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Journal Articles

Analysis of the HI-TRAC VW Transfer Cask Dose Rates for Spent Fuel Assemblies Loaded in Nuclear Power Plant Krsko Storage Campaign One

Davor Grgić, Mario Matijević, Paulina Dučkić, Radomir Ječmenica
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2022, 8(4): 041902.
Paper No: NERS-21-1029
https://doi.org/10.1115/1.4051447
Published Online: March 16, 2022
View Article titled, Analysis of the HI-TRAC VW Transfer Cask Dose Rates for Spent Fuel Assemblies Loaded in Nuclear Power Plant Krsko Storage Campaign One
Open the PDF for Analysis of the HI-TRAC VW Transfer Cask Dose Rates for Spent Fuel Assemblies Loaded in Nuclear Power Plant Krsko Storage Campaign One in another window
Topics: Accidents, Fuels, Hardware, Neutrons, Nuclear power stations, Particulate matter, Spent nuclear fuels, Storage, Uncertainty, Manufacturing
Journal Articles

Postoperation Dose Rate Estimates for the Very-Small, Long-Life, Modular Reactor

Luis M. Palomino, Mohamed S. El-Genk, Timothy M. Schriener
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2020, 6(3): 031302.
Paper No: NERS-19-1045
https://doi.org/10.1115/1.4045297
Published Online: March 9, 2020
View Article titled, Postoperation Dose Rate Estimates for the Very-Small, Long-Life, Modular Reactor
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Topics: Cladding systems (Building), Emissions, Fuels, Neutrons, Photons, Steel, Vessels, Storage, Radioactivity, Isotopes
Journal Articles

Implementation of Hydrogen Solid Solubility Data and Precipitation Threshold Stresses in the Fuel Rod Code TESPA-ROD

Felix Boldt
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2019, 5(2): 020904.
Paper No: NERS-18-1065
https://doi.org/10.1115/1.4042118
Published Online: March 15, 2019
View Article titled, Implementation of Hydrogen Solid Solubility Data and Precipitation Threshold Stresses in the Fuel Rod Code TESPA-ROD
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Topics: Cladding systems (Building), Fuel rods, Heat, Hydrogen, Precipitation, Storage, Stress, Temperature, Transients (Dynamics), Simulation
Journal Articles

Transfer and Storage of Molten Salt for the Pyroprocessing of Used Nuclear Fuel

Matthew C. Morrison, Kenneth J. Bateman
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research Papers
ASME J of Nuclear Rad Sci. January 2017, 3(1): 011001.
Paper No: NERS-15-1016
https://doi.org/10.1115/1.4032999
Published Online: December 20, 2016
View Article titled, Transfer and Storage of Molten Salt for the Pyroprocessing of Used Nuclear Fuel
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Topics: Containers, Storage, Switches, Vacuum pumps, Cooling