [Internet] [Thesis]. University of Tennessee – Knoxville; 2014. [cited 2019 Jan 23]. Available from: http://trace.tennessee.edu/utk_gradthes/2820.

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

Council of Science Editors:

Griswold JR. Thick Target Yield of Th-229 via Low Energy Proton Bombardment of Th-232. [Thesis]. University of Tennessee – Knoxville; 2014. Available from: http://trace.tennessee.edu/utk_gradthes/2820

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


Texas A&M University

3. Ragusa, Jean Concetto. Accelerator driven production of tritium: target and blanket design.

Degree: MS, nuclear engineering, 2012, Texas A&M University

 Tritium is an essential component of thermonuclear weapons in the US arsenal. Unfortunately, tritium is a radioactive form of hydrogen, and one-half of the inventory… (more)

Subjects/Keywords: nuclear engineering.; Major nuclear engineering.

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APA (6th Edition):

Ragusa, J. C. (2012). Accelerator driven production of tritium: target and blanket design. (Masters Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/ETD-TAMU-1996-THESIS-R34

Chicago Manual of Style (16th Edition):

Ragusa, Jean Concetto. “Accelerator driven production of tritium: target and blanket design.” 2012. Masters Thesis, Texas A&M University. Accessed January 23, 2019. http://hdl.handle.net/1969.1/ETD-TAMU-1996-THESIS-R34.

MLA Handbook (7th Edition):

Ragusa, Jean Concetto. “Accelerator driven production of tritium: target and blanket design.” 2012. Web. 23 Jan 2019.

Vancouver:

Ragusa JC. Accelerator driven production of tritium: target and blanket design. [Internet] [Masters thesis]. Texas A&M University; 2012. [cited 2019 Jan 23]. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-1996-THESIS-R34.

Council of Science Editors:

Ragusa JC. Accelerator driven production of tritium: target and blanket design. [Masters Thesis]. Texas A&M University; 2012. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-1996-THESIS-R34


Texas A&M University

4. Ramone, Gilles Lionel. A Transport Synthetic Acceleration method for transport iterations.

Degree: MS, nuclear engineering, 2012, Texas A&M University

 We present a family of Transport Synthetic Acceleration (TSA) methods to iteratively solve within-group scattering problems. A single iteration in these schemes consists of a… (more)

Subjects/Keywords: nuclear engineering.; Major nuclear engineering.

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APA (6th Edition):

Ramone, G. L. (2012). A Transport Synthetic Acceleration method for transport iterations. (Masters Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/ETD-TAMU-1996-THESIS-R365

Chicago Manual of Style (16th Edition):

Ramone, Gilles Lionel. “A Transport Synthetic Acceleration method for transport iterations.” 2012. Masters Thesis, Texas A&M University. Accessed January 23, 2019. http://hdl.handle.net/1969.1/ETD-TAMU-1996-THESIS-R365.

MLA Handbook (7th Edition):

Ramone, Gilles Lionel. “A Transport Synthetic Acceleration method for transport iterations.” 2012. Web. 23 Jan 2019.

Vancouver:

Ramone GL. A Transport Synthetic Acceleration method for transport iterations. [Internet] [Masters thesis]. Texas A&M University; 2012. [cited 2019 Jan 23]. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-1996-THESIS-R365.

Council of Science Editors:

Ramone GL. A Transport Synthetic Acceleration method for transport iterations. [Masters Thesis]. Texas A&M University; 2012. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-1996-THESIS-R365


Texas A&M University

5. Reyes, Joseph Patrick. Simulation of condensation in the presence of noncondensible gases using the French Thermal Hydraulic computer code CATHARE.

Degree: MS, nuclear engineering, 2012, Texas A&M University

 The modeling of the complex thermal hydraulics of reactor systems involves the use of experimental test systems as well as numerical codes. A simulation of… (more)

Subjects/Keywords: nuclear engineering.; Major nuclear engineering.

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APA (6th Edition):

Reyes, J. P. (2012). Simulation of condensation in the presence of noncondensible gases using the French Thermal Hydraulic computer code CATHARE. (Masters Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/ETD-TAMU-1996-THESIS-R49

Chicago Manual of Style (16th Edition):

Reyes, Joseph Patrick. “Simulation of condensation in the presence of noncondensible gases using the French Thermal Hydraulic computer code CATHARE.” 2012. Masters Thesis, Texas A&M University. Accessed January 23, 2019. http://hdl.handle.net/1969.1/ETD-TAMU-1996-THESIS-R49.

MLA Handbook (7th Edition):

Reyes, Joseph Patrick. “Simulation of condensation in the presence of noncondensible gases using the French Thermal Hydraulic computer code CATHARE.” 2012. Web. 23 Jan 2019.

Vancouver:

Reyes JP. Simulation of condensation in the presence of noncondensible gases using the French Thermal Hydraulic computer code CATHARE. [Internet] [Masters thesis]. Texas A&M University; 2012. [cited 2019 Jan 23]. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-1996-THESIS-R49.

Council of Science Editors:

Reyes JP. Simulation of condensation in the presence of noncondensible gases using the French Thermal Hydraulic computer code CATHARE. [Masters Thesis]. Texas A&M University; 2012. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-1996-THESIS-R49


Texas A&M University

6. Troshko, Andrey Arthurovich. Simulation of the loss of the residual heat removal of an integral test facility using computer code Cathare7.

Degree: MS, nuclear engineering, 2012, Texas A&M University

 Assessment of the ability of thermal hydraulic codes to correctly predict complex phenomena during reactor transients can be performed only by means of comparison against… (more)

Subjects/Keywords: nuclear engineering.; Major nuclear engineering.

