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Journal Articles

Neutronic Analysis and Fuel Cycle Parameters of Transuranic-UO 2 Fueled Dual Cooled VVER-1000 Assembly

Md. Tanvir Ahmed, Afroza Shelley, Md. Nobir Hosen
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2024, 10(2): 021602.
Paper No: NERS-23-1069
https://doi.org/10.1115/1.4063757
Published Online: January 29, 2024
View Article titled, Neutronic Analysis and Fuel Cycle Parameters of Transuranic-UO 2 Fueled Dual Cooled VVER-1000 Assembly
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Topics: Cycles, Fuel rods, Fuels, Manufacturing, Neutron flux, Neutrons, Nuclear fission, Nuclear fuel cycle, Rods, Safety
Journal Articles

Guest Editorial: Special Section on Research Center Řež: Nuclear-Engineering Activities in 2018

Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Guest Editorial
ASME J of Nuclear Rad Sci. July 2019, 5(3): 030301.
Paper No: NERS-19-1035
https://doi.org/10.1115/1.4043382
Published Online: April 19, 2019
View Article titled, Guest Editorial: Special Section on Research Center Řež: Nuclear-Engineering Activities in 2018
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Topics: Accidents, Circuits, Coolants, Corrosion, Generation IV reactors, Materials research, Modeling, Nuclear engineering, Nuclear fuel cycle, Nuclear reactors
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
Publisher: ASME
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
Journal Articles

Validation of the Onsite Used Operational Code Against Burnup Measurement

Michal Koleška, Michal Šunka, Jaroslav Ernest
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Technical Briefs
ASME J of Nuclear Rad Sci. January 2017, 3(1): 014502.
Paper No: NERS-15-1230
https://doi.org/10.1115/1.4034570
Published Online: December 20, 2016
View Article titled, Validation of the Onsite Used Operational Code Against Burnup Measurement
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Topics: Fuels, Nuclear fission, Nuclear fuel cycle, Manufacturing, Thermography, Spent nuclear fuels
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
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Topics: Carbon reinforced plastics, Optimization, Nuclear fuel cycle, Cycles, Fuels, Pressurized water reactors
Journal Articles

Neutronic Design Features of a Transportable Fluoride-Salt-Cooled High-Temperature Reactor

Kaichao Sun, Lin-Wen Hu, Charles Forsberg
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research Papers
ASME J of Nuclear Rad Sci. July 2016, 2(3): 031003.
Paper No: NERS-15-1184
https://doi.org/10.1115/1.4032873
Published Online: June 17, 2016
View Article titled, Neutronic Design Features of a Transportable Fluoride-Salt-Cooled High-Temperature Reactor
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Topics: Coolants, Design, Fuels, Nuclear fuel cycle, Safety, Rods, Particulate matter, Control systems, High temperature
Journal Articles

Editorial

Igor L. Pioro
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Editorial
ASME J of Nuclear Rad Sci. January 2015, 1(1): 010201.
Paper No: NERS-14-1055
https://doi.org/10.1115/1.4029141
Published Online: February 9, 2015
View Article titled, Editorial
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Topics: China, Design, Nuclear engineering, Nuclear fuel cycle, Nuclear power, Nuclear power stations, Nuclear reactors, Physics, Radiation (Physics), Risk
Journal Articles

Parametric Lattice Study of a Graphite-Moderated Molten Salt Reactor

Boris A. Hombourger, Jiří Křepel, Konstantin Mikityuk, Andreas Pautz
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research Papers
ASME J of Nuclear Rad Sci. January 2015, 1(1): 011009.
Paper No: NERS-14-1038
https://doi.org/10.1115/1.4026401
Published Online: February 9, 2015
View Article titled, Parametric Lattice Study of a Graphite-Moderated Molten Salt Reactor
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Topics: Equilibrium (Physics), Fuels, Graphite, Molten salt reactors, Neutrons, Nuclear fuel cycle, Design, Nuclear fission, Uranium