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Proceedings Papers

The Core Design Modifications for Stirling Thermal-Electric Integrated Micro Reactor

Xia Yan, Xuedong Ou, Mingqiang Lin, Jian Mou, Shaolei Sun, Chunyun Chi, Chunqing Zhao, Qin Zhou
Proc. ASME. ICONE29, Volume 12: Innovative and Smart Nuclear Power Plant Design, V012T12A045, August 8–12, 2022
Paper No: ICONE29-93465
https://doi.org/10.1115/ICONE29-93465
View Paper titled, The Core Design Modifications for Stirling Thermal-Electric Integrated Micro Reactor
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Topics: Design, Fuels, Compression, Coolants, Flow (Dynamics), Generators, Gravity (Force), Heat, Heat transfer, Nuclear design
Proceedings Papers

Reliability Analysis of Active Reactor Pit Flooding Function of EHR DFT System of a NPP Using an Enhanced Component-Connection Method

Dingqing Guo, Shaoxuan Wang, Daochuan Ge, Lili Tong, Xuewu Cao
Proc. ASME. ICONE29, Volume 13: Risk Assessments and Management, V013T13A020, August 8–12, 2022
Paper No: ICONE29-91669
https://doi.org/10.1115/ICONE29-91669
View Paper titled, Reliability Analysis of Active Reactor Pit Flooding Function of EHR DFT System of a NPP Using an Enhanced Component-Connection Method
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Topics: Event history analysis, Floods, Nuclear power stations, Reliability, Safety, Failure, Probability, Design, Redundancy (Engineering), Trains
Proceedings Papers

Construction and Application of Mitigation System Performance Index (MSPI) Platform for a China Nuclear Power Plant

Jie Zhang, Jing Wang, Peiying Zhang, Kun Tan, Minxue Yang
Proc. ASME. ICONE29, Volume 13: Risk Assessments and Management, V013T13A024, August 8–12, 2022
Paper No: ICONE29-91837
https://doi.org/10.1115/ICONE29-91837
View Paper titled, Construction and Application of Mitigation System Performance Index (MSPI) Platform for a China Nuclear Power Plant
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Topics: China, Construction, Nuclear power stations, Water, Safety, Risk, Accidents, Maintenance, Pressurized water reactors, Cooling
Proceedings Papers

Probability Safety Analysis for Nuclear Power Plant Long-Term Temporary Shutdown State

Yanzhu Chen, Zhi Yang
Proc. ASME. ICONE29, Volume 13: Risk Assessments and Management, V013T13A021, August 8–12, 2022
Paper No: ICONE29-91782
https://doi.org/10.1115/ICONE29-91782
View Paper titled, Probability Safety Analysis for Nuclear Power Plant Long-Term Temporary Shutdown State
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Topics: Nuclear power stations, Probability, Safety, Risk, Maintenance, Damage, Heat, Power grids, Power stations, Sensitivity analysis
Proceedings Papers

Development and Verification of Heat Pipe and Fin Radiation Heat Dissipation Program Based on MOOSE Platform

Sipeng Wang, Xiaoquan Chen, Rui Tian
Proc. ASME. ICONE29, Volume 14: Computer Code Verification and Validation; Nuclear Education and Public Acceptance, V014T14A005, August 8–12, 2022
Paper No: ICONE29-92418
https://doi.org/10.1115/ICONE29-92418
View Paper titled, Development and Verification of Heat Pipe and Fin Radiation Heat Dissipation Program Based on MOOSE Platform
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Topics: Energy dissipation, Fins, Heat, Heat pipes, Radiation (Physics)
Proceedings Papers

The Research on the Risk Monitor With Specific Plant Configuration at Shutdown Mode for VVER Nuclear Reactor

Fangyu Dong, Jinyan Du, Chao Ma, Wei Deng, Qingqing Xu, Rui Zhang
Proc. ASME. ICONE29, Volume 13: Risk Assessments and Management, V013T13A019, August 8–12, 2022
Paper No: ICONE29-91663
https://doi.org/10.1115/ICONE29-91663
View Paper titled, The Research on the Risk Monitor With Specific Plant Configuration at Shutdown Mode for VVER Nuclear Reactor
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Topics: Heat, Nuclear reactors, Probabilistic safety assessment, Risk, Risk monitoring, Risk management, Design, Nuclear power stations, Decision making, Maintenance
Proceedings Papers

