1-20 of 1165
Pressure
Close
Save search
Follow your search
Access your saved searches in your account
Would you like to receive an alert when new items match your search?
Close Modal
Sort by
Proceedings Papers

Extending a Fluid-to-Fluid Similarity Rationale for Heat Transfer at Supercritical Pressure to R134a

Sara Kassem, Andrea Pucciarelli, Walter Ambrosini
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, V003T08A014, August 4–6, 2021
Paper No: ICONE28-64822
DOI: https://doi.org/10.1115/ICONE28-64822
View Paper
PDF
Topics: Fluids, Heat transfer, Pressure
Proceedings Papers

Preliminary Verification Calculation and Sensitivity Analysis on PISAA Code Compared to MELCOR

Mingqiang Song, Ningna Zhang, Xiaoming Yang, Rubing Ma, Zhiyi Yang, Chao Ding
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, V003T09A006, August 4–6, 2021
Paper No: ICONE28-64749
DOI: https://doi.org/10.1115/ICONE28-64749
View Paper
PDF
Topics: Accidents, Sensitivity analysis, Hydrogen production, Nuclear industry, China, Coolants, Flow (Dynamics), Fukushima nuclear disaster, Japan, 2011, Nuclear power stations, Pressure
Proceedings Papers

Analysis of the Reflooding Process in Degraded Particle Beds by Simulations of the Debris Test Facility With the Severe Accident Analysis Code ASTEC V2.1 and COCOMO Code

Jan M. Peschel, Christoph Bratfisch, Marco K. Koch
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, V003T12A001, August 4–6, 2021
Paper No: ICONE28-60964
DOI: https://doi.org/10.1115/ICONE28-60964
View Paper
PDF
Topics: Accidents, Particulate matter, Simulation, Test facilities, Temperature, Cooling, Design, Floods, Flow (Dynamics), Gravity (Force)
Proceedings Papers

Tritium Transport Modeling and Analysis for HCCB Blanket of CFETR

Baorui Zhang, Zhaoyang Xia, Zhiwei Zhou
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, V003T08A017, August 4–6, 2021
Paper No: ICONE28-65076
DOI: https://doi.org/10.1115/ICONE28-65076
View Paper
PDF
Topics: Ceramics, China, Computational fluid dynamics, Coolants, Design, Discrete element methods, Flow (Dynamics), Fusion reactors, Helium, Modeling
Proceedings Papers

A Finnish District Heating Reactor: Neutronics Design and Fuel Cycle Simulations

Jaakko Leppänen, Ville Valtavirta, Riku Tuominen, Antti Rintala, Unna Lauranto
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, V001T04A010, August 4–6, 2021
Paper No: ICONE28-64347
DOI: https://doi.org/10.1115/ICONE28-64347
View Paper
PDF
Topics: Central heating, Design, Engineering simulation, Nuclear fuel cycle, Simulation, Fuels, Boron, Cycles, Heating, Operating temperature
Proceedings Papers

A Statistical Approach for Modeling the Effect of Hot Press Conditions on the Mechanical Strength Properties of HTGR Fuel Elements

Aihara Jun, Kuroda Masatoshi, Tachibana Yukio
Proc. ASME. ICONE28, Volume 2: Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics, V002T05A011, August 4–6, 2021
Paper No: ICONE28-64507
DOI: https://doi.org/10.1115/ICONE28-64507
View Paper
PDF
Topics: Fuels, Modeling, Strength (Materials), Very high temperature reactors, Carbon, Design, Experimental design, Oxidation, Pressure, Response surface methodology
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
View Paper
PDF
Topics: Failure, Fuels, Probability, Very high temperature reactors, Irradiation (Radiation exposure), Particulate matter, Stress, Materials properties, Temperature, Anisotropy
Proceedings Papers

Application of High Accuracy Numerical Methods for the Natural Circulation Problem

Fei Chao, Longze Li, Wen Yang, Jinrong Qiu, Yun Tai, Jianqiang Shan
Proc. ASME. ICONE28, Volume 2: Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics, V002T07A014, August 4–6, 2021
Paper No: ICONE28-64367
DOI: https://doi.org/10.1115/ICONE28-64367
View Paper
PDF
Topics: Accuracy and precision, Algorithms, Density, Diffusion (Physics), Errors, Fluids, Nuclear power, Numerical analysis, Pressure, Safety
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
View Paper
PDF
Topics: Boilers, Coolants, Design, Electric power generation, Feedwater, Flow (Dynamics), Frequency-domain analysis, Heating, Momentum, Neutrons
Proceedings Papers

Study on Influence of Rolling and Heaving Motions on Differential Pressure and Flow Rate Measurements

Biao Zhang, Jingyu Liu, Xin Li, Shouxu Qiao, Dongyang Li, Sichao Tan
Proc. ASME. ICONE28, Volume 2: Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics, V002T07A037, August 4–6, 2021
Paper No: ICONE28-65755
DOI: https://doi.org/10.1115/ICONE28-65755
View Paper
PDF
Topics: Flow (Dynamics), Pressure
Proceedings Papers

Eigenvalue Analysis of Well-Posedness of Two-Fluid Single Pressure Model With Virtual Mass Force and Interfacial Pressure

