1-20 of 20
Graphite
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

The Transfer of Xenon-135 to Molten Salt Reactor Graphite

Terry Price, Ondrej Chvala
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2024, 10(4): 041001.
Paper No: NERS-22-1113
https://doi.org/10.1115/1.4064464
Published Online: June 21, 2024
View Article titled, The Transfer of Xenon-135 to Molten Salt Reactor Graphite
Open the PDF for The Transfer of Xenon-135 to Molten Salt Reactor Graphite in another window
Topics: Graphite, Porosity, Fuels, Molten salt reactors, Mass transfer, Diffusion (Physics)
Journal Articles

Special Experimental Environment for Generation IV Reactors With Graphite Reflector

Eva Vilímová, Tomáš Peltan, Radek Škoda
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2024, 10(1): 011501.
Paper No: NERS-23-1017
https://doi.org/10.1115/1.4064124
Published Online: December 19, 2023
View Article titled, Special Experimental Environment for Generation IV Reactors With Graphite Reflector
Open the PDF for Special Experimental Environment for Generation IV Reactors With Graphite Reflector in another window
Topics: Graphite, Neutron flux, Neutrons, Fuels
Journal Articles

Assessment of Reactor Physics Characteristics of Prismatic Fuel Concepts With a Hydrogen-Based Moderator for Use in a Fluoride Salt-Cooled Small Modular Reactor

Huiping V. Yan, Blair P. Bromley
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2024, 10(2): 021502.
Paper No: NERS-23-1010
https://doi.org/10.1115/1.4063388
Published Online: November 1, 2023
View Article titled, Assessment of Reactor Physics Characteristics of Prismatic Fuel Concepts With a Hydrogen-Based Moderator for Use in a Fluoride Salt-Cooled Small Modular Reactor
Open the PDF for Assessment of Reactor Physics Characteristics of Prismatic Fuel Concepts With a Hydrogen-Based Moderator for Use in a Fluoride Salt-Cooled Small Modular Reactor in another window
Topics: Coolants, Fuels, Temperature, Hydrogen, Graphite, Design, Rods, Physics
Journal Articles

Long-Term Performance of Semimetallic Gaskets

Abdel-Hakim Bouzid, Shubhra Kanti Das
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2023, 9(3): 031801.
Paper No: NERS-22-1036
https://doi.org/10.1115/1.4056260
Published Online: February 8, 2023
View Article titled, Long-Term Performance of Semimetallic Gaskets
Open the PDF for Long-Term Performance of Semimetallic Gaskets in another window
Topics: Gaskets, Graphite, Leakage, Temperature, Relaxation (Physics), High temperature, Weight (Mass), Stress
Journal Articles

Possible Implementation of Ex-Core Measurement in TEPLATOR Graphite Reflector

Eva Vilímová, Tomáš Peltan, Jana Jiřičková
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2022, 8(4): 041505.
Paper No: NERS-21-1013
https://doi.org/10.1115/1.4050990
Published Online: June 15, 2022
View Article titled, Possible Implementation of Ex-Core Measurement in TEPLATOR Graphite Reflector
Open the PDF for Possible Implementation of Ex-Core Measurement in TEPLATOR Graphite Reflector in another window
Topics: Graphite, Neutron flux, Neutrons, Sensors, Spent nuclear fuels, Water, Fuels
Journal Articles

Neutron Field Shaping Using Graphite for Reaction Rate Measurements

Mikita Sobaleu, Michal Košťál, Jan Šimon, Evžen Losa
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2021, 7(2): 022004.
Paper No: NERS-20-1129
https://doi.org/10.1115/1.4049725
Published Online: February 19, 2021
View Article titled, Neutron Field Shaping Using Graphite for Reaction Rate Measurements
Open the PDF for Neutron Field Shaping Using Graphite for Reaction Rate Measurements in another window
Topics: Chemical kinetics, Graphite, Irradiation (Radiation exposure), Neutrons, Uncertainty, Dosimetry
Journal Articles

Xenon Behavior in Molten Salt Reactor Graphite

Terry J. Price, Ondrej Chvala, Zack Taylor
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2020, 6(4): 041303.
Paper No: NERS-19-1115
https://doi.org/10.1115/1.4046356
Published Online: June 3, 2020
View Article titled, Xenon Behavior in Molten Salt Reactor Graphite
Open the PDF for Xenon Behavior in Molten Salt Reactor Graphite in another window
Topics: Graphite, Molten salt reactors, Diffusion (Physics), Mass transfer
Journal Articles

Statistical Burnup Distribution of Moving Pebbles in the High-Temperature Reactor HTR-PM