A Transient Model of Sodium Heat Pipe With Phase Change Temperature Difference

Ruicheng Zhong, Yugao Ma, Qingzhu Zhao, Jian Deng, Yu Liu, Shuhua Ding
Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A085, August 8–12, 2022
Paper No: ICONE29-92202
https://doi.org/10.1115/ICONE29-92202
View Paper titled, A Transient Model of Sodium Heat Pipe With Phase Change Temperature Difference
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Topics: Condensation, Evaporation, Flow (Dynamics), Heat pipes, Sodium, Temperature, Thermal resistance, Transients (Dynamics), Steady state, Heat transfer
Proceedings Papers

Effect of Water Jet Behavior on the Operating Range in Supersonic Steam Injector

Yukiya Minamizono, Akiko Kaneko
Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A021, August 8–12, 2022
Paper No: ICONE29-90414
https://doi.org/10.1115/ICONE29-90414
View Paper titled, Effect of Water Jet Behavior on the Operating Range in Supersonic Steam Injector
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Topics: Ejectors, Water, Steam, Pressure, Accidents, Internal flow, Stability, Condensation, Condensers (steam plant), Cooling
Proceedings Papers

Quantitative Risk Assessment With CMMC Method on Abnormal Snowfall Incident for a Sodium-Cooled Fast Reactor

Risako Nakashima, Akari Koike, Takaaki Sakai, Norihiro Doda, Masaaki Tanaka
Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A107, August 8–12, 2022
Paper No: ICONE29-93039
https://doi.org/10.1115/ICONE29-93039
View Paper titled, Quantitative Risk Assessment With CMMC Method on Abnormal Snowfall Incident for a Sodium-Cooled Fast Reactor
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Topics: Risk assessment, Sodium fast reactors, Hazards, Meteorology, Temperature, Dynamics (Mechanics), Probability, Chain, Climate change, Coolants
Proceedings Papers

Research on the Influence of Water Tank Liquid Level on Low Pressure Two-Phase Open Natural Circulation Flow and Heat Exchange

Shengnan Zhang, Zhongning Sun, Nan Zhang
Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A072, August 8–12, 2022
Paper No: ICONE29-92041
https://doi.org/10.1115/ICONE29-92041
View Paper titled, Research on the Influence of Water Tank Liquid Level on Low Pressure Two-Phase Open Natural Circulation Flow and Heat Exchange
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Topics: Flow (Dynamics), Heat, Pressure, Water
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
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

Review of Flow Characteristics in Narrow Rectangular Channels Under Marine Conditions

Enpei Wang, Lei Li, Mingjun Wei, Yongsheng Wen, Bowen Zhou
Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A116, August 8–12, 2022
Paper No: ICONE29-93743
https://doi.org/10.1115/ICONE29-93743
View Paper titled, Review of Flow Characteristics in Narrow Rectangular Channels Under Marine Conditions
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Topics: Flow (Dynamics), Heat transfer, Pressure drop, Heat exchangers, Heat, Nuclear power stations, Nuclear reactors, Ocean engineering, Pipes, Power stations
Proceedings Papers

CFD Analysis of the Steam Side in a Cross-Flow X-Type Steam Superheater

Shujie Zhao, Weihua Li, Wentao Hao, Wenwen Zhang
Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A041, August 8–12, 2022
Paper No: ICONE29-91387
https://doi.org/10.1115/ICONE29-91387
View Paper titled, CFD Analysis of the Steam Side in a Cross-Flow X-Type Steam Superheater
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Topics: Computational fluid dynamics, Cross-flow, Steam, Superheaters, Flow (Dynamics), Shells, Computer software, Design, Geometry, Heat
Proceedings Papers

Relap5 MOD3.2 Lead and LBE Model Addition and Program Validation

Sifan Dong, Xiao Luo, Hongli Chen
Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A064, August 8–12, 2022
Paper No: ICONE29-92103
https://doi.org/10.1115/ICONE29-92103
View Paper titled, Relap5 MOD3.2 Lead and LBE Model Addition and Program Validation
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Topics: China, Errors, Fast neutron reactors, Flow (Dynamics), Fluids, Heat, Liquid metals, Safety, Simulation, Simulation results
Proceedings Papers

