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Proceedings Papers

Development Progress of Neutronics and Thermal-Hydraulics Calculation Program NECP-Panda for Pebble-Bed High Temperature Gas-Cooled Reactor

Yuxuan Wu, Yongping Wang, Shuai Qin, Liangzhi Cao, Hongchun Wu, Yong Luo
Proc. ASME. ICONE31, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A025, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-134649
https://doi.org/10.1115/ICONE31-134649
View Paper titled, Development Progress of Neutronics and Thermal-Hydraulics Calculation Program NECP-Panda for Pebble-Bed High Temperature Gas-Cooled Reactor
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Topics: Thermal hydraulics, Very high temperature reactors
Proceedings Papers

Development and Preliminary Validation of the Fine Fuel Cell Subchannel Analysis Code CUNLUN

Hongwei Jiang, Guangliang Chen, Zhaofei Tian
Proc. ASME. ICONE31, Volume 6: Thermal-Hydraulics and Safety Analysis, V006T07A048, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-134838
https://doi.org/10.1115/ICONE31-134838
View Paper titled, Development and Preliminary Validation of the Fine Fuel Cell Subchannel Analysis Code CUNLUN
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Topics: Computational fluid dynamics, Computer simulation, Coolants, Design, Flow (Dynamics), Fuel cells, Fuel rods, Fuels, Pressurized water reactors, Resolution (Optics)
Proceedings Papers

Three-Dimensional Refined Burnup Calculation of Helical-Cruciform Nuclear Fuel

Duan Qianni, Li Wei, Wu Junmei
Proc. ASME. ICONE31, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A035, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135085
https://doi.org/10.1115/ICONE31-135085
View Paper titled, Three-Dimensional Refined Burnup Calculation of Helical-Cruciform Nuclear Fuel
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Topics: High cycle fatigue, Nuclear fuels, Neutrons, Physics, Power density, Fuels, Geometry, Innovation, Thermal hydraulics, Uranium
Proceedings Papers

Multi-Mesh Approach for Geometry-Independent Neutronic/Thermal-Hydraulics Coupling Analyses Using RMC and Ansys Fluent

Xingyu Zhao, Guodong Liu, Shanfang Huang, Qiaoyan Chen, Hao Luo, Ying He, Junren Hou, Kan Wang
Proc. ASME. ICONE31, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A015, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-133607
https://doi.org/10.1115/ICONE31-133607
View Paper titled, Multi-Mesh Approach for Geometry-Independent Neutronic/Thermal-Hydraulics Coupling Analyses Using RMC and Ansys Fluent
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Topics: Computational fluid dynamics, Geometry, Thermal hydraulics
Proceedings Papers

The Steady States and DLOFC Accident Analysis of HTR-PM in the OTTO Operation Scheme

Songyang Liu, Xuelin Li, Yong Luo, Wei Liu, Qin Zhou, Cheng Gu, Tian Zhang
Proc. ASME. ICONE31, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A021, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-133310
https://doi.org/10.1115/ICONE31-133310
View Paper titled, The Steady States and DLOFC Accident Analysis of HTR-PM in the OTTO Operation Scheme
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Topics: Accidents, Steady state, Fuels, Temperature, China, Equilibrium (Physics), Graphite, Construction, Coolants, Design
Proceedings Papers

Current Results of BME NTI in the ECC-SMART Project: Different Analysis on the SCW-SMR

Tamás Varju, Attila Kiss, Csenge Antók, Boglárka Babcsány, Ildikó Boros, Péter Mészáros, Zeno Bertesina, Szabolcs Czifrus
Proc. ASME. ICONE31, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A058, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135760
https://doi.org/10.1115/ICONE31-135760
View Paper titled, Current Results of BME NTI in the ECC-SMART Project: Different Analysis on the SCW-SMR
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Topics: Biomedical engineering, Supercritical water reactors, Design, Fuels, Physics, Circuits, Computational fluid dynamics, Computer software, Finite element analysis, Heat
Proceedings Papers

Conceptual Design and Feasibility Analysis of a Modular Supercritical CO 2 Fast Reactor Core

Guihua Lai, Tian Wang, Ding She, Hong Wang
Proc. ASME. ICONE31, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A045, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135206
https://doi.org/10.1115/ICONE31-135206
View Paper titled, Conceptual Design and Feasibility Analysis of a Modular Supercritical CO 2 Fast Reactor Core
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Topics: Conceptual design, Fast neutron reactors, Small modular reactors, Supercritical carbon dioxide, Safety, Temperature, Design, Fuel rods, Heat, Particulate matter
Proceedings Papers