Fanny Vitullo, Jiri Krepel, Jarmo Kalilainen, Horst-Michael Prasser, Andreas Pautz
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2020, 6(2): 021108.
Paper No: NERS-19-1059
https://doi.org/10.1115/1.4044910
Published Online: February 5, 2020
View Article titled, Statistical Burnup Distribution of Moving Pebbles in the High-Temperature Reactor HTR-PM
Open the PDF for Statistical Burnup Distribution of Moving Pebbles in the High-Temperature Reactor HTR-PM in another window
Topics: Cross section (Physics), Fuels, Simulation, Temperature, Graphite, Neutron flux, Nuclear fission, Neutrons, High temperature, Flow (Dynamics)
Journal Articles

A Review of Molten Salt Reactor Xenon Analysis Literature

T. J. Price, O. Chvala
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2020, 6(1): 011202.
Paper No: NERS-19-1008
https://doi.org/10.1115/1.4044746
Published Online: November 29, 2019
View Article titled, A Review of Molten Salt Reactor Xenon Analysis Literature
Open the PDF for A Review of Molten Salt Reactor Xenon Analysis Literature in another window
Topics: Molten salt reactors, Graphite, Bubbles, Mass transfer, Fuels, Porosity
Journal Articles

Molten Salt Reactor Xenon Analysis: Review and Decomposition

Terry J. Price, Ondrej Chvala, Zack Taylor
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2019, 5(4): 041210.
Paper No: NERS-18-1087
https://doi.org/10.1115/1.4043813
Published Online: September 3, 2019
View Article titled, Molten Salt Reactor Xenon Analysis: Review and Decomposition
Open the PDF for Molten Salt Reactor Xenon Analysis: Review and Decomposition in another window
Topics: Fuels, Graphite, Mass transfer, Molten salt reactors, Bubbles, Diffusion (Physics)
Journal Articles

Breeding Properties Study on High-Power Thorium Molten Salt Reactor

Yafen Liu, Rui Guo, Xiangzhou Cai, Rui Yan, Yang Zou, Bo Zhou
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2019, 5(1): 011003.
Paper No: NERS-17-1151
https://doi.org/10.1115/1.4041272
Published Online: January 24, 2019
View Article titled, Breeding Properties Study on High-Power Thorium Molten Salt Reactor
Open the PDF for Breeding Properties Study on High-Power Thorium Molten Salt Reactor in another window
Topics: Fuels, Molten salt reactors, Nuclides, Security, Temperature, Transients (Dynamics), Fluids, Nuclear fission, Graphite
Journal Articles

New Exploration on TMSR: Redesign of the TMSR Lattice

J. K. Zhao, S. Y. Si, Q. C. Chen, H. Bei
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2019, 5(1): 011008.
Paper No: NERS-17-1187
https://doi.org/10.1115/1.4041192
Published Online: January 24, 2019
View Article titled, New Exploration on TMSR: Redesign of the TMSR Lattice
Open the PDF for New Exploration on TMSR: Redesign of the TMSR Lattice in another window
Topics: Design, Fuels, Graphite, Optimization, Molten salt reactors, Neutrons, Cladding systems (Building), Safety
Journal Articles

Sputtering of Graphite by Hydrogen Isotopes in the Fusion Environment: A Molecular Dynamics Simulation Study

Qiang Zhao, Yang Li, Zheng Zhang, Xiaoping Ouyang
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2018, 4(4): 041022.
Paper No: NERS-17-1279
https://doi.org/10.1115/1.4040495
Published Online: September 10, 2018
View Article titled, Sputtering of Graphite by Hydrogen Isotopes in the Fusion Environment: A Molecular Dynamics Simulation Study
Open the PDF for Sputtering of Graphite by Hydrogen Isotopes in the Fusion Environment: A Molecular Dynamics Simulation Study in another window
Topics: Carbon, Graphite, Hydrogen, Ions, Isotopes, Sputtering (Irradiation), Temperature, Molecular dynamics simulation, Atoms
Journal Articles

Neutronics Analysis of Small Compact Prismatic Nuclear Reactors for Space Crafts

Xie Yang, Ding She, Lei Shi
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2018, 4(2): 021006.
Paper No: NERS-17-1123
https://doi.org/10.1115/1.4038774
Published Online: March 5, 2018
View Article titled, Neutronics Analysis of Small Compact Prismatic Nuclear Reactors for Space Crafts
Open the PDF for Neutronics Analysis of Small Compact Prismatic Nuclear Reactors for Space Crafts in another window
Topics: Accidents, Design, Fuels, Nuclear reactors, Neutrons, Temperature, Uranium, Helium, Graphite, Thermal energy
Journal Articles

The Effect of Alkali Metal and Alkaline Earth Metal Impurities on the Iodine-Induced Corrosion of CANDU Fuel Sheathing

