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Journal Articles

Method Based on Characteristic Ray Information for Arbitrary Geometry Volume Calculation in NECP-X

Xinyu Zhou, Zhouyu Liu, Lu Cao, Liangzhi Cao, Hongchun Wu, Yu Han, Chuntao Tang
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2020, 6(2): 021901.
Paper No: NERS-19-1024
DOI: https://doi.org/10.1115/1.4045035
Published Online: February 24, 2020
View Article titled, Method Based on Characteristic Ray Information for Arbitrary Geometry Volume Calculation in NECP-X
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Topics: Errors, Geometry, Interpolation, Polynomials, Octrees, Sampling methods, Virtual reality
Journal Articles

Application of Stiffness Confinement Method in Transient Transport Calculation

Chuntao Tang
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2020, 6(1): 011107.
Paper No: NERS-19-1033
DOI: https://doi.org/10.1115/1.4044749
Published Online: November 8, 2019
View Article titled, Application of Stiffness Confinement Method in Transient Transport Calculation
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Topics: Density, Neutrons, Stiffness, Transients (Dynamics), Diffusion (Physics)
Proceedings Papers

Numerical Comparison and Analysis of Nuclear Core Design Code System SCAP and MPACT

Weiyan Yang, Chuntao Tang, Hongbo Zhang, Bo Yang
Proc. ASME. ICONE25, Volume 3: Nuclear Fuel and Material, Reactor Physics and Transport Theory; Innovative Nuclear Power Plant Design and New Technology Application, V003T02A017, July 2–6, 2017
Paper No: ICONE25-66567
DOI: https://doi.org/10.1115/ICONE25-66567
View Paper titled, Numerical Comparison and Analysis of Nuclear Core Design Code System SCAP and MPACT
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Topics: Design, Nuclear power stations, Boron, Cycles, Electrical measurement, Nuclear engineering, Simulation
Proceedings Papers

Development and Verification of the PWR Lattice Code PANDA

Hongbo Zhang, Chuntao Tang, Weiyan Yang, Guangwen Bi, Bo Yang
Proc. ASME. ICONE25, Volume 3: Nuclear Fuel and Material, Reactor Physics and Transport Theory; Innovative Nuclear Power Plant Design and New Technology Application, V003T02A018, July 2–6, 2017
Paper No: ICONE25-66573
DOI: https://doi.org/10.1115/ICONE25-66573
View Paper titled, Development and Verification of the PWR Lattice Code PANDA
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Topics: Pressurized water reactors, Collapse, Cross section (Physics), Design, Nuclear design, Nuclear engineering, Physics, Resonance
Proceedings Papers

Development and Application of Cobalt Adjuster Rod for 60 Co Medical Radioactive Sources Production in CANDU-6 Reactor

Jie Ding, Yu Dang, Libing Zhu, Chuntao Tang, Hui Li, Huimin Qin
Proc. ASME. ICONE25, Volume 3: Nuclear Fuel and Material, Reactor Physics and Transport Theory; Innovative Nuclear Power Plant Design and New Technology Application, V003T02A022, July 2–6, 2017
Paper No: ICONE25-66623
DOI: https://doi.org/10.1115/ICONE25-66623
View Paper titled, Development and Application of Cobalt Adjuster Rod for 60 Co Medical Radioactive Sources Production in CANDU-6 Reactor
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Topics: Biomedicine, Cobalt, Design, Safety, Manufacturing, Nuclear design
Proceedings Papers

Control Strategy of Soluble Boron-Free Operation for a Small PWR

Guangwen Bi, Chuntao Tang, Bo Yang
Proc. ASME. ICONE25, Volume 3: Nuclear Fuel and Material, Reactor Physics and Transport Theory; Innovative Nuclear Power Plant Design and New Technology Application, V003T13A007, July 2–6, 2017
Paper No: ICONE25-66570
DOI: https://doi.org/10.1115/ICONE25-66570
View Paper titled, Control Strategy of Soluble Boron-Free Operation for a Small PWR
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Topics: Boron, Pressurized water reactors