Search Results | ICONE | ASME Digital Collection

Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A078, August 8–12, 2022

Paper No: ICONE29-93343

DOI: https://doi.org/10.1115/ICONE29-93343

View Paper

Topics: Corrosion, Feedwater, Pipes, Pumps

Proceedings Papers

Effect of Carbon Content on the Resistance to Intergranular Corrosion of Alloy 800H

Qiang Zhong, Man Wang, Wen-Qiang Sun, Jun-Jie Wu, Jiong Qian, Sen-Sen Ning

Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A023, August 8–12, 2022

Paper No: ICONE29-91676

DOI: https://doi.org/10.1115/ICONE29-91676

View Paper

Topics: Alloys, Carbon, Computer software, Corrosion, Precipitation, Simulation

Proceedings Papers

Effect of Contact Stress on Fretting Corrosion Behavior of Alloy 690 Tube Exposed to Simulated Secondary Water

Wenhua Zhuang, Zhongli Han, Xianglong Guo, Lefu Zhang

Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A054, August 8–12, 2022

Paper No: ICONE29-92395

DOI: https://doi.org/10.1115/ICONE29-92395

View Paper

Topics: Alloys, Corrosion, Stress, Water, Wear

Proceedings Papers

Effect of Surface Treatment on the Corrosion Behavior of Stainless Steels in High-Temperature Supercritical Carbon Dioxide

Zhu Liu, Haozhan Su, Jiachen Long, Shuo Cong, Kai Chen, Xianglong Guo, Lefu Zhang

Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A020, August 8–12, 2022

Paper No: ICONE29-90718

DOI: https://doi.org/10.1115/ICONE29-90718

View Paper

Topics: Carburization, Corrosion, High temperature, Oxidation, Stainless steel, Supercritical carbon dioxide, Surface finishing

Proceedings Papers

The Research of Corrosion Resistance of CZ2 Zirconium Alloy Welding Specimens

Yang Xu, Liu-Tao Chen, Chang-Yuan Gao, Jun Tan, Lin Shi

Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A092, August 8–12, 2022

Paper No: ICONE29-93838

DOI: https://doi.org/10.1115/ICONE29-93838

View Paper

Topics: Corrosion, Corrosion resistance, Weight (Mass), Welding, Zirconium alloys

Proceedings Papers

Corrosion Behavior of a Novel Alumina Forming Austenitic Steel Exposed to Supercritical Water

Dayun Sun, Yang Gao, Shuo Cong, Xianglong Guo

Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A057, August 8–12, 2022

Paper No: ICONE29-92471

DOI: https://doi.org/10.1115/ICONE29-92471

View Paper

Topics: Corrosion, Steel, Water

Proceedings Papers

The Wear and General Corrosion Properties of Low-Temperature Plasma Nitrided 17-4PH Stainless Steel With a Work-Hardened Sublayer

Zhongli Han, Ping Lai, Wenhua Zhuang, Xianglong Guo, Lefu Zhang

Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A026, August 8–12, 2022

Paper No: ICONE29-90835

DOI: https://doi.org/10.1115/ICONE29-90835

View Paper

Topics: Corrosion, Low temperature, Nitriding, Plasmas (Ionized gases), Stainless steel, Wear

Proceedings Papers

Rapid Assessment Method for Corrosion Flaws of Seawater Cooling Pipes in Nuclear Power Plants

Zhichao Han, Haijun Chang, Mengling Shen, Zhishen Rong, Zhengpeng Li

Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A057, August 8–12, 2022

Paper No: ICONE29-92871

DOI: https://doi.org/10.1115/ICONE29-92871

View Paper

Topics: Cooling, Corrosion, Finite element methods, Nuclear power stations, Pipes, Seawater

Proceedings Papers

Preliminary Study on Corrosion Behavior and Mechanical Properties Of Inconel 617 in Impure Helium Environment of VHTR

Bin Du, Huaqiang Yin, Tao Ma, Haoxiang Li, Wei Zheng, Xuedong He

Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A003, August 8–12, 2022

Paper No: ICONE29-88943

DOI: https://doi.org/10.1115/ICONE29-88943

View Paper

Topics: Corrosion, Helium, Mechanical properties, Very high temperature reactors

Proceedings Papers

Study on Out-Pile Performance of CZ Zirconium Alloy Guide Tube

Changyuan Gao, Lin Shi, Guoliang Zhang, Yang Xu, Minli Chen, Liutao Chen, Jun Tan

Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A089, August 8–12, 2022

Paper No: ICONE29-93816

DOI: https://doi.org/10.1115/ICONE29-93816

View Paper

Topics: Corrosion, Creep, Zirconium alloys, Alloys, Zirconium, Corrosion resistance, Stress, Temperature, Mechanical testing, Particulate matter

Proceedings Papers

Effect of a Cr 2 O 3 /A-Al 2 O 3 Coating on the Corrosion Behavior of Incoloy 800H Alloy in High Temperature Impure Helium

Haoxiang Li, Wei Zheng, Bin Du, Huaqiang Yin, Zhihao Hong, Long Wang, Xuedong He, Tao Ma, Xingtuan Yang

Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A016, August 8–12, 2022

Paper No: ICONE29-90536

DOI: https://doi.org/10.1115/ICONE29-90536

View Paper

Topics: Alloys, Carburization, Coating processes, Coatings, Corrosion, Helium, High temperature

Proceedings Papers

Hydrogenation of Zircaloy-4 in a Defective Fuel Pellet for Pressurized Water Reactors