Neutronics/Thermal-Hydraulics Coupling Simulation Using JAMPAN in a Single BWR Fuel Assembly

Tomohiro Kamiya, Taku Nagatake, Ayako Ono, Kenichi Tada, Ryoichi Kondo, Yasunobu Nagaya, Hiroyuki Yoshida
Proc. ASME. ICONE31, Volume 6: Thermal-Hydraulics and Safety Analysis, V006T07A092, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135974
https://doi.org/10.1115/ICONE31-135974
View Paper titled, Neutronics/Thermal-Hydraulics Coupling Simulation Using JAMPAN in a Single BWR Fuel Assembly
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Topics: Boiling water reactors, Fuels, Manufacturing, Simulation, Thermal hydraulics
Proceedings Papers

Thermal-Hydraulics and Neutronics Coupling Calculation and Validation of NECP-Panda: A Computational Code for Pebble-Bed High Temperature Gas-Cooled Reactors

Dongyu Xu, Yongping Wang, Hongchun Wu, Aolin Zhang, Yuxuan Wu, Yong Luo
Proc. ASME. ICONE31, Volume 6: Thermal-Hydraulics and Safety Analysis, V006T07A098, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-136096
https://doi.org/10.1115/ICONE31-136096
View Paper titled, Thermal-Hydraulics and Neutronics Coupling Calculation and Validation of NECP-Panda: A Computational Code for Pebble-Bed High Temperature Gas-Cooled Reactors
Open the PDF for Thermal-Hydraulics and Neutronics Coupling Calculation and Validation of NECP-Panda: A Computational Code for Pebble-Bed High Temperature Gas-Cooled Reactors in another window
Topics: Simulation, Thermal hydraulics, Very high temperature reactors
Proceedings Papers

Study on Scaling Method for Natural Circulation Instability in Narrow Channel

Yao Yao, Tao Zhou, Dongli Huang, Jianyu Tang, Wenbin Liu, Shilei Dun
Proc. ASME. ICONE31, Volume 6: Thermal-Hydraulics and Safety Analysis, V006T07A025, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-134167
https://doi.org/10.1115/ICONE31-134167
View Paper titled, Study on Scaling Method for Natural Circulation Instability in Narrow Channel
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Topics: Condensation, Control systems, Design, Dynamic systems, Engineering prototypes, Fatigue failure, Flow (Dynamics), Flow instability, Heat flux, High pressure (Physics)
Proceedings Papers

Thermal Hydraulics Simulation of a Typical Pressurized Water Reactor Coolant System Using CFD Method

Mingqian Zhang, Run Lin
Proc. ASME. ICONE31, Volume 6: Thermal-Hydraulics and Safety Analysis, V006T07A015, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-132452
https://doi.org/10.1115/ICONE31-132452
View Paper titled, Thermal Hydraulics Simulation of a Typical Pressurized Water Reactor Coolant System Using CFD Method
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Topics: Computational fluid dynamics, Coolants, Domes (Structural elements), Nuclear reactor coolants, Pressurized water reactors, Simulation, Swirling flow, Thermal hydraulics, Pumps, Reactor vessels
Proceedings Papers

RCCA Ejection Accident Analysis Based on Coupled 3d Neutronics and Thermal-Hydraulics

Zang Liye
Proc. ASME. ICONE31, Volume 6: Thermal-Hydraulics and Safety Analysis, V006T07A029, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-134296
https://doi.org/10.1115/ICONE31-134296
View Paper titled, RCCA Ejection Accident Analysis Based on Coupled 3d Neutronics and Thermal-Hydraulics
Open the PDF for RCCA Ejection Accident Analysis Based on Coupled 3d Neutronics and Thermal-Hydraulics in another window
Topics: Accidents, Thermal hydraulics
Proceedings Papers

Coupled Thermal-Hydraulics and Neutron Transport Calculations of Small Modular Reactor Using Serpent, OpenFOAM and SUBCHANFLOW Codes

Tomáš Kořínek, Jiri Zavorka, Martin Lovecky, Radek Skoda
Proc. ASME. ICONE31, Volume 7: Computational Fluid Dynamics (CFD) and Applications, V007T08A049, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-136127
https://doi.org/10.1115/ICONE31-136127
View Paper titled, Coupled Thermal-Hydraulics and Neutron Transport Calculations of Small Modular Reactor Using Serpent, OpenFOAM and SUBCHANFLOW Codes
Open the PDF for Coupled Thermal-Hydraulics and Neutron Transport Calculations of Small Modular Reactor Using Serpent, OpenFOAM and SUBCHANFLOW Codes in another window
Topics: Neutrons, Small modular reactors, Thermal hydraulics
Proceedings Papers