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APA (6th Edition):

Troshko, A. A. (2012). Simulation of the loss of the residual heat removal of an integral test facility using computer code Cathare7. (Masters Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/ETD-TAMU-1996-THESIS-T76

Chicago Manual of Style (16th Edition):

Troshko, Andrey Arthurovich. “Simulation of the loss of the residual heat removal of an integral test facility using computer code Cathare7.” 2012. Masters Thesis, Texas A&M University. Accessed January 23, 2019. http://hdl.handle.net/1969.1/ETD-TAMU-1996-THESIS-T76.

MLA Handbook (7th Edition):

Troshko, Andrey Arthurovich. “Simulation of the loss of the residual heat removal of an integral test facility using computer code Cathare7.” 2012. Web. 23 Jan 2019.

Vancouver:

Troshko AA. Simulation of the loss of the residual heat removal of an integral test facility using computer code Cathare7. [Internet] [Masters thesis]. Texas A&M University; 2012. [cited 2019 Jan 23]. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-1996-THESIS-T76.

Council of Science Editors:

Troshko AA. Simulation of the loss of the residual heat removal of an integral test facility using computer code Cathare7. [Masters Thesis]. Texas A&M University; 2012. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-1996-THESIS-T76


Texas A&M University

7. Walkowicz, Joshua Peter. Investigation of a thermoluminescent dosimeter mixture between LiF:Mg,Ti and Li2B4O7 in a solid form.

Degree: MS, nuclear engineering, 2012, Texas A&M University

 Thermoluminescent dosimetry is one of the most popular methods in use today for the monitoring of personnel exposures to radiation. This research investigates a different… (more)

Subjects/Keywords: nuclear engineering.; Major nuclear engineering.

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APA (6th Edition):

Walkowicz, J. P. (2012). Investigation of a thermoluminescent dosimeter mixture between LiF:Mg,Ti and Li2B4O7 in a solid form. (Masters Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/ETD-TAMU-1996-THESIS-W355

Chicago Manual of Style (16th Edition):

Walkowicz, Joshua Peter. “Investigation of a thermoluminescent dosimeter mixture between LiF:Mg,Ti and Li2B4O7 in a solid form.” 2012. Masters Thesis, Texas A&M University. Accessed January 23, 2019. http://hdl.handle.net/1969.1/ETD-TAMU-1996-THESIS-W355.

MLA Handbook (7th Edition):

Walkowicz, Joshua Peter. “Investigation of a thermoluminescent dosimeter mixture between LiF:Mg,Ti and Li2B4O7 in a solid form.” 2012. Web. 23 Jan 2019.

Vancouver:

Walkowicz JP. Investigation of a thermoluminescent dosimeter mixture between LiF:Mg,Ti and Li2B4O7 in a solid form. [Internet] [Masters thesis]. Texas A&M University; 2012. [cited 2019 Jan 23]. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-1996-THESIS-W355.

Council of Science Editors:

Walkowicz JP. Investigation of a thermoluminescent dosimeter mixture between LiF:Mg,Ti and Li2B4O7 in a solid form. [Masters Thesis]. Texas A&M University; 2012. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-1996-THESIS-W355


Texas A&M University

8. Dixon, John Leslie. Electrostatic coalescence of used automotive crankcase oil as an alternative to other separation processes.

Degree: MS, nuclear engineering, 2012, Texas A&M University

 This thesis presents an initial investigation of using electrostatic coalescence as an alternative to conventional separation processes to purify used automotive crankcase oil. Specific emphasis… (more)

Subjects/Keywords: nuclear engineering.; Major nuclear engineering.

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APA (6th Edition):

Dixon, J. L. (2012). Electrostatic coalescence of used automotive crankcase oil as an alternative to other separation processes. (Masters Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/ETD-TAMU-1998-THESIS-D59

Chicago Manual of Style (16th Edition):

Dixon, John Leslie. “Electrostatic coalescence of used automotive crankcase oil as an alternative to other separation processes.” 2012. Masters Thesis, Texas A&M University. Accessed January 23, 2019. http://hdl.handle.net/1969.1/ETD-TAMU-1998-THESIS-D59.

MLA Handbook (7th Edition):

Dixon, John Leslie. “Electrostatic coalescence of used automotive crankcase oil as an alternative to other separation processes.” 2012. Web. 23 Jan 2019.

Vancouver:

Dixon JL. Electrostatic coalescence of used automotive crankcase oil as an alternative to other separation processes. [Internet] [Masters thesis]. Texas A&M University; 2012. [cited 2019 Jan 23]. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-1998-THESIS-D59.

Council of Science Editors:

Dixon JL. Electrostatic coalescence of used automotive crankcase oil as an alternative to other separation processes. [Masters Thesis]. Texas A&M University; 2012. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-1998-THESIS-D59


Texas A&M University

9. Hamm, Trenton Allen. A steady state analysis code for prediction of behavior in loop heat pipes.

Degree: MS, nuclear engineering, 2012, Texas A&M University

 The purpose of this work is to prepare an analysis raphics. code for the prediction of Loop Heat Pipe (LHP) behavior in steady-state operation. The… (more)

Subjects/Keywords: nuclear engineering.; Major nuclear engineering.

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APA (6th Edition):

Hamm, T. A. (2012). A steady state analysis code for prediction of behavior in loop heat pipes. (Masters Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/ETD-TAMU-1998-THESIS-H354

Chicago Manual of Style (16th Edition):

Hamm, Trenton Allen. “A steady state analysis code for prediction of behavior in loop heat pipes.” 2012. Masters Thesis, Texas A&M University. Accessed January 23, 2019. http://hdl.handle.net/1969.1/ETD-TAMU-1998-THESIS-H354.

MLA Handbook (7th Edition):

Hamm, Trenton Allen. “A steady state analysis code for prediction of behavior in loop heat pipes.” 2012. Web. 23 Jan 2019.

Vancouver:

Hamm TA. A steady state analysis code for prediction of behavior in loop heat pipes. [Internet] [Masters thesis]. Texas A&M University; 2012. [cited 2019 Jan 23]. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-1998-THESIS-H354.