Doctor Enivweru, Qingyu Wang, Abiodun Ayodeji, John Njoroge

Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A021, August 8–12, 2022

Paper No: ICONE29-90736

DOI: https://doi.org/10.1115/ICONE29-90736

View Paper

Topics: Corrosion, Fuels, Hydrogen embrittlement, Pressurized water reactors, Cladding systems (Building), Hydrogen, Temperature, Accidents, Boundary-value problems, Coolants

Proceedings Papers

Microstructual and Micro-Chemical Analysis of Zr Cladding Alloys on Corrosion and Creep Properties

Qing Yang Lv, Libin Zhang, Minli Chen, Changyuan Gao, Yang Xu, Liutao Chen, Jun Tan

Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A086, August 8–12, 2022

Paper No: ICONE29-93770

DOI: https://doi.org/10.1115/ICONE29-93770

View Paper

Topics: Alloys, Annealing, Cladding systems (Building), Corrosion, Creep, Tin, Zirconium

Proceedings Papers

Applying Machine Learning to Improve BOA Analysis of CIPS/CILC

Jun Liao, Alexander Mace, Guoqiang Wang, Jesse S. Fisher

Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A095, August 8–12, 2022

Paper No: ICONE29-94480

DOI: https://doi.org/10.1115/ICONE29-94480

View Paper

Topics: Machine learning, Boron, Corrosion, Fuels, Nuclear power stations, Algorithms, Calibration, Chemistry, Cladding systems (Building), Computers

Proceedings Papers

Potential Crud Related Margin Gains With Chromium Coated Zirconium Cladding

William A. Byers, Guoqiang Wang

Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A094, August 8–12, 2022

Paper No: ICONE29-94477

DOI: https://doi.org/10.1115/ICONE29-94477

View Paper

Topics: Cladding systems (Building), Zirconium, Corrosion, Coating processes, Coatings, Fuels, Pressurized water reactors, Accidents, Boiling, Boron

Proceedings Papers

Application of Boron Feedback From BOA CIPS/CILC Analysis on Neutronic Models

Jesse Fisher, Gary Mangham, Christopher Briggs, Guoqiang Wang, Baocheng Zhang

Proc. ASME. ICONE29, Volume 7B: Thermal-Hydraulics and Safety Analysis, V07BT07A061, August 8–12, 2022

Paper No: ICONE29-94476

DOI: https://doi.org/10.1115/ICONE29-94476

View Paper

Topics: Boron, Feedback, Physics, Fuels, Linkages, Pressurized water reactors, Boiling, Boron compounds, Corrosion, Cycles

Proceedings Papers

Study on Time-Dependent Co-58 and Co-60 Activities in the Primary Coolant of CPR1000 PWRs

Xiaoqian Zhang, Pengtao Fu

Proc. ASME. ICONE29, Volume 9: Decontamination and Decommissioning, Radiation Protection, and Waste Management, V009T09A034, August 8–12, 2022

Paper No: ICONE29-92822

DOI: https://doi.org/10.1115/ICONE29-92822

View Paper

Topics: Boiling, Coolants, Corrosion, Pressurized water reactors, Radioisotopes, Cycles, Circuits, Maintenance, Shapes, Cobalt

2 3 4 5

NARROW

Corrosion Behavior of Zr-0.75Sn-0.35Fe-0.15Cr- x Nb Alloys in Oxygen-Containing Super-Heated Steam at 400 °C

Effect of Oxidizing All-Volatile Treatment on Alumina-Forming Austenitic Oxidation Behavior in Supercritical Water

Effect of Cr 6+ Concentrations on the Corrosion Behavior of 316LN Stainless Steel in Supercritical Water

Cause Analysis and Treatment Measures for Corrosion of Warm-Up Pipe of Hualong no.1 Main Feed Water Pump System

Effect of Carbon Content on the Resistance to Intergranular Corrosion of Alloy 800H

Effect of Contact Stress on Fretting Corrosion Behavior of Alloy 690 Tube Exposed to Simulated Secondary Water

Effect of Surface Treatment on the Corrosion Behavior of Stainless Steels in High-Temperature Supercritical Carbon Dioxide

The Research of Corrosion Resistance of CZ2 Zirconium Alloy Welding Specimens

Corrosion Behavior of a Novel Alumina Forming Austenitic Steel Exposed to Supercritical Water

The Wear and General Corrosion Properties of Low-Temperature Plasma Nitrided 17-4PH Stainless Steel With a Work-Hardened Sublayer

Rapid Assessment Method for Corrosion Flaws of Seawater Cooling Pipes in Nuclear Power Plants

Preliminary Study on Corrosion Behavior and Mechanical Properties Of Inconel 617 in Impure Helium Environment of VHTR

Study on Out-Pile Performance of CZ Zirconium Alloy Guide Tube

Effect of a Cr 2 O 3 /A-Al 2 O 3 Coating on the Corrosion Behavior of Incoloy 800H Alloy in High Temperature Impure Helium

Hydrogenation of Zircaloy-4 in a Defective Fuel Pellet for Pressurized Water Reactors

Microstructual and Micro-Chemical Analysis of Zr Cladding Alloys on Corrosion and Creep Properties

Applying Machine Learning to Improve BOA Analysis of CIPS/CILC

Potential Crud Related Margin Gains With Chromium Coated Zirconium Cladding

Application of Boron Feedback From BOA CIPS/CILC Analysis on Neutronic Models

Study on Time-Dependent Co-58 and Co-60 Activities in the Primary Coolant of CPR1000 PWRs

Journals

Conference Proceedings

eBooks

Resources

Opportunities

Journals

Conference Proceedings

eBooks

Resources

Opportunities

This Feature Is Available To Subscribers Only