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Proceedings Papers

Preliminary Study on Three-Dimensional Characteristics of Modular High Temperature Gas-Cooled Reactor

Haojie Zhang, Yanhua Zheng, Ding She, Lei Shi
Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A057, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-91754
https://doi.org/10.1115/ICONE29-91754
View Paper titled, Preliminary Study on Three-Dimensional Characteristics of Modular High Temperature Gas-Cooled Reactor
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Topics: Rods, Very high temperature reactors
Proceedings Papers

Validation of NUIT for Nuclides Composition Calculation With PWR Spent Fuel Isotropic Measurement

Kai Tan, Ruihan Li, Jian Li, Jingang Liang, Ding She
Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A053, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-91659
https://doi.org/10.1115/ICONE29-91659
View Paper titled, Validation of NUIT for Nuclides Composition Calculation With PWR Spent Fuel Isotropic Measurement
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Topics: Nuclides, Pressurized water reactors, Spent nuclear fuels, Density, Errors, Accuracy and precision, Fuels, Heat, Isotopes, Nuclear fission
Proceedings Papers

Validation of NUIT for Decay Heat Predictions of PWR Spent Fuel Assemblies

Jian Li, Ruihan Li, Ding She, Jin'gang Liang, Lei Shi
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A008, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-89241
https://doi.org/10.1115/ICONE29-89241
View Paper titled, Validation of NUIT for Decay Heat Predictions of PWR Spent Fuel Assemblies
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Topics: Heat, Pressurized water reactors, Spent nuclear fuels, Fuels, Neutrons, Boiling water reactors, Collapse, Cooling, Cross section (Physics), Density
Proceedings Papers

The Study of a New Efficient Monte Carlo Method for Deep-Penetration Transport

Tao Zhang, Zhihong Liu, Ding She, Jing Zhao
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A058, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92621
https://doi.org/10.1115/ICONE29-92621
View Paper titled, The Study of a New Efficient Monte Carlo Method for Deep-Penetration Transport
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Topics: Monte Carlo methods
Proceedings Papers

Sensitivity Study on TRISO Fuel Failure Probability Evaluation for HTGR

Jian Li, Ding She, Lei Shi
Proc. ASME. ICONE28, Volume 2: Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics, V002T05A008, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-64154
https://doi.org/10.1115/ICONE28-64154
View Paper titled, Sensitivity Study on TRISO Fuel Failure Probability Evaluation for HTGR
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Topics: Failure, Fuels, Probability, Very high temperature reactors, Irradiation (Radiation exposure), Particulate matter, Stress, Materials properties, Temperature, Anisotropy
Proceedings Papers

Preliminary Neutronics and Thermal-Hydraulics Study on Thorium-Based HTR-PM With Outer Breeding Zone

Qiudong Wang, Bing Xia, Jiong Guo, Ding She, Lei Shi, Zuoyi Zhang
Proc. ASME. ICONE26, Volume 5: Advanced Reactors and Fusion Technologies; Codes, Standards, Licensing, and Regulatory Issues, V005T05A019, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81975
https://doi.org/10.1115/ICONE26-81975
View Paper titled, Preliminary Neutronics and Thermal-Hydraulics Study on Thorium-Based HTR-PM With Outer Breeding Zone
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Topics: Thermal hydraulics, Fuels, Design, Heavy metals, Temperature, Accidents, Optimization, Particulate matter, Safety
Proceedings Papers

Preliminary Development of a TRISO Fuel Performance Analysis Code: FFAT

Jian Li, Ding She, Lei Shi, Jing Zhao
Proc. ASME. ICONE26, Volume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory, V003T02A046, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82242
https://doi.org/10.1115/ICONE26-82242
View Paper titled, Preliminary Development of a TRISO Fuel Performance Analysis Code: FFAT
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Topics: Fuels, Particulate matter, Failure, Very high temperature reactors, Accidents, Equipment performance, Gas cooled reactors, High temperature, Pressure vessels, Probability
Journal Articles

Research on MMPA Algorithm for Solving Detailed Depletion Chain With the NUIT Code

Jian Li, Ding She, Lei Shi
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2018, 4(2): 021007.
Paper No: NERS-17-1089
https://doi.org/10.1115/1.4038771
Published Online: March 5, 2018
View Article titled, Research on MMPA Algorithm for Solving Detailed Depletion Chain With the NUIT Code
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Topics: Algorithms, Chain, Errors, Nuclides, Polynomial approximation, Physics
Journal Articles

Neutronics Analysis of Small Compact Prismatic Nuclear Reactors for Space Crafts

Xie Yang, Ding She, Lei Shi
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2018, 4(2): 021006.
Paper No: NERS-17-1123
https://doi.org/10.1115/1.4038774
Published Online: March 5, 2018
View Article titled, Neutronics Analysis of Small Compact Prismatic Nuclear Reactors for Space Crafts
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Topics: Accidents, Design, Fuels, Nuclear reactors, Neutrons, Temperature, Uranium, Helium, Graphite, Thermal energy
Proceedings Papers

Neutronics Analyses of Small Compact Prismatic Nuclear Reactors for the Preliminary Design

Xie Yang, Lei Shi, Ding She
Proc. ASME. ICONE25, Volume 5: Advanced and Next Generation Reactors, Fusion Technology; Codes, Standards, Conformity Assessment, Licensing, and Regulatory Issues, V005T05A012, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66290
https://doi.org/10.1115/ICONE25-66290
View Paper titled, Neutronics Analyses of Small Compact Prismatic Nuclear Reactors for the Preliminary Design
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Topics: Design, Nuclear reactors, Accidents, Helium, Alloys, Brayton cycle, Energy conversion, Energy resources, Fuels, Graphite
Proceedings Papers

Research on Detailed Depletion Chain Solving Algorithm With the NUIT Code

Jian Li, Ding She, Lei Shi
Proc. ASME. ICONE25, Volume 3: Nuclear Fuel and Material, Reactor Physics and Transport Theory; Innovative Nuclear Power Plant Design and New Technology Application, V003T02A008, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66238
https://doi.org/10.1115/ICONE25-66238
View Paper titled, Research on Detailed Depletion Chain Solving Algorithm With the NUIT Code
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Topics: Algorithms, Chain, Nuclides, Approximation, Polynomial approximation
Proceedings Papers

RMC1.0: Development of Monte Carlo Code for Reactor Analysis

Ding She, Qi Xu, Kan Wang, Ganglin Yu
Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 2, 127-131, May 17–21, 2010
Publisher: American Society of Mechanical Engineers
Paper No: ICONE18-29482
https://doi.org/10.1115/ICONE18-29482
View Paper titled, RMC1.0: Development of Monte Carlo Code for Reactor Analysis
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Topics: Collisions (Physics), Eigenvalues, Geometry