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Proceedings Papers

Neutron Physics Characterization & Optimization Analysis of the ACPR100 Small Modular Reactor

Songyang Liu, Xiang Wang
Proc. ASME. ICONE28, Volume 1: Operating Plant Challenges, Successes, and Lessons Learned; Nuclear Plant Engineering; Advanced Reactors and Fusion; Small Modular and Micro-Reactors Technologies and Applications, V001T04A014, August 4–6, 2021
Paper No: ICONE28-65689
DOI: https://doi.org/10.1115/ICONE28-65689
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Topics: Isotopes, Neutrons, Optimization, Physics, Small modular reactors, Temperature, Cycles, Design, Fuels, China
Proceedings Papers

A Sodium-Cooled Thermal-Spectrum Fission Battery

Patrick J. McDaniel, Charles Forsberg
Proc. ASME. ICONE28, Volume 1: Operating Plant Challenges, Successes, and Lessons Learned; Nuclear Plant Engineering; Advanced Reactors and Fusion; Small Modular and Micro-Reactors Technologies and Applications, V001T04A015, August 4–6, 2021
Paper No: ICONE28-65765
DOI: https://doi.org/10.1115/ICONE28-65765
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Topics: Batteries, Nuclear fission, Sodium, Heat, Neutrons, Uranium, Carbon, Data centers, Design, Economics
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
Paper No: ICONE28-64154
DOI: https://doi.org/10.1115/ICONE28-64154
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Topics: Failure, Fuels, Probability, Very high temperature reactors, Irradiation (Radiation exposure), Particulate matter, Stress, Materials properties, Temperature, Anisotropy
Proceedings Papers

Dynamic Characteristics Analysis of NuScale in Frequency Domain

Jingrui Yang, Qian Ma, Lingtong Han, Peiwei Sun
Proc. ASME. ICONE28, Volume 1: Operating Plant Challenges, Successes, and Lessons Learned; Nuclear Plant Engineering; Advanced Reactors and Fusion; Small Modular and Micro-Reactors Technologies and Applications, V001T02A016, August 4–6, 2021
Paper No: ICONE28-64460
DOI: https://doi.org/10.1115/ICONE28-64460
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Topics: Boilers, Coolants, Design, Electric power generation, Feedwater, Flow (Dynamics), Frequency-domain analysis, Heating, Momentum, Neutrons
Proceedings Papers

Conceptual Study of Neutron Physics of Nuclear Fuel Cycle for Ceramic Fast Reactor

Xuesong Yan, Yaling Zhang, Yucui Gao, Lei Yang
Proc. ASME. ICONE28, Volume 1: Operating Plant Challenges, Successes, and Lessons Learned; Nuclear Plant Engineering; Advanced Reactors and Fusion; Small Modular and Micro-Reactors Technologies and Applications, V001T03A008, August 4–6, 2021
Paper No: ICONE28-65406
DOI: https://doi.org/10.1115/ICONE28-65406
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Topics: Ceramics, Fast neutron reactors, High temperature, Neutrons, Nuclear fuel cycle, Physics, Spent nuclear fuels
Proceedings Papers

Features of a BWR Neutron Absorber Melt Relocation in an Oxidative Environment During the CLADS-MADE-02 Test

Anton Pshenichnikov, Yuji Nagae, Masaki Kurata
Proc. ASME. ICONE28, Volume 3: Computational Fluid Dynamics (CFD); Verification and Validation; Advanced Methods of Manufacturing (AMM) for Nuclear Reactors and Components; Decontamination, Decommissioning, and Radioactive Waste Management; Beyond Design Basis and Nuclear Safety; Risk Informed Management and Regulation, V003T11A012, August 4–6, 2021
Paper No: ICONE28-65129
DOI: https://doi.org/10.1115/ICONE28-65129
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Topics: Accidents, Blades, Boiling water reactors, Fukushima nuclear disaster, Japan, 2011, Neutrons
Proceedings Papers

Calculation of Probability of Survival (POS) in Dynamic Systems Based on RMC Code

