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Keywords: Fusion Engineering
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Journal Articles

Analysis of the Effect of Beam Divergence Angle on Back-Streaming Electron Region in Ion Source for EAST-Neutral Beam Injection

Hu Chundong, Wu Mingshan, Xie Yahong, Wei Jianglong, Yu Ling
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Technical Briefs
ASME J of Nuclear Rad Sci. July 2018, 4(3): 034501.
Paper No: NERS-17-1266
DOI: https://doi.org/10.1115/1.4039694
Published Online: May 16, 2018
... manuscript received March 4, 2018; published online May 16, 2018. Assoc. Editor: Michal Kostal. 31 10 2017 04 03 2018 Fusion Engineering A 4 MW neutral beam injection (NBI) system based on the positive ion source has been used to plasma heating and current drive for Experimental...
View Article titled, Analysis of the Effect of Beam Divergence Angle on Back-Streaming Electron Region in Ion Source for EAST-Neutral Beam Injection
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Topics: Electrons, Ions, Silencers, Heat
Journal Articles

Thermal Hydraulic Safety Assessment of LLCB Test Blanket System in ITER Using Modified relap/scdapsim/mod4.0 Code

S. P. Saraswat, P. Munsh, A. Khanna, C. Allison
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2018, 4(2): 021001.
Paper No: NERS-16-1138
DOI: https://doi.org/10.1115/1.4038823
Published Online: March 5, 2018
.... Editor: Igor Pioro. 09 10 2016 08 12 2017 Fusion Engineering Next generation reactors Nuclear safety Research reactors Thermal hydraulics Security Lithium lead ceramic breeder (LLCB) test blanket module (TBM) is one of the TBM concepts for test in International...
View Article titled, Thermal Hydraulic Safety Assessment of LLCB Test Blanket System in ITER Using Modified relap/scdapsim/mod4.0 Code
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Topics: Accidents, Coolants, Heat, Helium, Pressure, Vessels, Water, Safety, Temperature, Vacuum
Journal Articles

Ex-Vessel Loss of Coolant Accident Analysis of ITER Divertor Cooling System Using Modified RELAP/SCADAPSIM/Mod 4.0

S. P. Saraswat, P. Munshi, A. Khanna, C. Allison
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2017, 3(4): 041009.
Paper No: NERS-17-1021
DOI: https://doi.org/10.1115/1.4037188
Published Online: July 31, 2017
.... Advanced reactors Fusion Engineering Nuclear engineering Research reactors Thermal hydraulics Standards Licensing Regulatory issues Codes Copyright © 2017 by ASME 2017 2332-8983/2017/3(4)/041009/13/ $25.00 ...
View Article titled, Ex-Vessel Loss of Coolant Accident Analysis of ITER Divertor Cooling System Using Modified RELAP/SCADAPSIM/Mod 4.0
Click here to open pdf in another window PDF for Ex-Vessel Loss of Coolant Accident Analysis of ITER Divertor Cooling System Using Modified RELAP/SCADAPSIM/Mod 4.0
Topics: Accidents, Coolants, Flow (Dynamics), Vessels, Temperature, Heat, Pressure, Cooling systems, Water, Tungsten
Journal Articles

Experimental Study on Cavitation of a Liquid Lithium Jet for International Fusion Materials Irradiation Facility

Hiroo Kondo, Takuji Kanemura, Tomohiro Furukawa, Yasushi Hirakawa, Eiichi Wakai, Juan Knaster
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2017, 3(4): 041005.
Paper No: NERS-16-1045
DOI: https://doi.org/10.1115/1.4036513
Published Online: July 31, 2017
... project. Fusion Engineering Nuclear engineering Thermal hydraulics 26 04 2016 04 04 2017 Manuscript received April 26, 2016; final manuscript received April 4, 2017; published online July 31, 2017. Assoc. Editor: Lin-wen Hu. 2 Present address: Michigan State University...
View Article titled, Experimental Study on Cavitation of a Liquid Lithium Jet for International Fusion Materials Irradiation Facility
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Topics: Acoustic intensity, Acoustics, Cavitation, Noise (Sound), Pressure, Sensors, Waves, Flow (Dynamics), Pipes, Irradiation (Radiation exposure)
Journal Articles

Thermal Hydraulic and Safety Assessment of First Wall Helium Cooling System of a Generalized Test Blanket System in ITER Using RELAP/SCDAPSIM/MOD4.0 Code

S. P. Saraswat, P. Munshi, A. Khanna, C. Allison
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Technical Briefs
ASME J of Nuclear Rad Sci. January 2017, 3(1): 014503.
Paper No: NERS-16-1012
DOI: https://doi.org/10.1115/1.4034680
Published Online: December 20, 2016
... , “ Analysis of the Reference Accidental Sequence for Safety Assessment of LLCB TBM System, Fusion Engineering and Design ,” 87 , 747 – 752 . Design-basis event Fusion Engineering Nuclear engineering Systems reliability Thermal hydraulics Systems performance Currently, different countries...
View Article titled, Thermal Hydraulic and Safety Assessment of First Wall Helium Cooling System of a Generalized Test Blanket System in ITER Using RELAP/SCDAPSIM/MOD4.0 Code
Click here to open pdf in another window PDF for Thermal Hydraulic and Safety Assessment of First Wall Helium Cooling System of a Generalized Test Blanket System in ITER Using RELAP/SCDAPSIM/MOD4.0 Code
Topics: Accidents, Coolants, Flow (Dynamics), Heat, Helium, Vessels, Safety, Cooling systems, Design, Temperature