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George L. Mesina
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Proceedings Papers

Using Code Adequacy Methodologies in Confomance with ASME Standards for Nuclear Power Plant Analysis Evaluation Models

Richard R. Schultz, George L. Mesina
Proc. ASME. VVUQ2023, ASME 2023 Verification, Validation, and Uncertainty Quantification Symposium, V001T07A002, May 17–19, 2023
Paper No: VVUQ2023-108796
https://doi.org/10.1115/VVUQ2023-108796
View Paper titled, Using Code Adequacy Methodologies in Confomance with ASME Standards for Nuclear Power Plant Analysis Evaluation Models
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Topics: ASME Standards, Computational fluid dynamics, Nuclear power stations, Systems analysis, Cycles, Design, Accidents, Boilers, Boiling water reactors, Control systems
Proceedings Papers

Improvement of the RELAP5-3D Model of Condensation in the Presence of Noncondensables

Nolan A. Anderson, George L. Mesina
Proc. ASME. NUCLRF2017, ASME 2017 Nuclear Forum, V009T03A002, June 26–30, 2017
Paper No: NUCLRF2017-3401
https://doi.org/10.1115/NUCLRF2017-3401
View Paper titled, Improvement of the RELAP5-3D Model of Condensation in the Presence of Noncondensables
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Topics: Condensation, Vapors, Accidents, Density, Nuclear power stations, Pressure, Pressurized water reactors, Steam, Boilers, Coolants
Proceedings Papers

Solution of Governing Equations for Six-Field System Code

Glenn A. Roth, George L. Mesina, Fatih Aydogan
Proc. ASME. NUCLRF2017, ASME 2017 Nuclear Forum, V009T03A004, June 26–30, 2017
Paper No: NUCLRF2017-3515
https://doi.org/10.1115/NUCLRF2017-3515
View Paper titled, Solution of Governing Equations for Six-Field System Code
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Topics: Accidents, Algebra, Boiling, Bubbles, Computer software, Computers, Condensation, Coolants, Cooling, Design
Journal Articles

Combining RAVEN, RELAP5-3D, and PHISICS for Fuel Cycle and Core Design Analysis for New Cladding Criteria

Andrea Alfonsi, George L. Mesina, Angelo Zoino, Nolan Anderson, Cristian Rabiti
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2017, 3(2): 020906.
Paper No: NERS-16-1120
https://doi.org/10.1115/1.4035851
Published Online: March 1, 2017
View Article titled, Combining RAVEN, RELAP5-3D, and PHISICS for Fuel Cycle and Core Design Analysis for New Cladding Criteria
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Topics: Accidents, Cladding systems (Building), Coolants, Cycles, Design, Flow (Dynamics), Fuels, Nuclear fuel cycle, Oxidation, Safety
Proceedings Papers

Enhanced Verification for RELAP5-3D Parameter and Sensitivity Studies

George L. Mesina, Nolan Anderson
Proc. ASME. ICONE24, Volume 3: Thermal-Hydraulics, V003T09A084, June 26–30, 2016
Paper No: ICONE24-61040
https://doi.org/10.1115/ICONE24-61040
View Paper titled, Enhanced Verification for RELAP5-3D Parameter and Sensitivity Studies
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Topics: Complex systems, Computer software, Computers, Nuclear power stations, Physics, Quality control
Proceedings Papers

A Fuel Cycle and Core Design Analysis Method for New Cladding Acceptance Criteria Using PHISICS, RAVEN and RELAP5-3D

Andrea Alfonsi, George L. Mesina, Angelo Zoino, Cristian Rabiti
Proc. ASME. ICONE24, Volume 3: Thermal-Hydraulics, V003T09A085, June 26–30, 2016
Paper No: ICONE24-61045
https://doi.org/10.1115/ICONE24-61045
View Paper titled, A Fuel Cycle and Core Design Analysis Method for New Cladding Acceptance Criteria Using PHISICS, RAVEN and RELAP5-3D
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Topics: Acceptance criteria, Cladding systems (Building), Design, Nuclear fuel cycle, Accidents, Physics, Pressurized water reactors, Coolants, Fuels, Leakage
Proceedings Papers

Automated, Highly Accurate Verification of RELAP5-3D

George L. Mesina, David L. Aumiller, Francis X. Buschman
Proc. ASME. ICONE22, Volume 2B: Thermal Hydraulics, V02BT09A054, July 7–11, 2014
Paper No: ICONE22-31153
https://doi.org/10.1115/ICONE22-31153
View Paper titled, Automated, Highly Accurate Verification of RELAP5-3D
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Topics: Algorithms, Complex systems, Computer software, Design, Light water reactors, Mathematical analysis, Physics, Quality control, Safety
Proceedings Papers

Reformulation RELAP5-3D in FORTRAN 95 and Results

George L. Mesina
Proc. ASME. FEDSM2010, ASME 2010 3rd Joint US-European Fluids Engineering Summer Meeting: Volume 1, Symposia – Parts A, B, and C, 1959-1968, August 1–5, 2010
Paper No: FEDSM-ICNMM2010-30401
https://doi.org/10.1115/FEDSM-ICNMM2010-30401
View Paper titled, Reformulation RELAP5-3D in FORTRAN 95 and Results
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Topics: FORTRAN, Machinery, Computer programming, Databases, Design, Fluids, Maintenance, Manifolds, Nuclear power stations, Safety
Proceedings Papers

Visualization of Heat Transfer and Core Damage With RGUI 1.5

George L. Mesina
Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 3, 1077-1086, April 14–18, 2002
Paper No: ICONE10-22698
https://doi.org/10.1115/ICONE10-22698
View Paper titled, Visualization of Heat Transfer and Core Damage With RGUI 1.5
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Topics: Damage, Heat transfer, Visualization, Graphical user interfaces, Computer software, Accidents, Fuel rods, Heat, Modeling, Nuclear power stations