Council of Science Editors:

Hamm TA. A steady state analysis code for prediction of behavior in loop heat pipes. [Masters Thesis]. Texas A&M University; 2012. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-1998-THESIS-H354


Texas A&M University

10. Hari, Sridhar. Analysis of a research reactor under anticipated transients without scram events using the RELAP5/MOD3.2 computer program.

Degree: MS, nuclear engineering, 2012, Texas A&M University

 Simulations for two series of anticipated transients phics. without scram (ATWS) events have been carried out for a small, hypothetical, research reactor based on the… (more)

Subjects/Keywords: nuclear engineering.; Major nuclear engineering.

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APA (6th Edition):

Hari, S. (2012). Analysis of a research reactor under anticipated transients without scram events using the RELAP5/MOD3.2 computer program. (Masters Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/ETD-TAMU-1998-THESIS-H373

Chicago Manual of Style (16th Edition):

Hari, Sridhar. “Analysis of a research reactor under anticipated transients without scram events using the RELAP5/MOD3.2 computer program.” 2012. Masters Thesis, Texas A&M University. Accessed January 23, 2019. http://hdl.handle.net/1969.1/ETD-TAMU-1998-THESIS-H373.

MLA Handbook (7th Edition):

Hari, Sridhar. “Analysis of a research reactor under anticipated transients without scram events using the RELAP5/MOD3.2 computer program.” 2012. Web. 23 Jan 2019.

Vancouver:

Hari S. Analysis of a research reactor under anticipated transients without scram events using the RELAP5/MOD3.2 computer program. [Internet] [Masters thesis]. Texas A&M University; 2012. [cited 2019 Jan 23]. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-1998-THESIS-H373.

Council of Science Editors:

Hari S. Analysis of a research reactor under anticipated transients without scram events using the RELAP5/MOD3.2 computer program. [Masters Thesis]. Texas A&M University; 2012. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-1998-THESIS-H373


Texas A&M University

11. Dorsey, Daniel John. Electrical resistance of gases in explosive magnetic flux compression generator environments.

Degree: MS, nuclear engineering, 2012, Texas A&M University

 Gases that are electrical insulators at STP can become conductors when subjected to the high pressure and temperature environment in explosive magnetic flux compression generators… (more)

Subjects/Keywords: nuclear engineering.; Major nuclear engineering.

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APA (6th Edition):

Dorsey, D. J. (2012). Electrical resistance of gases in explosive magnetic flux compression generator environments. (Masters Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/ETD-TAMU-2000-THESIS-D68

Chicago Manual of Style (16th Edition):

Dorsey, Daniel John. “Electrical resistance of gases in explosive magnetic flux compression generator environments.” 2012. Masters Thesis, Texas A&M University. Accessed January 23, 2019. http://hdl.handle.net/1969.1/ETD-TAMU-2000-THESIS-D68.

MLA Handbook (7th Edition):

Dorsey, Daniel John. “Electrical resistance of gases in explosive magnetic flux compression generator environments.” 2012. Web. 23 Jan 2019.

Vancouver:

Dorsey DJ. Electrical resistance of gases in explosive magnetic flux compression generator environments. [Internet] [Masters thesis]. Texas A&M University; 2012. [cited 2019 Jan 23]. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-2000-THESIS-D68.

Council of Science Editors:

Dorsey DJ. Electrical resistance of gases in explosive magnetic flux compression generator environments. [Masters Thesis]. Texas A&M University; 2012. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-2000-THESIS-D68


Texas A&M University

12. Fu, Chun. RELAP5/MOD3.2 analysis of a VVER-1000 reactor with UO[2] fuel and MOX fuel.

Degree: MS, nuclear engineering, 2012, Texas A&M University

 A RELAP5/MOD3.2 model of a VVER-1000/MODEL V320 nuclear power plant, Balakovo Unit 4, was updated, improved and validated on the basis of an input deck… (more)

Subjects/Keywords: nuclear engineering.; Major nuclear engineering.

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APA (6th Edition):

Fu, C. (2012). RELAP5/MOD3.2 analysis of a VVER-1000 reactor with UO[2] fuel and MOX fuel. (Masters Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/ETD-TAMU-2000-THESIS-F8

Chicago Manual of Style (16th Edition):

Fu, Chun. “RELAP5/MOD3.2 analysis of a VVER-1000 reactor with UO[2] fuel and MOX fuel.” 2012. Masters Thesis, Texas A&M University. Accessed January 23, 2019. http://hdl.handle.net/1969.1/ETD-TAMU-2000-THESIS-F8.

MLA Handbook (7th Edition):

Fu, Chun. “RELAP5/MOD3.2 analysis of a VVER-1000 reactor with UO[2] fuel and MOX fuel.” 2012. Web. 23 Jan 2019.

Vancouver:

Fu C. RELAP5/MOD3.2 analysis of a VVER-1000 reactor with UO[2] fuel and MOX fuel. [Internet] [Masters thesis]. Texas A&M University; 2012. [cited 2019 Jan 23]. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-2000-THESIS-F8.

Council of Science Editors:

Fu C. RELAP5/MOD3.2 analysis of a VVER-1000 reactor with UO[2] fuel and MOX fuel. [Masters Thesis]. Texas A&M University; 2012. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-2000-THESIS-F8


Texas A&M University

13. Carlisle, Bruce Scott. An evaluation of the neutron radiography facility at the Nuclear Science Center for dynamic imaging of two-phase hydrogenous fluids.

Degree: MS, nuclear engineering, 2012, Texas A&M University

 Though both film and video radiographic image techniques are available in neutron radiography, radiographic cameras are commonly used to capture the dynamic flow patterns in… (more)

Subjects/Keywords: nuclear engineering.; Major nuclear engineering.