Graham A. Ferrier, David Kerr, Joseph Metzler, Evan Veryard, Mohsen Farahani, Paul K. Chan, Mark R. Daymond, Emily C. Corcoran
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2017, 3(4): 041004.
Paper No: NERS-16-1030
https://doi.org/10.1115/1.4037115
Published Online: July 31, 2017
View Article titled, The Effect of Alkali Metal and Alkaline Earth Metal Impurities on the Iodine-Induced Corrosion of CANDU Fuel Sheathing
Open the PDF for The Effect of Alkali Metal and Alkaline Earth Metal Impurities on the Iodine-Induced Corrosion of CANDU Fuel Sheathing in another window
Topics: Alkali metals, Coatings, Corrosion, Deflection, Fuels, Metal impurities, Metals, Stress, Vapors, Oxygen
Journal Articles

Nuclear Heat Supply Fluctuation Tests by Non-Nuclear Heating With HTTR

Yoshitomo Inaba, Kenji Sekita, Takahiro Nemoto, Yuki Honda, Daisuke Tochio, Hiroyuki Sato, Shigeaki Nakagawa, Shoji Takada, Kazuhiro Sawa
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research Papers
ASME J of Nuclear Rad Sci. October 2016, 2(4): 041001.
Paper No: NERS-15-1194
https://doi.org/10.1115/1.4034320
Published Online: October 12, 2016
View Article titled, Nuclear Heat Supply Fluctuation Tests by Non-Nuclear Heating With HTTR
Open the PDF for Nuclear Heat Supply Fluctuation Tests by Non-Nuclear Heating With HTTR in another window
Topics: Coolants, Heat, Heating, Pressure, Temperature, Graphite, Helium, Heat transfer, Stress
Journal Articles

Mitigating the Stress Corrosion Cracking of Zircaloy-4 Fuel Sheathing: Siloxane Coatings Revisited

Graham A. Ferrier, Mohsen Farahani, Joseph Metzler, Paul K. Chan, Emily C. Corcoran
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2016, 2(2): 021004.
Paper No: NERS-15-1068
https://doi.org/10.1115/1.4031620
Published Online: February 29, 2016
View Article titled, Mitigating the Stress Corrosion Cracking of Zircaloy-4 Fuel Sheathing: Siloxane Coatings Revisited
Open the PDF for Mitigating the Stress Corrosion Cracking of Zircaloy-4 Fuel Sheathing: Siloxane Coatings Revisited in another window
Topics: Coatings, Graphite, Coating processes, Fuels, Siloxanes
Journal Articles

Thermal Predictions of the AGR-3/4 Experiment With Time-Varying Gas Gaps

Grant L. Hawkes, James W. Sterbentz, John T. Maki
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research Papers
ASME J of Nuclear Rad Sci. October 2015, 1(4): 041012.
Paper No: NERS-15-1006
https://doi.org/10.1115/1.4030046
Published Online: September 3, 2015
View Article titled, Thermal Predictions of the AGR-3/4 Experiment With Time-Varying Gas Gaps
Open the PDF for Thermal Predictions of the AGR-3/4 Experiment With Time-Varying Gas Gaps in another window
Topics: Fluence (Radiation measurement), Fuels, Graphite, Neutrons, Temperature, Thermal conductivity, Heat, Irradiation (Radiation exposure)
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
Open the PDF for Parametric Lattice Study of a Graphite-Moderated Molten Salt Reactor in another window
Topics: Equilibrium (Physics), Fuels, Graphite, Molten salt reactors, Neutrons, Nuclear fuel cycle, Design, Nuclear fission, Uranium
Journal Articles

Computational Fluid Dynamics Analysis for Asymmetric Power Generation in a Prismatic Fuel Block of Fluoride-Salt-Cooled High-Temperature Test Reactor

Wen-Chi Cheng, Kaichao Sun, Lin-Wen Hu, Ching-Chang Chieng
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research Papers
ASME J of Nuclear Rad Sci. January 2015, 1(1): 011003.
Paper No: NERS-14-1009
https://doi.org/10.1115/1.4026391
Published Online: February 9, 2015
View Article titled, Computational Fluid Dynamics Analysis for Asymmetric Power Generation in a Prismatic Fuel Block of Fluoride-Salt-Cooled High-Temperature Test Reactor
Open the PDF for Computational Fluid Dynamics Analysis for Asymmetric Power Generation in a Prismatic Fuel Block of Fluoride-Salt-Cooled High-Temperature Test Reactor in another window
Topics: Computational fluid dynamics, Coolants, Energy generation, Fuels, Graphite, Heat flux, Laminar flow, Temperature, Turbulence, Wall temperature