Fei Chao, Wen Yang, Longze Li, Jinrong Qiu, Jianqiang Shan
Proc. ASME. ICONE28, Volume 2: Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics, V002T07A016, August 4–6, 2021
Paper No: ICONE28-64434
DOI: https://doi.org/10.1115/ICONE28-64434
View Paper
PDF
Topics: Eigenvalues, Fluids, Pressure
Proceedings Papers

Theoretical Study on Single Bubble Expansion After Pressurized Subcooled Water Injected in Thermal Glycerin

Feng Mao, Lei Zhang, Xiangyu Yun, Donghua Lu, Wenxi Tian, Huiyong Zhang
Proc. ASME. ICONE28, Volume 2: Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics, V002T07A023, August 4–6, 2021
Paper No: ICONE28-64720
DOI: https://doi.org/10.1115/ICONE28-64720
View Paper
PDF
Topics: Bubbles, Pressure, Subcooling, Water
Proceedings Papers

Development of an Integrated Design Evaluation ‘HITEP’ Platform for High-Temperature Pressure Boundary Components and Piping Systems

Hyeong-Yeon Lee, Si-Hwa Jeong, Min-Gu Won, Nam-Su Huh
Proc. ASME. ICONE28, Volume 2: Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics, V002T06A004, August 4–6, 2021
Paper No: ICONE28-65552
DOI: https://doi.org/10.1115/ICONE28-65552
View Paper
PDF
Topics: Creep, Design, High temperature, Pipes, Piping systems, Pressure, Temperature
Proceedings Papers

Advances in the Development of a Fluid-to-Fluid Similarity Theory for Fluids at Supercritical Pressure: Results From Sensitivity Analyses

A. De Angelis, A. Pucciarelli, S. Kassem, W. Ambrosini
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, V003T08A010, August 4–6, 2021
Paper No: ICONE28-64713
DOI: https://doi.org/10.1115/ICONE28-64713
View Paper
PDF
Topics: Fluids, Heat transfer, Pressure, Sensitivity analysis, Carbon dioxide, Computational fluid dynamics, Supercritical fluids, Supercritical water reactors, Water
Proceedings Papers

Numerical Simulation of Bubble Shape and Departure in Nucleate Pool Boiling at High Superheat

Jyoti Bhati, Swapan Paruya, Farheen Akhtar
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, V003T08A012, August 4–6, 2021
Paper No: ICONE28-64740
DOI: https://doi.org/10.1115/ICONE28-64740
View Paper
PDF
Topics: Bubbles, Computer simulation, Nucleate pool boiling, Pressure, Shapes
Proceedings Papers

Water Hammer Simulation in Two-Phase Flow Regimes Using Open Source Code OpenFOAM

Paul Fuchs, Marco K. Koch
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, V003T08A001, August 4–6, 2021
Paper No: ICONE28-61351
DOI: https://doi.org/10.1115/ICONE28-61351
View Paper
PDF
Topics: Computational fluid dynamics, Simulation, Two-phase flow, Water hammer, Pipes, Pressure, Cavitation, Fluid structure interaction, Bubbles, Fluids
Proceedings Papers

Hydrodynamic Analysis of Steam Generator Under LOCA Conditions

Xiaoqiang He, Puzhen Gao, Weichao Yuan
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, V003T12A030, August 4–6, 2021
Paper No: ICONE28-64709
DOI: https://doi.org/10.1115/ICONE28-64709
View Paper
PDF
Topics: Boilers, Fluid-dynamic forces, Pressure, Accidents, Nuclear power stations, Coolants, Design, Flow (Dynamics), Fluids, Nozzles
Proceedings Papers

Equal Forced Time Step Approach to PSA for a Dynamic System – A Case of the Holdup Tank

E. E. Taapopi, H. Wang, J. Zhou
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, V003T12A011, August 4–6, 2021
Paper No: ICONE28-64081
DOI: https://doi.org/10.1115/ICONE28-64081
View Paper
PDF
Topics: Accidents, Boilers, Computers, Dynamic systems, Errors, Failure, Failure mechanisms, Nuclear power stations, Pressure, Probability
Proceedings Papers

Research on the Diagnosis Model of Break Diameter During the Blowdown Process of SBLOCA

Bingzheng Ke, Puzhen Gao, Kun Cheng, Lingyan Wu, Bo Wang, Bowen Chen, Ruifeng Tian, Jiming Wen
Proc. ASME. ICONE28, Volume 4: Student Paper Competition, V004T14A026, August 4–6, 2021
Paper No: ICONE28-64215
DOI: https://doi.org/10.1115/ICONE28-64215
View Paper
PDF
Topics: Accidents, Coolants, Energy conversion, Errors, Evaporation, Flow (Dynamics), Nuclear power stations, Pressure, Safety
Proceedings Papers

Characteristics of Debris From Simulated Molten Fuel Coolant Interaction Experiments

E. Hemanth Rao, Prabhat Kumar Shukla, Paulson Varghese, S. R. Polaki, E. Vetrivendan, Sanjay Kumar Das, D. Ponraju, S. Athmalingam, B. Venkatraman
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, V003T12A033, August 4–6, 2021
Paper No: ICONE28-65676
DOI: https://doi.org/10.1115/ICONE28-65676
View Paper
PDF
Topics: Accidents, Coolants, Fuels, Sodium fast reactors, Sodium, Heat, High temperature, Particulate matter, Damage, Evaporation