1-20 of 403
Reactor vessels
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

Evaluations of TiO 2 Deposition on Structure Surfaces and Water Radiolysis for the Corrosive Environment in a Reactor Pressure Vessel

Takashi Mawatari, Yasushi Yamamoto, Osamu Shibasaki, Takahiro Hara, Yusuke Horayama, Junichi Takagi
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, V001T02A032, August 4–6, 2021
Paper No: ICONE28-64931
DOI: https://doi.org/10.1115/ICONE28-64931
View Paper
PDF
Topics: Electrolytic corrosion, Reactor vessels, Stress corrosion cracking, Titanium dioxide, Water
Proceedings Papers

Numerical Analysis on the Thermal-Hydraulic Characteristics for the Reactor Main Vessel Cooling System of Chinese Sodium Cooled Fast Reactor

Ping Song, Tangtao Feng, Dalin Zhang, Lie Chen, Shaodan Li, Yuansheng Lin, Suizheng Qiu
Proc. ASME. ICONE28, Volume 2: Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics, V002T07A012, August 4–6, 2021
Paper No: ICONE28-64293
DOI: https://doi.org/10.1115/ICONE28-64293
View Paper
PDF
Topics: Cooling systems, Numerical analysis, Reactor vessels, Sodium fast reactors, Vessels
Proceedings Papers

Mixing Characteristic Measurement of Flow in Reactor Pressure Vessel by Laser Induced Fluorescent Method

Mingpeng Chen, Guanhui Xie, Dongyang Li, Sichao Tan
Proc. ASME. ICONE28, Volume 2: Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics, V002T07A038, August 4–6, 2021
Paper No: ICONE28-65770
DOI: https://doi.org/10.1115/ICONE28-65770
View Paper
PDF
Topics: Boron, Flow measurement, Fluids, Lasers, Reactor vessels, Slug flows, Coolants, Flow (Dynamics), Pressure vessels, Annulus
Proceedings Papers

Preliminary Transient Analysis for LBE-Cooled Fast Reactor BLESS-D

Mian Xing, Linsen Li, Gang Zheng, Junlang Wen, Chunyuan Liu, Yeoh Eing Yee, Zhen Luo, Peidong Sun, Jinjun Feng
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, V001T04A002, August 4–6, 2021
Paper No: ICONE28-63220
DOI: https://doi.org/10.1115/ICONE28-63220
View Paper
PDF
Topics: Fast neutron reactors, Safety, Transient analysis, Transients (Dynamics), Design, Reactor vessels, Accidents, Boilers, Conceptual design, Coolants
Proceedings Papers

Research on Dimensionless Analysis Method of Scale Effects for Molten Pool Experiments

Fengyang Quan, Wei Li, Zikun Zhao, Xiao Zeng, Yong Guo, Yidan Yuan
Proc. ASME. ICONE28, Volume 2: Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics, V002T07A024, August 4–6, 2021
Paper No: ICONE28-64739
DOI: https://doi.org/10.1115/ICONE28-64739
View Paper
PDF
Topics: Accidents, Cladding systems (Building), Coolants, Cooling, Dimensional analysis, Engineering prototypes, Failure, Floods, Fuels, Heat flux
Proceedings Papers

Core Thermal-Hydraulic Analysis During Dipped-Type Direct Heat Exchanger Operation in Natural Circulation Conditions

Erina Hamase, Norihiro Doda, Ayako Ono, Masaaki Tanaka, Yasuhiro Miyake, Yasutomo Imai
Proc. ASME. ICONE28, Volume 2: Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics, V002T07A005, August 4–6, 2021
Paper No: ICONE28-63380
DOI: https://doi.org/10.1115/ICONE28-63380
View Paper
PDF
Topics: Computational fluid dynamics, Flow (Dynamics), Heat exchangers, Sodium fast reactors, Fuels, Reactor vessels, Sodium, Coolants, Cooling, Cooling systems
Proceedings Papers

