1-4 of 4
G. Ivan Maldonado
Close
Save search
Follow your search
Access your saved searches in your account
Would you like to receive an alert when new items match your search?
Close Modal
Sort by
Journal Articles

Thermomechanical Safety Analyses for a 238 Pu Production Target at the HFIR

Christopher J. Hurt, James D. Freels, Prashant K. Jain, G. Ivan Maldonado
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2019, 5(2): 021004.
Paper No: NERS-16-1070
https://doi.org/10.1115/1.4041295
Published Online: March 15, 2019
View Article titled, Thermomechanical Safety Analyses for a 238 Pu Production Target at the HFIR
Open the PDF for Thermomechanical Safety Analyses for a 238 Pu Production Target at the HFIR in another window
Topics: Cycles, Irradiation (Radiation exposure), Safety, Temperature, Stress, Heat transfer, Electrical conductance, Steady state, Heat, Cladding systems (Building)
Journal Articles

Thermo-Mechanical Safety Analyses of Preliminary Design Experiments for 238 Pu Production

Christopher J. Hurt, James D. Freels, Prashant K. Jain, G. Ivan Maldonado
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2019, 5(1): 011002.
Paper No: NERS-16-1069
https://doi.org/10.1115/1.4041269
Published Online: January 24, 2019
View Article titled, Thermo-Mechanical Safety Analyses of Preliminary Design Experiments for 238 Pu Production
Open the PDF for Thermo-Mechanical Safety Analyses of Preliminary Design Experiments for 238 Pu Production in another window
Topics: Heat, Irradiation (Radiation exposure), Safety, Temperature, Manufacturing, Heat transfer, Design, Shrinkage (Materials), Geometry, Cycles
Proceedings Papers

Towards Development of Uncertainty Library for Nuclear Reactor Core Simulation

Hany S. Abdel-Khalik, Dongli Huang, Ondrej Chvala, G. Ivan Maldonado
Proc. ASME. ICONE26, Volume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory, V003T02A052, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82385
https://doi.org/10.1115/ICONE26-82385
View Paper titled, Towards Development of Uncertainty Library for Nuclear Reactor Core Simulation
Open the PDF for Towards Development of Uncertainty Library for Nuclear Reactor Core Simulation in another window
Topics: Nuclear reactors, Simulation, Uncertainty, Physics, Algorithms, Boiling water reactors, Cross section (Physics), Degrees of freedom, Modeling, Uncertainty quantification
Journal Articles

SMR Fuel Cycle Optimization Using LWROpt

Keith E. Ottinger, G. Ivan Maldonado
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research Papers
ASME J of Nuclear Rad Sci. January 2017, 3(1): 011014.
Paper No: NERS-16-1047
https://doi.org/10.1115/1.4034573
Published Online: December 20, 2016
View Article titled, SMR Fuel Cycle Optimization Using LWROpt
Open the PDF for SMR Fuel Cycle Optimization Using LWROpt in another window
Topics: Carbon reinforced plastics, Optimization, Nuclear fuel cycle, Cycles, Fuels, Pressurized water reactors