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APA (6th Edition):

Carlisle, B. S. (2012). An evaluation of the neutron radiography facility at the Nuclear Science Center for dynamic imaging of two-phase hydrogenous fluids. (Masters Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/ETD-TAMU-1994-THESIS-C283

Chicago Manual of Style (16th Edition):

Carlisle, Bruce Scott. “An evaluation of the neutron radiography facility at the Nuclear Science Center for dynamic imaging of two-phase hydrogenous fluids.” 2012. Masters Thesis, Texas A&M University. Accessed January 23, 2019. http://hdl.handle.net/1969.1/ETD-TAMU-1994-THESIS-C283.

MLA Handbook (7th Edition):

Carlisle, Bruce Scott. “An evaluation of the neutron radiography facility at the Nuclear Science Center for dynamic imaging of two-phase hydrogenous fluids.” 2012. Web. 23 Jan 2019.

Vancouver:

Carlisle BS. An evaluation of the neutron radiography facility at the Nuclear Science Center for dynamic imaging of two-phase hydrogenous fluids. [Internet] [Masters thesis]. Texas A&M University; 2012. [cited 2019 Jan 23]. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-1994-THESIS-C283.

Council of Science Editors:

Carlisle BS. An evaluation of the neutron radiography facility at the Nuclear Science Center for dynamic imaging of two-phase hydrogenous fluids. [Masters Thesis]. Texas A&M University; 2012. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-1994-THESIS-C283


Texas A&M University

14. Castrianni, Christopher Lee. A one-dimensional nonlinear corner balance method for solving the neutron transport equation.

Degree: MS, nuclear engineering, 2012, Texas A&M University

 The one-dimensional nonlinear comer balance method is a new spatial discretization scheme for solving the transport equation on grids consisting of arbitrarily connected polygonal meshes.… (more)

Subjects/Keywords: nuclear engineering.; Major nuclear engineering.

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APA (6th Edition):

Castrianni, C. L. (2012). A one-dimensional nonlinear corner balance method for solving the neutron transport equation. (Masters Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/ETD-TAMU-1994-THESIS-C355

Chicago Manual of Style (16th Edition):

Castrianni, Christopher Lee. “A one-dimensional nonlinear corner balance method for solving the neutron transport equation.” 2012. Masters Thesis, Texas A&M University. Accessed January 23, 2019. http://hdl.handle.net/1969.1/ETD-TAMU-1994-THESIS-C355.

MLA Handbook (7th Edition):

Castrianni, Christopher Lee. “A one-dimensional nonlinear corner balance method for solving the neutron transport equation.” 2012. Web. 23 Jan 2019.

Vancouver:

Castrianni CL. A one-dimensional nonlinear corner balance method for solving the neutron transport equation. [Internet] [Masters thesis]. Texas A&M University; 2012. [cited 2019 Jan 23]. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-1994-THESIS-C355.

Council of Science Editors:

Castrianni CL. A one-dimensional nonlinear corner balance method for solving the neutron transport equation. [Masters Thesis]. Texas A&M University; 2012. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-1994-THESIS-C355


Texas A&M University

15. Cebull, Peter Patrick. Simulation of the SPE-4 small-break loss-of-coolant accident using RELAP5/MOD 3.1.

Degree: MS, nuclear engineering, 2012, Texas A&M University

 A small-break loss-of-coolant accident experiment conducted at the PMK-2 integral test facility in Hungary is analyzed using the RELAP5/MOD3.1 thermal-hydrauhc code. The experiment simulated a… (more)

Subjects/Keywords: nuclear engineering.; Major nuclear engineering.

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APA (6th Edition):

Cebull, P. P. (2012). Simulation of the SPE-4 small-break loss-of-coolant accident using RELAP5/MOD 3.1. (Masters Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/ETD-TAMU-1994-THESIS-C3875

Chicago Manual of Style (16th Edition):

Cebull, Peter Patrick. “Simulation of the SPE-4 small-break loss-of-coolant accident using RELAP5/MOD 3.1.” 2012. Masters Thesis, Texas A&M University. Accessed January 23, 2019. http://hdl.handle.net/1969.1/ETD-TAMU-1994-THESIS-C3875.

MLA Handbook (7th Edition):

Cebull, Peter Patrick. “Simulation of the SPE-4 small-break loss-of-coolant accident using RELAP5/MOD 3.1.” 2012. Web. 23 Jan 2019.

Vancouver:

Cebull PP. Simulation of the SPE-4 small-break loss-of-coolant accident using RELAP5/MOD 3.1. [Internet] [Masters thesis]. Texas A&M University; 2012. [cited 2019 Jan 23]. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-1994-THESIS-C3875.

Council of Science Editors:

Cebull PP. Simulation of the SPE-4 small-break loss-of-coolant accident using RELAP5/MOD 3.1. [Masters Thesis]. Texas A&M University; 2012. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-1994-THESIS-C3875


Texas A&M University

16. Costes, Sylvain Vincent. Development of a three-dimensional particle image velocimetry algorithm and analysis of synthetic and experimental flows in three-dimensions.

Degree: MS, nuclear engineering, 2012, Texas A&M University

 This study concerns with the development of a simple three-dimensional technique to determine the velocity of fluid by tracing the motion of seeded particles in… (more)

Subjects/Keywords: nuclear engineering.; Major nuclear engineering.

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APA (6th Edition):

Costes, S. V. (2012). Development of a three-dimensional particle image velocimetry algorithm and analysis of synthetic and experimental flows in three-dimensions. (Masters Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/ETD-TAMU-1994-THESIS-C842

Chicago Manual of Style (16th Edition):

Costes, Sylvain Vincent. “Development of a three-dimensional particle image velocimetry algorithm and analysis of synthetic and experimental flows in three-dimensions.” 2012. Masters Thesis, Texas A&M University. Accessed January 23, 2019. http://hdl.handle.net/1969.1/ETD-TAMU-1994-THESIS-C842.

MLA Handbook (7th Edition):

Costes, Sylvain Vincent. “Development of a three-dimensional particle image velocimetry algorithm and analysis of synthetic and experimental flows in three-dimensions.” 2012. Web. 23 Jan 2019.