Numerical Analysis of Pressurized Thermal Shock in Reactor Pressure Vessel

Yubin Zhang
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, V003T08A011, August 4–6, 2021
Paper No: ICONE28-64737
DOI: https://doi.org/10.1115/ICONE28-64737
View Paper
PDF
Topics: Numerical analysis, Reactor vessels, Thermal shock, Accidents, Computational fluid dynamics, Computer software, Coolants, Flow (Dynamics), Mechanical structures, Nozzles
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
Proceedings Papers

Development of Ultrasonic Measurement System for Shape and 2D Velocity Field Using Ultrasonic Velocity Profiler and Total Focusing Methods

Zeliang Zhang, Tianrun Liu, Munkhbat Batsaikhan, Hideharu Takahashi, Hiroshige Kikura
Proc. ASME. ICONE28, Volume 4: Student Paper Competition, V004T14A049, August 4–6, 2021
Paper No: ICONE28-64510
DOI: https://doi.org/10.1115/ICONE28-64510
View Paper
PDF
Topics: Fuels, Fukushima nuclear disaster, Japan, 2011, Nuclear decommissioning, Nuclear power stations, Shapes, Transducers, Ultrasonic measurement, Accidents, Radiation (Physics), Water leakage
Proceedings Papers

Study on Buckling Strength and Post Buckling Behaviors of Reactor Vessel Lower Heads

Masato Murohara, Akira Yamazaki, Takuya Sato, Naoto Kasahara
Proc. ASME. ICONE28, Volume 4: Student Paper Competition, V004T14A072, August 4–6, 2021
Paper No: ICONE28-65553
DOI: https://doi.org/10.1115/ICONE28-65553
View Paper
PDF
Topics: Buckling, Reactor vessels, Failure, Design, Accidents, Deformation, Earthquakes, Fukushima nuclear disaster, Japan, 2011, High temperature, Nuclear reactor accidents
Proceedings Papers

Computational Modeling of Terry Turbine Airflow Testing to Support the Expansion of Operating Band in Beyond Design Basis Conditions

Lindsay N. Gilkey, Nathan Andrews, Kyle Ross, Matthew Solom
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, V001T01A012, August 4–5, 2020
Paper No: ICONE2020-16547
DOI: https://doi.org/10.1115/ICONE2020-16547
View Paper
PDF
Topics: Air flow, Computer simulation, Design, Testing, Turbines, Modeling, Batteries, Accidents, Safety, Water
Proceedings Papers

Study of the Ageing Effects on the Lower Head Failure in a PWR Reactor

R. Lo Frano, S. Paci, P. Darnowski, P. Mazgaj
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, V001T01A016, August 4–5, 2020
Paper No: ICONE2020-16664
DOI: https://doi.org/10.1115/ICONE2020-16664
View Paper
PDF
Topics: Failure, Finite element methods, Pressurized water reactors, Accidents, Nuclear power stations, Reactor vessels, Boundary-value problems, Computers, Engineering simulation, Materials properties
Proceedings Papers

Sensitivity Analysis for Release and Transport Behavior of Radionuclide of the 1F Unit-1 Accident Using SAMPSON

Chiaki Kino, Hidetoshi Karasawa, Shunsuke Uchida
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, V001T01A017, August 4–5, 2020
Paper No: ICONE2020-16839
DOI: https://doi.org/10.1115/ICONE2020-16839
View Paper
PDF
Topics: Accidents, Radioisotopes, Sensitivity analysis, Molybdenum, Hydrogen, Fuels, Nuclear decommissioning, Nuclear power stations, Reactor vessels, Simulation
Proceedings Papers

Analysis of Transient Corium Pool Structure in the Lower Plenum of Reactor Vessel

