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Journal Articles

Neutronic and Thermal-Mechanical Coupling Schemes for Heat Pipe-Cooled Reactor Designs

Yugao Ma, Minyun Liu, Biheng Xie, Wenbin Han, Xiaoming Chai, Shanfang Huang, Hongxing Yu
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2022, 8(2): 021303.
Paper No: NERS-20-1207
https://doi.org/10.1115/1.4051612
Published Online: October 19, 2021
View Article titled, Neutronic and Thermal-Mechanical Coupling Schemes for Heat Pipe-Cooled Reactor Designs
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Topics: Design, Displacement, Fuels, Geometry, Heat, Heat pipes, Molten salt reactors, Nuclear fission, Pipes, Temperature
Journal Articles

Coupled Neutronics–Mechanics Analysis Method for Evaluation of Reactivity Change Due to Core Distortion in Sodium Fast Reactor

Janos Bodi, Alexander Ponomarev, Konstantin Mikityuk
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2022, 8(1): 011307.
Paper No: NERS-20-1183
https://doi.org/10.1115/1.4050417
Published Online: August 3, 2021
View Article titled, Coupled Neutronics–Mechanics Analysis Method for Evaluation of Reactivity Change Due to Core Distortion in Sodium Fast Reactor
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Topics: Deformation, Displacement, Finite element analysis, Geometry, Manufacturing, Sodium fast reactors, Fuels, Simulation, Absorption
Journal Articles

Verification and Validation of SuperMC3.2 Using VENUS-3 Benchmark Experiments

I. K. Baidoo, J. Zou, B. Li, J. Song, B. Wu, Q. Yang, Z. Zhao
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2019, 5(4): 041402.
Paper No: NERS-18-1123
https://doi.org/10.1115/1.4043100
Published Online: July 19, 2019
View Article titled, Verification and Validation of SuperMC3.2 Using VENUS-3 Benchmark Experiments
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Topics: Atoms, Displacement, Dosimetry, Fluence (Radiation measurement), Fuels, Geometry, Iron, Manufacturing, Modeling, Neutron flux
Journal Articles

Deceleration Performance and Parameter Influence Analysis of the Control Rod Hydraulic Deceleration Device for Control Rod Hydraulic Drive System

Qin Benke, Li Leishi, Bo Hanliang
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2019, 5(3): 031702.
Paper No: NERS-17-1229
https://doi.org/10.1115/1.4042541
Published Online: May 3, 2019
View Article titled, Deceleration Performance and Parameter Influence Analysis of the Control Rod Hydraulic Deceleration Device for Control Rod Hydraulic Drive System
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Topics: Clearances (Engineering), Cylinders, Design, Flow (Dynamics), Fuels, Hydraulic drive systems, Pressure, Scram, Temperature, Water
Journal Articles

Effects of the Foil Flatness on Irradiation Performance of U10Mo Monolithic Mini-Plates

Hakan Ozaltun, Pavel G. Medvedev, Barry H. Rabin
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research Papers
ASME J of Nuclear Rad Sci. October 2015, 1(4): 041003.
Paper No: NERS-15-1045
https://doi.org/10.1115/1.4030982
Published Online: September 16, 2015
View Article titled, Effects of the Foil Flatness on Irradiation Performance of U10Mo Monolithic Mini-Plates
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Topics: Cladding systems (Building), Fuels, Irradiation (Radiation exposure), Plates (structures), Stress, Temperature, Displacement, Density
Journal Articles

Validation Facility and Model Development for Nuclear Fuel Assembly Response to Seismic Loading

Noah A. Weichselbaum, Morteza Rahimi Abkenar, Marcos Vanella, Majid T. Manzari, Elias Balaras, Philippe M. Bardet
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research Papers
ASME J of Nuclear Rad Sci. October 2015, 1(4): 041005.
Paper No: NERS-15-1013
https://doi.org/10.1115/1.4031031
Published Online: September 16, 2015
View Article titled, Validation Facility and Model Development for Nuclear Fuel Assembly Response to Seismic Loading
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Topics: Computation, Engineering prototypes, Engineering simulation, Flow (Dynamics), Fluids, Fuel rods, Fuels, Geometry, Manufacturing, Nuclear fuels
Journal Articles

Noncontact Measurement Method of Vibration Stress Using Optical Displacement Sensors for Piping Systems in Nuclear Power Plants

Akira Maekawa, Tsuneo Takahashi, Takashi Tsuji, Michiyasu Noda
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research Papers
ASME J of Nuclear Rad Sci. July 2015, 1(3): 031002.
Paper No: NERS-14-1006
https://doi.org/10.1115/1.4029338
Published Online: May 14, 2015
View Article titled, Noncontact Measurement Method of Vibration Stress Using Optical Displacement Sensors for Piping Systems in Nuclear Power Plants
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Topics: Stress, Vibration, Pipes, Sensors, Displacement