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Journal Articles

Calculation of Radiation Field and Shutdown Dose Rate for Fusion Reactor Based on cosRMC

Zhenyu Wang, Xian Zhang, Shichang Liu, Rui Che, Yixue Chen

Publisher: ASME

ASME J of Nuclear Rad Sci.

Paper No: NERS-24-1095

https://doi.org/10.1115/1.4068167

Published Online: March 13, 2025

View Articletitled, Calculation of Radiation Field and Shutdown Dose Rate for Fusion Reactor Based on cosRMC

Topics: Fusion reactors, Radiation (Physics), Algorithms, Resolution (Optics), Accuracy and precision, Computational methods, Geometry, Nuclear design, Particulate matter, Safety

Proceedings Papers

Calculation of Radiation Field and Shutdown Dose Rate for Fusion Reactor Based on cosRMC

Shichang Liu, Zhenyu Wang, Rui Che

Proc. ASME. ICONE31, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A027, August 4–8, 2024

Publisher: American Society of Mechanical Engineers

Paper No: ICONE31-134661

https://doi.org/10.1115/ICONE31-134661

View Paper titled, Calculation of Radiation Field and Shutdown Dose Rate for Fusion Reactor Based on cosRMC

Topics: Fusion reactors, Radiation (Physics), Algorithms, Resolution (Optics), Accuracy and precision, Computational methods, Geometry, Nuclear design, Particulate matter, Safety

Proceedings Papers

Study on Selection Method of Shielding Nuclides in Nuclear Reactor Based on Non-Dominated Sorting

Rui Li, Shichang Liu

Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A027, August 8–12, 2022

Publisher: American Society of Mechanical Engineers

Paper No: ICONE29-90902

https://doi.org/10.1115/ICONE29-90902

View Paper titled, Study on Selection Method of Shielding Nuclides in Nuclear Reactor Based on Non-Dominated Sorting

Topics: Nuclear reactors, Nuclides, Radiation (Physics), Neutrons, Cross section (Physics), Monte Carlo methods, Photons, Absorption, Databases, Elastic scattering

Proceedings Papers

Neutronics comparative analysis of fuel assemblies using CSG and DAGMC methods

NingYan Sun, ShiChang Liu

Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A037, August 8–12, 2022

Publisher: American Society of Mechanical Engineers

Paper No: ICONE29-91727

https://doi.org/10.1115/ICONE29-91727

View Paper titled, Neutronics comparative analysis of fuel assemblies using CSG and DAGMC methods

Topics: Fuels, Geometry, Computer-aided design, Modeling, Particulate matter, Monte Carlo methods

Proceedings Papers

Implementation and Verification of the DAGMC Module in Monte Carlo Code RMC

Pengfei Shen, Jingang Liang, Shichang Liu, Kan Wang

Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A075, August 8–12, 2022

Publisher: American Society of Mechanical Engineers

Paper No: ICONE29-93103

https://doi.org/10.1115/ICONE29-93103