Vancouver:

Costes SV. Development of a three-dimensional particle image velocimetry algorithm and analysis of synthetic and experimental flows in three-dimensions. [Internet] [Masters thesis]. Texas A&M University; 2012. [cited 2019 Jan 23]. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-1994-THESIS-C842.

Council of Science Editors:

Costes SV. Development of a three-dimensional particle image velocimetry algorithm and analysis of synthetic and experimental flows in three-dimensions. [Masters Thesis]. Texas A&M University; 2012. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-1994-THESIS-C842


Texas A&M University

17. Eaton, Thomas Lance. A generalized simple corner-balance transport method for 1-D problems.

Degree: MS, nuclear engineering, 2012, Texas A&M University

 A new generalized simple Comer Balance transport method was developed in an attempt to produce accurate solutions to all one-dimensional transport problems. The method allows… (more)

Subjects/Keywords: nuclear engineering.; Major nuclear engineering.

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APA (6th Edition):

Eaton, T. L. (2012). A generalized simple corner-balance transport method for 1-D problems. (Masters Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/ETD-TAMU-1994-THESIS-E145

Chicago Manual of Style (16th Edition):

Eaton, Thomas Lance. “A generalized simple corner-balance transport method for 1-D problems.” 2012. Masters Thesis, Texas A&M University. Accessed January 23, 2019. http://hdl.handle.net/1969.1/ETD-TAMU-1994-THESIS-E145.

MLA Handbook (7th Edition):

Eaton, Thomas Lance. “A generalized simple corner-balance transport method for 1-D problems.” 2012. Web. 23 Jan 2019.

Vancouver:

Eaton TL. A generalized simple corner-balance transport method for 1-D problems. [Internet] [Masters thesis]. Texas A&M University; 2012. [cited 2019 Jan 23]. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-1994-THESIS-E145.

Council of Science Editors:

Eaton TL. A generalized simple corner-balance transport method for 1-D problems. [Masters Thesis]. Texas A&M University; 2012. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-1994-THESIS-E145


Texas A&M University

18. Yoon, Churl. Development of a genetic algorithm tracking technique for the particle image velocimetry and comparison with other tracking models.

Degree: MS, nuclear engineering, 2012, Texas A&M University

 The Particle Image Velocimetry (plV) flow measu rement technique is a very efficient technique for studying the structure of various fluid flows. It provides quantitative… (more)

Subjects/Keywords: nuclear engineering.; Major nuclear engineering.

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APA (6th Edition):

Yoon, C. (2012). Development of a genetic algorithm tracking technique for the particle image velocimetry and comparison with other tracking models. (Masters Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/ETD-TAMU-1996-THESIS-Y66

Chicago Manual of Style (16th Edition):

Yoon, Churl. “Development of a genetic algorithm tracking technique for the particle image velocimetry and comparison with other tracking models.” 2012. Masters Thesis, Texas A&M University. Accessed January 23, 2019. http://hdl.handle.net/1969.1/ETD-TAMU-1996-THESIS-Y66.

MLA Handbook (7th Edition):

Yoon, Churl. “Development of a genetic algorithm tracking technique for the particle image velocimetry and comparison with other tracking models.” 2012. Web. 23 Jan 2019.

Vancouver:

Yoon C. Development of a genetic algorithm tracking technique for the particle image velocimetry and comparison with other tracking models. [Internet] [Masters thesis]. Texas A&M University; 2012. [cited 2019 Jan 23]. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-1996-THESIS-Y66.

Council of Science Editors:

Yoon C. Development of a genetic algorithm tracking technique for the particle image velocimetry and comparison with other tracking models. [Masters Thesis]. Texas A&M University; 2012. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-1996-THESIS-Y66


Texas A&M University

19. Caldwell, Amy Baker. Risk analysis of shipping plutonium pits and mixed oxide fuel.

Degree: MS, nuclear engineering, 2012, Texas A&M University

 With the end of the cold war, there no longer seems to be a credible threat of war between nuclear superpowers, with its possible consequence… (more)

Subjects/Keywords: nuclear engineering.; Major nuclear engineering.

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APA (6th Edition):

Caldwell, A. B. (2012). Risk analysis of shipping plutonium pits and mixed oxide fuel. (Masters Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/ETD-TAMU-1997-THESIS-C35

Chicago Manual of Style (16th Edition):

Caldwell, Amy Baker. “Risk analysis of shipping plutonium pits and mixed oxide fuel.” 2012. Masters Thesis, Texas A&M University. Accessed January 23, 2019. http://hdl.handle.net/1969.1/ETD-TAMU-1997-THESIS-C35.

MLA Handbook (7th Edition):

Caldwell, Amy Baker. “Risk analysis of shipping plutonium pits and mixed oxide fuel.” 2012. Web. 23 Jan 2019.

Vancouver:

Caldwell AB. Risk analysis of shipping plutonium pits and mixed oxide fuel. [Internet] [Masters thesis]. Texas A&M University; 2012. [cited 2019 Jan 23]. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-1997-THESIS-C35.

Council of Science Editors:

Caldwell AB. Risk analysis of shipping plutonium pits and mixed oxide fuel. [Masters Thesis]. Texas A&M University; 2012. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-1997-THESIS-C35


Texas A&M University

20. Chang, Jae Ho. Statistical comparison of two-phase flow, void fraction fluctuations in a microgravity environment.

Degree: MS, nuclear engineering, 2012, Texas A&M University

 A two-phase flow experiment was flown aboard the NASA KC-135 zero gravity aircraft to test void fraction sensors and collect void fraction data under the… (more)

Subjects/Keywords: nuclear engineering.; Major nuclear engineering.