Conglong Jia, Guanlin Shi, Zhiyuan Feng, Xiaoyu Guo, Kan Wang, Shanfang Huang, Jingang Liang
Proc. ASME. ICONE28, Volume 4: Student Paper Competition, V004T14A021, August 4–6, 2021
Paper No: ICONE28-64077
DOI: https://doi.org/10.1115/ICONE28-64077
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Topics: Dynamic systems, Probability, Neutrons, Chain, Interpolation, Neutron sources, Particulate matter, Simulation
Proceedings Papers

Dropping-Rod Analysis of Control Rod in ADS Lead-Bismuth Alloy Zero-Power Reactor

Hui Fu, Daogang Lu, Yu Liu
Proc. ASME. ICONE28, Volume 3: Computational Fluid Dynamics (CFD); Verification and Validation; Advanced Methods of Manufacturing (AMM) for Nuclear Reactors and Components; Decontamination, Decommissioning, and Radioactive Waste Management; Beyond Design Basis and Nuclear Safety; Risk Informed Management and Regulation, V003T12A012, August 4–6, 2021
Paper No: ICONE28-64082
DOI: https://doi.org/10.1115/ICONE28-64082
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Topics: Alloys, Safety, Earthquakes, Collisions (Physics), Computer simulation, Coolants, Finite element methods, Leakage, Neutrons, Nuclear fuels
Proceedings Papers

Analysis and Research on Sodium Single Droplet Combustion

Lei Zhao
Proc. ASME. ICONE28, Volume 3: Computational Fluid Dynamics (CFD); Verification and Validation; Advanced Methods of Manufacturing (AMM) for Nuclear Reactors and Components; Decontamination, Decommissioning, and Radioactive Waste Management; Beyond Design Basis and Nuclear Safety; Risk Informed Management and Regulation, V003T12A020, August 4–6, 2021
Paper No: ICONE28-64402
DOI: https://doi.org/10.1115/ICONE28-64402
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Topics: Combustion, Drops, Sodium, Fire, Sodium fast reactors, Oxygen, Absorption, Accidents, Chemical properties, Chemical reactions
Proceedings Papers

Key Parameters Determination of Integral-Plate Cruciform Control Rod

Hao Zhang, Songyang Li, Dingqu Wang, Yueyuan Jiang, Wentao Hao, Wei Xiong, Jizhong Ma
Proc. ASME. ICONE28, Volume 4: Student Paper Competition, V004T14A027, August 4–6, 2021
Paper No: ICONE28-64220
DOI: https://doi.org/10.1115/ICONE28-64220
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Topics: Absorption, Cladding systems (Building), Design, Economics , Equipment performance, Heating, Manufacturing, Neutrons, Plates (structures), Weight (Mass)
Proceedings Papers

Improvement of Conversion Ratio of Thorium Fuel in LWR by Adding Neutron Absorber

Taichi Takeishi, Satoshi Takeda, Takanori Kitada
Proc. ASME. ICONE28, Volume 4: Student Paper Competition, V004T14A078, August 4–6, 2021
Paper No: ICONE28-65683
DOI: https://doi.org/10.1115/ICONE28-65683
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Topics: Fuels, Light water reactors, Neutrons
Proceedings Papers

Neutronic/Thermal-Hydraulic Coupling Analysis of Xi'an Pulsed Reactor Based on RMC and COBRA-TF

Ruihan Li, Jianzhu Cao, Lipeng Wang, Xinyi Zhang, Xiaoyu Guo, Jingang Liang
Proc. ASME. ICONE28, Volume 4: Student Paper Competition, V004T14A059, August 4–6, 2021
Paper No: ICONE28-64623
DOI: https://doi.org/10.1115/ICONE28-64623
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Topics: Fuel rods, Monte Carlo methods, Neutrons, Physics, Simulation, Steady state, Temperature
Proceedings Papers

All-Coefficient Adaptive Control System Design for a Space Nuclear Reactor

Qian Ma, Zhitong Yu, Peiwei Sun, Yuwen Jia, Shifa Wu
Proc. ASME. ICONE28, Volume 4: Student Paper Competition, V004T14A043, August 4–6, 2021
Paper No: ICONE28-64459
DOI: https://doi.org/10.1115/ICONE28-64459
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Topics: Adaptive control, Design, Nuclear reactors, Control systems, Feedback, Fuels, Transfer functions, Ceramics, Control equipment, Dynamic models
Proceedings Papers