Pure Lead Thermodynamic Properties in SIMMER-III Code: A Comparative Review and New Evaluation Proposal

Alessandro Bellomo, Mattia Massone, Simone Gianfelici, Koji Morita, Mariano Tarantino, Alessio Pesetti, Vittorio Cossu, Andrei Rineiski
Proc. ASME. ICONE31, Volume 10: Risk Assessments and Management; Computer Code Verification and Validation; Nuclear Education and Public Acceptance, V010T13A016, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-136243
https://doi.org/10.1115/ICONE31-136243
View Paper titled, Pure Lead Thermodynamic Properties in SIMMER-III Code: A Comparative Review and New Evaluation Proposal
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Topics: Equations of state, Fast neutron reactors, Thermodynamic properties, Heat capacity, Accidents, Design, Liquid metals, Pressure, Sodium fast reactors, Boilers
Proceedings Papers

Verification and Analysis of Thermal-Hydraulics System Program for a Power Plant Model

Lixin Du, Peng Zhou, Hao Zhang, Yanhua Yang
Proc. ASME. ICONE31, Volume 10: Risk Assessments and Management; Computer Code Verification and Validation; Nuclear Education and Public Acceptance, V010T13A007, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-134794
https://doi.org/10.1115/ICONE31-134794
View Paper titled, Verification and Analysis of Thermal-Hydraulics System Program for a Power Plant Model
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Topics: Accidents, Circuits, Computer software, Design, Fluids, Heat transfer, Hydraulic drive systems, Nuclear power, Nuclear power stations, Power stations
Proceedings Papers

Scaling of Horizontal Steam Generator Based on Three-Dimensional Thermal-Hydraulic Simulations

Milos Lazarevic, Vladimir Stevanovic, Milan M. Petrovic, Sanja Milivojevic, Milica Ilic
Proc. ASME. ICONE31, Volume 11: Student Paper Competition, V011T15A081, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-136502
https://doi.org/10.1115/ICONE31-136502
View Paper titled, Scaling of Horizontal Steam Generator Based on Three-Dimensional Thermal-Hydraulic Simulations
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Topics: Boilers, Engineering simulation, Simulation, Thermal hydraulics
Proceedings Papers

Coupled OpenMC/CTF to VERA Core Physics Benchmark Problem 6

Chang Zhang, Ruixiang Wang, Hui Guo, Hanyang Gu, Yao Xiao
Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A101, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92642
https://doi.org/10.1115/ICONE29-92642
View Paper titled, Coupled OpenMC/CTF to VERA Core Physics Benchmark Problem 6
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Topics: Physics, Thermal hydraulics, Fuels, Temperature, Coolants, Light water reactors, Manufacturing, Simulation, Eigenvalues, Fuel rods
Proceedings Papers

3d Multi-Physics Numerical Coupling of Monte Carlo Neutronics and Thermal-Hydraulic for Solid Core

Qing Yang, Jianhua Xia, Xiaojing Liu, Qingquan Pan, Hui He, Tengfei Zhang
Proc. ASME. ICONE29, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A038, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-94534
https://doi.org/10.1115/ICONE29-94534
View Paper titled, 3d Multi-Physics Numerical Coupling of Monte Carlo Neutronics and Thermal-Hydraulic for Solid Core
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Topics: Physics, Neutrons, Simulation, Computational fluid dynamics, Computer simulation, Conceptual design, Coolants, Design, Nuclear design, Optimization
Proceedings Papers

Application of the Refinement Spacer Grid Model in Subchannel Analysis Code

Si Ying Dong, Ping Yang, Fujun Gan, Yuanrong Liu
Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A025, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-90296
https://doi.org/10.1115/ICONE29-90296
View Paper titled, Application of the Refinement Spacer Grid Model in Subchannel Analysis Code
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Topics: Axial flow, Economics , Flow (Dynamics), Fluids, Friction, Fuel rods, Momentum, Particulate matter, Pressurized water reactors, Rods
Proceedings Papers

Experimental Investigation on the Formation and Break-Up of Gas Stratification in the COTHYD Facility

Yuchen Zhang, Yuzhou Lu, Xiangyu Yun, Huiyong Zhang
Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A068, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92162
https://doi.org/10.1115/ICONE29-92162
View Paper titled, Experimental Investigation on the Formation and Break-Up of Gas Stratification in the COTHYD Facility
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Topics: Accidents, China, Containment, Erosion, Helium, Hydrogen, Nuclear power, Pressurized water reactors, Sprays, Steam