Development and Verification of Wall Heat Transfer Model Between Submerged Residual Decay Heat Removal System and Three-Dimensional Sodium Pool in Fast Reactor

Jun Zhang, Daogang Lu, Jinsong Guo, Yuhao Zhang, Danting Sui
Proc. ASME. ICONE29, Volume 7B: Thermal-Hydraulics and Safety Analysis, V07BT07A025, August 8–12, 2022
Paper No: ICONE29-92794
https://doi.org/10.1115/ICONE29-92794
View Paper titled, Development and Verification of Wall Heat Transfer Model Between Submerged Residual Decay Heat Removal System and Three-Dimensional Sodium Pool in Fast Reactor
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Topics: Fast neutron reactors, Heat, Heat transfer, Sodium
Proceedings Papers

An Optimal Design Method for Passive Residual Heat Removal System

Yuepeng Bi
Proc. ASME. ICONE29, Volume 7B: Thermal-Hydraulics and Safety Analysis, V07BT07A015, August 8–12, 2022
Paper No: ICONE29-92518
https://doi.org/10.1115/ICONE29-92518
View Paper titled, An Optimal Design Method for Passive Residual Heat Removal System
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Topics: Design methodology, Genetic algorithms, Heat
Proceedings Papers

Study on Decay Heat Removal by Dipped-Direct Heat Exchanger in Sodium-Cooled Fast Reactor

Toshiki Ezure, Erina Hamase, Masaaki Tanaka, Antoine Gerschenfeld, Yannick Gorsse, Simon Li
Proc. ASME. ICONE29, Volume 7B: Thermal-Hydraulics and Safety Analysis, V07BT07A034, August 8–12, 2022
Paper No: ICONE29-93119
https://doi.org/10.1115/ICONE29-93119
View Paper titled, Study on Decay Heat Removal by Dipped-Direct Heat Exchanger in Sodium-Cooled Fast Reactor
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Topics: Heat, Heat exchangers, Sodium fast reactors
Proceedings Papers

Research on Characteristics of Condensation Heat Transfer for Marine Nuclear Power Platform PRHR HX Under Tilting Condition

Pengzheng Li, Yongquan Li, Shaoyou Liu, Dongbao Zhu, Zhiqiang Zhu, Xiaming Kong
Proc. ASME. ICONE29, Volume 7B: Thermal-Hydraulics and Safety Analysis, V07BT07A007, August 8–12, 2022
Paper No: ICONE29-92406
https://doi.org/10.1115/ICONE29-92406
View Paper titled, Research on Characteristics of Condensation Heat Transfer for Marine Nuclear Power Platform PRHR HX Under Tilting Condition
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Topics: Condensation, Heat, Heat exchangers, Heat transfer, Nuclear power
Proceedings Papers

Machine Learning Modelling of Decay Heat Removal in High Temperature Gas-Cooled Reactor

Hao Wu, Liangzhi Yu, Fenglei Niu, Jiyuan Tu, Shengyao Jiang
Proc. ASME. ICONE29, Volume 7B: Thermal-Hydraulics and Safety Analysis, V07BT07A019, August 8–12, 2022
Paper No: ICONE29-92695
https://doi.org/10.1115/ICONE29-92695
View Paper titled, Machine Learning Modelling of Decay Heat Removal in High Temperature Gas-Cooled Reactor
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Topics: Heat, Machine learning, Modeling, Very high temperature reactors
Proceedings Papers

Three-Dimensional Numerical Simulation of the Natural Circulation Characteristics Based on PLANDTL-DHX for Different Modeling Methods of the Core

Jinsong Guo, Xueyuan Zhang, Haiqi Zhao, Daogang Lu, Yuhao Zhang
Proc. ASME. ICONE29, Volume 7B: Thermal-Hydraulics and Safety Analysis, V07BT07A003, August 8–12, 2022
Paper No: ICONE29-92364
https://doi.org/10.1115/ICONE29-92364
View Paper titled, Three-Dimensional Numerical Simulation of the Natural Circulation Characteristics Based on PLANDTL-DHX for Different Modeling Methods of the Core
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Topics: Computer simulation, Heat, Modeling, Flow (Dynamics), Wire, Fuel rods, Porous materials, Safety, Sodium fast reactors, Dynamics (Mechanics)