Liang Chen, Hua Pang, Ximing Xie, Lei Zhong, Rong Cai
Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T08A041, August 4–5, 2020
Paper No: ICONE2020-16470
DOI: https://doi.org/10.1115/ICONE2020-16470
View Paper
PDF
Topics: Accidents, Reactor vessels, Transients (Dynamics), Vessels, Density, Heat flux, Heavy metals, China, Coolants, Critical heat flux
Proceedings Papers

Nuclear Pressure Vessel Manufacture Using the Hot Isostatic Pressing (HIP) Process

John Sulley, Phil Wallace, Ted Warner, Gary Jones
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, V001T06A002, August 4–5, 2020
Paper No: ICONE2020-16035
DOI: https://doi.org/10.1115/ICONE2020-16035
View Paper
PDF
Topics: Hot pressing, Reactor vessels, Vessels, Nuclear power stations, Pressure vessels, Welding, Alloy steel, Electron beam welding, Energy generation, Fillers (Materials)
Proceedings Papers

Evaluation of Irradiation Embrittlement of the Weld Metals in the Chinese RPV

Yupeng Cao, Yinbiao He, Yifeng Huang, Binxi Wang, Yan Yu, Hui Li, Hu Hui
Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T09A003, August 4–5, 2020
Paper No: ICONE2020-16261
DOI: https://doi.org/10.1115/ICONE2020-16261
View Paper
PDF
Topics: Embrittlement, Irradiation (Radiation exposure), Metals, Forging, Mechanical properties, China, Damage, Design, Fluence (Radiation measurement), Fracture toughness
Proceedings Papers

Technology of Phased Array Ultrasonic Testing on Jet Pump Beam Installed in Reactor Pressure Vessel

Shunsuke Sasaki, Setsu Yamamoto, Toshiaki Takada, Keiji Matsunaga, Kohei Uraguchi, Ikuko Kameyama
Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T09A004, August 4–5, 2020
Paper No: ICONE2020-16386
DOI: https://doi.org/10.1115/ICONE2020-16386
View Paper
PDF
Topics: Inspection, Jet pumps, Reactor vessels, Ultrasonic testing
Proceedings Papers

Analysis of Gas Entrainment Phenomenon From Free Liquid Surface for a Sodium-Cooled Fast Reactor Design: Validation of Velocity Profile and Strouhal Number in a Flow Field

Mao Uchida, Moe Hirakawa, Aaru Sano, Keisuke Inoue, Takaaki Sakai, Toshiki Ezure, Masaaki Tanaka
Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T11A009, August 4–5, 2020
Paper No: ICONE2020-16418
DOI: https://doi.org/10.1115/ICONE2020-16418
View Paper
PDF
Topics: Design, Flow (Dynamics), Sodium fast reactors, Vortices, Computational fluid dynamics, Reactor vessels, Water, Coolants, Evaluation methods, Particulate matter
Proceedings Papers

Numerical Simulation of Concrete Ablation and Corium Cooling for Molten Corium-Concrete Interaction (MCCI)

Zhichun Xu, Yapei Zhang, G. H. Su, Wenxi Tian, Suizheng Qiu
Proc. ASME. ICONE2020, Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation, V003T12A026, August 4–5, 2020
Paper No: ICONE2020-16388
DOI: https://doi.org/10.1115/ICONE2020-16388
View Paper
PDF
Topics: Ablation (Vaporization technology), Computer simulation, Concretes, Cooling, Light water reactors, Reactor vessels, Accidents, Cavities, Containment, Flow (Dynamics)
Proceedings Papers

Heat Transfer and Fluid Flow Characteristic of One Side Heated Vertical Rectangular Channel That Inserted Thin Metallic Wire

Gota Suga, Tetsuaki Takeda
Proc. ASME. ICONE2020, Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation, V003T12A040, August 4–5, 2020
Paper No: ICONE2020-16705
DOI: https://doi.org/10.1115/ICONE2020-16705
View Paper
PDF
Topics: Fluid dynamics, Heat transfer, Wire, Very high temperature reactors, Flow (Dynamics), Natural convection, Cooling, Cooling systems, Copper, Gas turbines