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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

Nonhyperbolicity of Conservation Equations of RELAP5 Two-Fluid Model in Nuclear Reactor Safety Results (Investigation and Eigenvalue Analysis)

S. P. Saraswat, P. Munshi, C. Allison
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2021, 7(1): 011402.
Paper No: NERS-19-1022
https://doi.org/10.1115/1.4047161
Published Online: October 2, 2020
View Article titled, Nonhyperbolicity of Conservation Equations of RELAP5 Two-Fluid Model in Nuclear Reactor Safety Results (Investigation and Eigenvalue Analysis)
Open the PDF for Nonhyperbolicity of Conservation Equations of RELAP5 Two-Fluid Model in Nuclear Reactor Safety Results (Investigation and Eigenvalue Analysis) in another window
Topics: Accidents, Boiling water reactors, Eigenvalues, Fluids, Porosity, Pressure, Pressurized water reactors, Light water reactors, Water, Stability
Journal Articles

A Simplified Two-Group Multipoint Kinetics Model

Santosh K. Pradhan, K. Obaidurrahman, Kannan N. Iyer
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2021, 7(1): 011502.
Paper No: NERS-19-1155
https://doi.org/10.1115/1.4046254
Published Online: October 1, 2020
View Article titled, A Simplified Two-Group Multipoint Kinetics Model
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Topics: Eigenvalues, Heat flux, Neutrons, Steady state, Transients (Dynamics), Thermal hydraulics, Diffusion (Physics), Simulation, Circuits, Fluid dynamics
Journal Articles

The Differences Between the Two Forms of Semi-Analytical Nodal Methods on Solving the Third-Order Simplified Spherical Harmonics Method Equations

Pan Qingquan, Lu Haoliang, Li Dongsheng, Wang Kan
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2018, 4(2): 021008.
Paper No: NERS-17-1079
https://doi.org/10.1115/1.4038653
Published Online: March 5, 2018
View Article titled, The Differences Between the Two Forms of Semi-Analytical Nodal Methods on Solving the Third-Order Simplified Spherical Harmonics Method Equations
Open the PDF for The Differences Between the Two Forms of Semi-Analytical Nodal Methods on Solving the Third-Order Simplified Spherical Harmonics Method Equations in another window
Topics: Deformation, Diffusion (Physics), Eigenvalues, Neutron flux, Neutrons, Polynomials, Currents, Computational methods, Physics, Nuclear engineering
Journal Articles

A Reduced Basis Approach for Modeling the Movement of Nuclear Reactor Control Rods

Alberto Sartori, Antonio Cammi, Lelio Luzzi, Gianluigi Rozza
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2016, 2(2): 021019.
Paper No: NERS-14-1062
https://doi.org/10.1115/1.4031945
Published Online: February 29, 2016
View Article titled, A Reduced Basis Approach for Modeling the Movement of Nuclear Reactor Control Rods
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Topics: Eigenvalues, Errors, Modeling, Neutron flux, Nuclear reactors, Rods, Shapes, Approximation, Neutrons, Diffusion (Physics)