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Keywords: Monte Carlo method
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Journal Articles

K-Edge Measurement Technology Simulation Model Design

Wen-Tao Li, Li-Xia He, Lei Bai, Xiao Zhao, Yu-Qi Zhang, Hao-Cheng Zhao
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Technical Briefs
ASME J of Nuclear Rad Sci. July 2025, 11(3): 034502.
Paper No: NERS-24-1081
https://doi.org/10.1115/1.4067724
Published Online: February 14, 2025
....com e-mail:  Yuqizhang1998@hotmail.com e-mail:  zhhc0619@163.com 25 09 2024 13 01 2025 14 02 2025 K-edge measurement technology average K-edge absorption distance X-ray source high-purity germanium detector Monte Carlo method Nuclear safeguard measures...
View Articletitled, K-Edge Measurement Technology Simulation Model Design
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Topics: Absorption, Calibration, Light sources, Photons, Sensors, Uranium, X-rays, Germanium, Simulation models, Design
Journal Articles

Neutronic and Thermal-Fluidic Analyses for an Additive Manufactured Reactor With SiC Matrix and TRISO Particle Fuel

Wenbin Han, Jian Deng, Qi Lu, Chong Chen, Youyou Xu, Tao Zhang, Shanfang Huang
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2023, 9(4): 041104.
Paper No: NERS-22-1145
https://doi.org/10.1115/1.4062119
Published Online: April 17, 2023
... in Reactor Physics - Linking Research, Industry, and Education , American Nuclear Society , Knoxville, TN, LaGrange Park, IL , Apr. 15–20, p. CD-ROM15 . 24 10 2022 13 02 2023 17 04 2023 additive manufacturing reactor design Monte Carlo method computational fluid dynamics...
View Articletitled, Neutronic and Thermal-Fluidic Analyses for an Additive Manufactured Reactor With SiC Matrix and TRISO Particle Fuel
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Topics: Additive manufacturing, Computational fluid dynamics, Design, Fuels, Particulate matter, Temperature, Coolants, Neutrons, Heat transfer, Computer software
Journal Articles

Neutronic and Thermal-Mechanical Coupling Schemes for Heat Pipe-Cooled Reactor Designs

Yugao Ma, Minyun Liu, Biheng Xie, Wenbin Han, Xiaoming Chai, Shanfang Huang, Hongxing Yu
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2022, 8(2): 021303.
Paper No: NERS-20-1207
https://doi.org/10.1115/1.4051612
Published Online: October 19, 2021
... . 10.1063/1.1659844 01 12 2020 23 06 2021 19 10 2021 heat pipe cooled reactor neutronic and thermal-mechanical coupling reactor design Monte Carlo method finite element method Ambitious space explorations in the near future need safe, reliable, long-term, and self...
View Articletitled, Neutronic and Thermal-Mechanical Coupling Schemes for Heat Pipe-Cooled Reactor Designs
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Topics: Design, Displacement, Fuels, Geometry, Heat, Heat pipes, Molten salt reactors, Nuclear fission, Pipes, Temperature
Journal Articles

A New Global Variance Reduction Technique Based on Geometry and Energy Splitting/Roulette

Z. Zheng, R. Li, Y. Zhou, Q. Mei, L. Deng
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2020, 6(1): 011102.
Paper No: NERS-18-1130
https://doi.org/10.1115/1.4045030
Published Online: November 8, 2019
... of CAP1400 Based on JMCT-S Code ,” ASME Paper No. ICONE25-66429. 10.1115/ICONE25-66429 e-mail:  zhengzheng@snerdi.com.cn 03 12 2018 01 09 2019 08 11 2019 global variance reduction Monte Carlo method discrete ordinates method HBR-2 benchmark CAP1400 As one...
View Articletitled, A New Global Variance Reduction Technique Based on Geometry and Energy Splitting/Roulette
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Topics: Computers, Errors, Fluence (Radiation measurement), Geometry, Neutrons, Particulate matter, Phase space, Photons, Weight (Mass), Dosimeters