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APA (6th Edition):

Chang, J. H. (2012). Statistical comparison of two-phase flow, void fraction fluctuations in a microgravity environment. (Masters Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/ETD-TAMU-1997-THESIS-C4423

Chicago Manual of Style (16th Edition):

Chang, Jae Ho. “Statistical comparison of two-phase flow, void fraction fluctuations in a microgravity environment.” 2012. Masters Thesis, Texas A&M University. Accessed January 23, 2019. http://hdl.handle.net/1969.1/ETD-TAMU-1997-THESIS-C4423.

MLA Handbook (7th Edition):

Chang, Jae Ho. “Statistical comparison of two-phase flow, void fraction fluctuations in a microgravity environment.” 2012. Web. 23 Jan 2019.

Vancouver:

Chang JH. Statistical comparison of two-phase flow, void fraction fluctuations in a microgravity environment. [Internet] [Masters thesis]. Texas A&M University; 2012. [cited 2019 Jan 23]. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-1997-THESIS-C4423.

Council of Science Editors:

Chang JH. Statistical comparison of two-phase flow, void fraction fluctuations in a microgravity environment. [Masters Thesis]. Texas A&M University; 2012. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-1997-THESIS-C4423


Texas A&M University

21. Charlton, William S. Delayed neutron measurements from fast fission of actinide waste isotopes.

Degree: MS, nuclear engineering, 2012, Texas A&M University

 A study was performed to determine the delayed neutron emission properties from fast fission of several actinide waste isotopes. The specific isotopes evaluated were U-235,… (more)

Subjects/Keywords: nuclear engineering.; Major nuclear engineering.

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APA (6th Edition):

Charlton, W. S. (2012). Delayed neutron measurements from fast fission of actinide waste isotopes. (Masters Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/ETD-TAMU-1997-THESIS-C4427

Chicago Manual of Style (16th Edition):

Charlton, William S. “Delayed neutron measurements from fast fission of actinide waste isotopes.” 2012. Masters Thesis, Texas A&M University. Accessed January 23, 2019. http://hdl.handle.net/1969.1/ETD-TAMU-1997-THESIS-C4427.

MLA Handbook (7th Edition):

Charlton, William S. “Delayed neutron measurements from fast fission of actinide waste isotopes.” 2012. Web. 23 Jan 2019.

Vancouver:

Charlton WS. Delayed neutron measurements from fast fission of actinide waste isotopes. [Internet] [Masters thesis]. Texas A&M University; 2012. [cited 2019 Jan 23]. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-1997-THESIS-C4427.

Council of Science Editors:

Charlton WS. Delayed neutron measurements from fast fission of actinide waste isotopes. [Masters Thesis]. Texas A&M University; 2012. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-1997-THESIS-C4427


Texas A&M University

22. Ortensi, Javier. Rutherford backscattering analysis of gallium implanted 316 stainless steel.

Degree: MS, nuclear engineering, 2012, Texas A&M University

 Ion implantation of Ga ions into 316 stainless steel was performed at fluences ranging from 8x10¹⁶ to 10¹⁸ ions/cm². The depth profile of Ga in… (more)

Subjects/Keywords: nuclear engineering.; Major nuclear engineering.

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APA (6th Edition):

Ortensi, J. (2012). Rutherford backscattering analysis of gallium implanted 316 stainless steel. (Masters Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/ETD-TAMU-2000-THESIS-O78

Chicago Manual of Style (16th Edition):

Ortensi, Javier. “Rutherford backscattering analysis of gallium implanted 316 stainless steel.” 2012. Masters Thesis, Texas A&M University. Accessed January 23, 2019. http://hdl.handle.net/1969.1/ETD-TAMU-2000-THESIS-O78.

MLA Handbook (7th Edition):

Ortensi, Javier. “Rutherford backscattering analysis of gallium implanted 316 stainless steel.” 2012. Web. 23 Jan 2019.

Vancouver:

Ortensi J. Rutherford backscattering analysis of gallium implanted 316 stainless steel. [Internet] [Masters thesis]. Texas A&M University; 2012. [cited 2019 Jan 23]. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-2000-THESIS-O78.

Council of Science Editors:

Ortensi J. Rutherford backscattering analysis of gallium implanted 316 stainless steel. [Masters Thesis]. Texas A&M University; 2012. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-2000-THESIS-O78


Texas A&M University

23. Clarno, Kevin Taylor. Development of a RELAP5-3D three-dimensional model of a VVER-1000 Nuclear Power Plant for analysis of a large-break loss-of-coolant accident.

Degree: MS, nuclear engineering, 2012, Texas A&M University

 In order to analyze the benefits of the multi-dimensional hydrodynamic modeling capability of the RELAP5-3D system code in the VVER-1000 Nuclear Power Plant, a three-dimensional… (more)

Subjects/Keywords: nuclear engineering.; Major nuclear engineering.

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APA (6th Edition):

Clarno, K. T. (2012). Development of a RELAP5-3D three-dimensional model of a VVER-1000 Nuclear Power Plant for analysis of a large-break loss-of-coolant accident. (Masters Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/ETD-TAMU-2001-THESIS-C53

Chicago Manual of Style (16th Edition):

Clarno, Kevin Taylor. “Development of a RELAP5-3D three-dimensional model of a VVER-1000 Nuclear Power Plant for analysis of a large-break loss-of-coolant accident.” 2012. Masters Thesis, Texas A&M University. Accessed January 23, 2019. http://hdl.handle.net/1969.1/ETD-TAMU-2001-THESIS-C53.

MLA Handbook (7th Edition):

Clarno, Kevin Taylor. “Development of a RELAP5-3D three-dimensional model of a VVER-1000 Nuclear Power Plant for analysis of a large-break loss-of-coolant accident.” 2012. Web. 23 Jan 2019.

Vancouver:

Clarno KT. Development of a RELAP5-3D three-dimensional model of a VVER-1000 Nuclear Power Plant for analysis of a large-break loss-of-coolant accident. [Internet] [Masters thesis]. Texas A&M University; 2012. [cited 2019 Jan 23]. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-2001-THESIS-C53.