Numerical Simulation of Multi-Physics Processes in Nuclear System Based on Galerkin Finite Element Method

Baoxin Yuan, Wankui Yang, Songbao Zhang, Bin Zhong, Junxia Wei, Yangjun Ying
Proc. ASME. ICONE2020, Volume 1: Beyond Design Basis; Codes and Standards; Computational Fluid Dynamics (CFD); Decontamination and Decommissioning; Nuclear Fuel and Engineering; Nuclear Plant Engineering, V001T02A005, August 4–5, 2020
Paper No: ICONE2020-16801
DOI: https://doi.org/10.1115/ICONE2020-16801
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Topics: Computer simulation, Finite element methods, Physics, Heat, Heat transfer, Temperature, Thermoelasticity, Finite element analysis, Neutron flux, Neutrons
Proceedings Papers

Study on On-Site Calibration Method of Stationary Neutron Dosimeter

Jinxu Lv, Ning Lv, Huiping Guo, Mingyan Sun, Kuo Zhao, Wenhui Lv, Zhihao Wei, Qizhan Xiao, Daji Li, Yang Liu
Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T08A014, August 4–5, 2020
Paper No: ICONE2020-16144
DOI: https://doi.org/10.1115/ICONE2020-16144
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Topics: Calibration, Dosimeters, Neutrons
Proceedings Papers

Nuclear Material Measurement Based on Fast Neutron Multiplicity Counter

Xianghua Su, Quanhu Zhang, Suxia Hou, Sufen Li, Jianqing Yang, Linjun Hou, Qifan Chen, Zhichun Xu
Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T08A016, August 4–5, 2020
Paper No: ICONE2020-16151
DOI: https://doi.org/10.1115/ICONE2020-16151
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Topics: Neutrons
Proceedings Papers

Stress Analysis of the Pressurized-Water Reactor Control Rod Under Operating Conditions

Leo A. Carrilho
Proc. ASME. ICONE2020, Volume 1: Beyond Design Basis; Codes and Standards; Computational Fluid Dynamics (CFD); Decontamination and Decommissioning; Nuclear Fuel and Engineering; Nuclear Plant Engineering, V001T05A015, August 4–5, 2020
Paper No: ICONE2020-16872
DOI: https://doi.org/10.1115/ICONE2020-16872
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Topics: Pressurized water reactors, Stress, Stress analysis (Engineering), Water, Cladding systems (Building), Finite element model, Fluence (Radiation measurement), Temperature, Thermal expansion, Coolants
Proceedings Papers

Simulation and Construction of Fast Neutron Multi-Counter Based on Liquid Flash

Qifan Chen, Quanhu Zhang, Suxia Hou, Sufen Li, Jianqing Yang, Xianghua Su, Linjun Hou, Zhichun Xu
Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T08A017, August 4–5, 2020
Paper No: ICONE2020-16152
DOI: https://doi.org/10.1115/ICONE2020-16152
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Topics: Construction, Neutrons, Simulation
Proceedings Papers

Study on Preparation Process and Properties of High Hydrogen Content Concrete for Neutron Shielding

Li Yuanyuan, Pan Xiaoqiang, Huang Xiulin, Wu Ying, Yang Jing
Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T08A046, August 4–5, 2020
Paper No: ICONE2020-16631
DOI: https://doi.org/10.1115/ICONE2020-16631
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Topics: Boron, Cements (Adhesives), Concretes, Hydrogen, Neutrons
Proceedings Papers

Development of Three-Dimensional Distribution Visualization Technology for Boron Using Energy Resolved Neutron-Imaging System (RADEN)

Yuta Abe, Yusuke Tsuchikawa, Tetsuya Kai, Yoshihiro Matsumoto, Joseph D. Parker, Takenao Shinohara, Yuji Ohishi, Takashi Kamiyama, Yuji Nagae, Ikken Sato
Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T08A050, August 4–5, 2020
Paper No: ICONE2020-16723
DOI: https://doi.org/10.1115/ICONE2020-16723
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Topics: Boron, Fukushima nuclear disaster, Japan, 2011, Imaging, Melting, Neutrons, Nuclear decommissioning, Nuclear power stations, Visualization