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Journal Articles

Calculation and Uncertainty Analysis of Core Parameters of Advanced Lead-Cooled Modular Nuclear Reactor Using New Nuclear Data Libraries

Thanh Mai Vu, Le Quang Linh Tran, Thi Hong Bui, Nhu Viet Ha Pham
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2024, 10(3): 031501.
Paper No: NERS-23-1039
https://doi.org/10.1115/1.4064780
Published Online: April 17, 2024
View Article titled, Calculation and Uncertainty Analysis of Core Parameters of Advanced Lead-Cooled Modular Nuclear Reactor Using New Nuclear Data Libraries
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Topics: Eigenvalues, Fast neutron reactors, Neutrons, Nuclear fission, Nuclear reactors, Uncertainty, Uncertainty analysis, Cross section (Physics), Electromagnetic scattering, Radiation scattering
Journal Articles

System Thermal-Hydraulics Model for Fluoride Salt-Cooled Reactor Based on Small Modular Advanced High Temperature Reactor (SmAHTR) Design Concept

Shujun Wang, Xianmin Huang, Blair P. Bromley
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2023, 9(4): 041302.
Paper No: NERS-23-1011
https://doi.org/10.1115/1.4062500
Published Online: September 15, 2023
View Article titled, System Thermal-Hydraulics Model for Fluoride Salt-Cooled Reactor Based on Small Modular Advanced High Temperature Reactor (SmAHTR) Design Concept
Open the PDF for System Thermal-Hydraulics Model for Fluoride Salt-Cooled Reactor Based on Small Modular Advanced High Temperature Reactor (SmAHTR) Design Concept in another window
Topics: Coolants, Cycles, Design, Flow (Dynamics), Fuels, High temperature, Modeling, Temperature, Thermal hydraulics, Steady state
Journal Articles

Thermal-Hydraulic Safety Assessment of Full-Scale ESBWR Nuclear Reactor Design

S. P. Saraswat, D. Ray, G. Mishra, D. Yadav, V. S. Bhadouria, P. Munshi, C. Allison
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2022, 8(3): 031403.
Paper No: NERS-21-1073
https://doi.org/10.1115/1.4052014
Published Online: May 26, 2022
View Article titled, Thermal-Hydraulic Safety Assessment of Full-Scale ESBWR Nuclear Reactor Design
Open the PDF for Thermal-Hydraulic Safety Assessment of Full-Scale ESBWR Nuclear Reactor Design in another window
Topics: Accidents, Boiling water reactors, Containment, Design, Pressure, Safety, Steam, Water, Heat, Economics
Journal Articles

Development of a Phase-Field Method for Phase Change Simulations Using a Conservative Allen–Cahn Equation

Akinori Tamura, Kenichi Katono
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2022, 8(3): 031402.
Paper No: NERS-21-1068
https://doi.org/10.1115/1.4052807
Published Online: May 26, 2022
View Article titled, Development of a Phase-Field Method for Phase Change Simulations Using a Conservative Allen–Cahn Equation
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Topics: Boundary-value problems, Simulation, Wetting, Vapors, Bubbles, Simulation results
Journal Articles

Development of a Phase-Field Method for Phase Change Simulations Using a Conservative Allen–Cahn Equation

Akinori Tamura, Kenichi Katono
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2022, 8(2): 021401.
Paper No: NERS-20-1182
https://doi.org/10.1115/1.4050209
Published Online: October 19, 2021
View Article titled, Development of a Phase-Field Method for Phase Change Simulations Using a Conservative Allen–Cahn Equation
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Topics: Boundary-value problems, Simulation, Wetting, Vapors, Bubbles, Simulation results
Journal Articles

Application of Monte Carlo Simulation to Design of Sampler and Detector in Radiation Monitoring System

Kei Sugihara, Hirotaka Sakai, Kanako Hattori, Genki Tanaka, Mitsunobu Hayashi, Toshiaki Ito, Naotaka Oda
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2018, 4(4): 041021.
Paper No: NERS-17-1191
https://doi.org/10.1115/1.4039968
Published Online: September 10, 2018
View Article titled, Application of Monte Carlo Simulation to Design of Sampler and Detector in Radiation Monitoring System
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Topics: Design, Gas detectors, Radiation measurement, Sensors, Simulation, Simulation results, Beta particles, Radiation (Physics)
Journal Articles

Numerical Simulation of Supercritical Carbon Dioxide Critical Flow in the Nozzle Tube

Zhou Yuan, Wang Yangle, Chen Jingtan, Xia Zhaoyang, Wang Junfeng
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2018, 4(1): 011018.
Paper No: NERS-17-1034
https://doi.org/10.1115/1.4037896
Published Online: December 4, 2017
View Article titled, Numerical Simulation of Supercritical Carbon Dioxide Critical Flow in the Nozzle Tube
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Topics: Flow (Dynamics), Nozzles, Pressure, Simulation results, Temperature, Supercritical carbon dioxide, Errors, Computer simulation, Carbon dioxide
Journal Articles

A Physically Based, One-Dimensional Two-Fluid Model for Direct Contact Condensation of Steam Jets Submerged in Subcooled Water

David Heinze, Thomas Schulenberg, Lars Behnke
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research Papers
ASME J of Nuclear Rad Sci. April 2015, 1(2): 021002.
Paper No: NERS-14-1012
https://doi.org/10.1115/1.4029417
Published Online: March 24, 2015
View Article titled, A Physically Based, One-Dimensional Two-Fluid Model for Direct Contact Condensation of Steam Jets Submerged in Subcooled Water
Open the PDF for A Physically Based, One-Dimensional Two-Fluid Model for Direct Contact Condensation of Steam Jets Submerged in Subcooled Water in another window
Topics: Condensation, Drops, Flow (Dynamics), Fluids, Jets, Steam, Water, Turbulence, Subcooling, Temperature