Council of Science Editors:

Clarno KT. Development of a RELAP5-3D three-dimensional model of a VVER-1000 Nuclear Power Plant for analysis of a large-break loss-of-coolant accident. [Masters Thesis]. Texas A&M University; 2012. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-2001-THESIS-C53


Texas A&M University

24. Garcia, Richard Michael. Neon time-of-flight backscattering spectrometry for surface analysis.

Degree: MS, nuclear engineering, 2012, Texas A&M University

 Several time-of-flight backscattering spectrometry experiments using singly ionized neon for purposes of analyzing a bismuth coated silicon target were conducted. This work builds upon prior… (more)

Subjects/Keywords: nuclear engineering.; Major nuclear engineering.

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APA (6th Edition):

Garcia, R. M. (2012). Neon time-of-flight backscattering spectrometry for surface analysis. (Masters Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/ETD-TAMU-2001-THESIS-G366

Chicago Manual of Style (16th Edition):

Garcia, Richard Michael. “Neon time-of-flight backscattering spectrometry for surface analysis.” 2012. Masters Thesis, Texas A&M University. Accessed January 23, 2019. http://hdl.handle.net/1969.1/ETD-TAMU-2001-THESIS-G366.

MLA Handbook (7th Edition):

Garcia, Richard Michael. “Neon time-of-flight backscattering spectrometry for surface analysis.” 2012. Web. 23 Jan 2019.

Vancouver:

Garcia RM. Neon time-of-flight backscattering spectrometry for surface analysis. [Internet] [Masters thesis]. Texas A&M University; 2012. [cited 2019 Jan 23]. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-2001-THESIS-G366.

Council of Science Editors:

Garcia RM. Neon time-of-flight backscattering spectrometry for surface analysis. [Masters Thesis]. Texas A&M University; 2012. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-2001-THESIS-G366


Texas A&M University

25. Henderson, Ashley David. The radiological impact of the 2000 Hanford Fire (24-Command Fire).

Degree: MS, nuclear engineering, 2012, Texas A&M University

 The range fire at the Hanford facility in late June 2000 coupled with the fire at Los Alamos during the same year have raised a… (more)

Subjects/Keywords: nuclear engineering.; Major nuclear engineering.

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APA (6th Edition):

Henderson, A. D. (2012). The radiological impact of the 2000 Hanford Fire (24-Command Fire). (Masters Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/ETD-TAMU-2001-THESIS-H457

Chicago Manual of Style (16th Edition):

Henderson, Ashley David. “The radiological impact of the 2000 Hanford Fire (24-Command Fire).” 2012. Masters Thesis, Texas A&M University. Accessed January 23, 2019. http://hdl.handle.net/1969.1/ETD-TAMU-2001-THESIS-H457.

MLA Handbook (7th Edition):

Henderson, Ashley David. “The radiological impact of the 2000 Hanford Fire (24-Command Fire).” 2012. Web. 23 Jan 2019.

Vancouver:

Henderson AD. The radiological impact of the 2000 Hanford Fire (24-Command Fire). [Internet] [Masters thesis]. Texas A&M University; 2012. [cited 2019 Jan 23]. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-2001-THESIS-H457.

Council of Science Editors:

Henderson AD. The radiological impact of the 2000 Hanford Fire (24-Command Fire). [Masters Thesis]. Texas A&M University; 2012. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-2001-THESIS-H457


Texas A&M University

26. Stone, Joseph C. Delayed neutron measurements for Th-232, Np-237, Pu-239, Pu-241 and depleted uranium.

Degree: MS, nuclear engineering, 2012, Texas A&M University

 The neutron emission rates from five very pure actinide samples (Th-232, Np-237, Pu-239, Pu-241 and depleted uranium) were measured following equilibrium irradiation in fast and… (more)

Subjects/Keywords: nuclear engineering.; Major nuclear engineering.

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APA (6th Edition):

Stone, J. C. (2012). Delayed neutron measurements for Th-232, Np-237, Pu-239, Pu-241 and depleted uranium. (Masters Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/ETD-TAMU-2001-THESIS-S7454

Chicago Manual of Style (16th Edition):

Stone, Joseph C. “Delayed neutron measurements for Th-232, Np-237, Pu-239, Pu-241 and depleted uranium.” 2012. Masters Thesis, Texas A&M University. Accessed January 23, 2019. http://hdl.handle.net/1969.1/ETD-TAMU-2001-THESIS-S7454.

MLA Handbook (7th Edition):

Stone, Joseph C. “Delayed neutron measurements for Th-232, Np-237, Pu-239, Pu-241 and depleted uranium.” 2012. Web. 23 Jan 2019.

Vancouver:

Stone JC. Delayed neutron measurements for Th-232, Np-237, Pu-239, Pu-241 and depleted uranium. [Internet] [Masters thesis]. Texas A&M University; 2012. [cited 2019 Jan 23]. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-2001-THESIS-S7454.

Council of Science Editors:

Stone JC. Delayed neutron measurements for Th-232, Np-237, Pu-239, Pu-241 and depleted uranium. [Masters Thesis]. Texas A&M University; 2012. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-2001-THESIS-S7454


Texas A&M University

27. Furukawa, Toru. Three-dimensional reconstruction of bubble distribution in two-phase bubbly flows with the dynamic programming method.

Degree: MS, nuclear engineering, 2012, Texas A&M University

 A three-dimensional bubble reconstruction method is proposed in this thesis to analyze two-phase bubbly flows. Gas/liquid two-phase flows have important roles in the nuclear and… (more)

Subjects/Keywords: nuclear engineering.; Major nuclear engineering.

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APA (6th Edition):

Furukawa, T. (2012). Three-dimensional reconstruction of bubble distribution in two-phase bubbly flows with the dynamic programming method. (Masters Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/ETD-TAMU-2002-THESIS-F96

Chicago Manual of Style (16th Edition):

Furukawa, Toru. “Three-dimensional reconstruction of bubble distribution in two-phase bubbly flows with the dynamic programming method.” 2012. Masters Thesis, Texas A&M University. Accessed January 23, 2019. http://hdl.handle.net/1969.1/ETD-TAMU-2002-THESIS-F96.

MLA Handbook (7th Edition):

Furukawa, Toru. “Three-dimensional reconstruction of bubble distribution in two-phase bubbly flows with the dynamic programming method.” 2012. Web. 23 Jan 2019.

Vancouver:

Furukawa T. Three-dimensional reconstruction of bubble distribution in two-phase bubbly flows with the dynamic programming method. [Internet] [Masters thesis]. Texas A&M University; 2012. [cited 2019 Jan 23]. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-2002-THESIS-F96.

Council of Science Editors:

Furukawa T. Three-dimensional reconstruction of bubble distribution in two-phase bubbly flows with the dynamic programming method. [Masters Thesis]. Texas A&M University; 2012. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-2002-THESIS-F96


Texas A&M University

28. Gautier, Vincent Charles. Development of Nuclear Reactor remote Monitoring software (NRM) for the Star project.

Degree: MS, nuclear engineering, 2012, Texas A&M University

 As a response to the needs of developing countries to meet their rapidly growing energy requirements, the Safe, Transportable, Autonomous Reactor (STAR) program originated. This… (more)

Subjects/Keywords: nuclear engineering.; Major nuclear engineering.

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APA (6th Edition):

Gautier, V. C. (2012). Development of Nuclear Reactor remote Monitoring software (NRM) for the Star project. (Masters Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/ETD-TAMU-2002-THESIS-G385

Chicago Manual of Style (16th Edition):

Gautier, Vincent Charles. “Development of Nuclear Reactor remote Monitoring software (NRM) for the Star project.” 2012. Masters Thesis, Texas A&M University. Accessed January 23, 2019. http://hdl.handle.net/1969.1/ETD-TAMU-2002-THESIS-G385.

MLA Handbook (7th Edition):

Gautier, Vincent Charles. “Development of Nuclear Reactor remote Monitoring software (NRM) for the Star project.” 2012. Web. 23 Jan 2019.

Vancouver:

Gautier VC. Development of Nuclear Reactor remote Monitoring software (NRM) for the Star project. [Internet] [Masters thesis]. Texas A&M University; 2012. [cited 2019 Jan 23]. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-2002-THESIS-G385.

Council of Science Editors:

Gautier VC. Development of Nuclear Reactor remote Monitoring software (NRM) for the Star project. [Masters Thesis]. Texas A&M University; 2012. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-2002-THESIS-G385


Texas A&M University

29. Helton, Donald McLean. Calculation of unsteady turbulent flow around obstacles using the large eddy simulation turbulence model.

Degree: MS, nuclear engineering, 2012, Texas A&M University

 The premise of the work presented here is to use a common analytical tool, Computational Fluid Dynamics (CFD), along with a prevalent turbulence model, Large… (more)

Subjects/Keywords: nuclear engineering.; Major nuclear engineering.

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APA (6th Edition):

Helton, D. M. (2012). Calculation of unsteady turbulent flow around obstacles using the large eddy simulation turbulence model. (Masters Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/ETD-TAMU-2002-THESIS-H455

Chicago Manual of Style (16th Edition):

Helton, Donald McLean. “Calculation of unsteady turbulent flow around obstacles using the large eddy simulation turbulence model.” 2012. Masters Thesis, Texas A&M University. Accessed January 23, 2019. http://hdl.handle.net/1969.1/ETD-TAMU-2002-THESIS-H455.

MLA Handbook (7th Edition):

Helton, Donald McLean. “Calculation of unsteady turbulent flow around obstacles using the large eddy simulation turbulence model.” 2012. Web. 23 Jan 2019.

Vancouver:

Helton DM. Calculation of unsteady turbulent flow around obstacles using the large eddy simulation turbulence model. [Internet] [Masters thesis]. Texas A&M University; 2012. [cited 2019 Jan 23]. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-2002-THESIS-H455.

Council of Science Editors:

Helton DM. Calculation of unsteady turbulent flow around obstacles using the large eddy simulation turbulence model. [Masters Thesis]. Texas A&M University; 2012. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-2002-THESIS-H455


Texas A&M University

30. Jiltchenkov, Dmitri Victorovich. The development of a remote monitoring system for the Nuclear Science Center reactor.

Degree: MS, nuclear engineering, 2012, Texas A&M University

 With funding provided by Nuclear Energy Research Initiative (NERI), design of Secure, Transportable, Autonomous Reactors (STAR) to aid countries with insufficient energy supplies is underway.… (more)

Subjects/Keywords: nuclear engineering.; Major nuclear engineering.

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

APA (6th Edition):

Jiltchenkov, D. V. (2012). The development of a remote monitoring system for the Nuclear Science Center reactor. (Masters Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/ETD-TAMU-2002-THESIS-J57

Chicago Manual of Style (16th Edition):

Jiltchenkov, Dmitri Victorovich. “The development of a remote monitoring system for the Nuclear Science Center reactor.” 2012. Masters Thesis, Texas A&M University. Accessed January 23, 2019. http://hdl.handle.net/1969.1/ETD-TAMU-2002-THESIS-J57.

MLA Handbook (7th Edition):

Jiltchenkov, Dmitri Victorovich. “The development of a remote monitoring system for the Nuclear Science Center reactor.” 2012. Web. 23 Jan 2019.

Vancouver:

Jiltchenkov DV. The development of a remote monitoring system for the Nuclear Science Center reactor. [Internet] [Masters thesis]. Texas A&M University; 2012. [cited 2019 Jan 23]. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-2002-THESIS-J57.

Council of Science Editors:

Jiltchenkov DV. The development of a remote monitoring system for the Nuclear Science Center reactor. [Masters Thesis]. Texas A&M University; 2012. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-2002-THESIS-J57

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