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Proceedings Papers

Study on Water Chemistry and Temperature Adaptability of CZ Zirconium Alloy

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Hansen Chen, Changyuan Gao, Liutao Chen, Xu Wang, Jun Tan
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A090, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-93820
https://doi.org/10.1115/ICONE29-93820
View Paper titled, Study on Water Chemistry and Temperature Adaptability of CZ Zirconium Alloy
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Topics: Temperature, Water chemistry, Zirconium alloys
Proceedings Papers

WATCH Loop Development and Commissioning Tests

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W. A. Byers, G. Wang
Proc. ASME. ICONE26, Volume 2: Plant Systems, Structures, Components, and Materials; Risk Assessments and Management, V002T03A037, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82626
https://doi.org/10.1115/ICONE26-82626
View Paper titled, WATCH Loop Development and Commissioning Tests
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Topics: Boiling water reactors, Cladding systems (Building), Corrosion, Design, Electricity (Physics), Failure, Flow (Dynamics), Fuel rods, Fuels, Heat flux
Proceedings Papers

Operational Impacts and Consequences of Piping Component Failure: A Review of Operating Experience Data As Recorded in CODAP

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Braedon Carr, Bengt Lydell, Jovica R. Riznic
Proc. ASME. ICONE26, Volume 9: Student Paper Competition, V009T16A001, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81001
https://doi.org/10.1115/ICONE26-81001
View Paper titled, Operational Impacts and Consequences of Piping Component Failure: A Review of Operating Experience Data As Recorded in CODAP
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Topics: Failure, Pipes, Water, Chemistry, Transients (Dynamics), Accidents, Boiling water reactors, Control systems, Corrosion, Corrosion resistance
Proceedings Papers

Microstructure and Properties of New Zirconium Alloys for CAP1400 Fuel Assembly

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Qifeng Zeng, Libing Zhu, Gaihuan Yuan, Lian Wang, Guocheng Sun, Junqiang Lu
Proc. ASME. ICONE25, Volume 3: Nuclear Fuel and Material, Reactor Physics and Transport Theory; Innovative Nuclear Power Plant Design and New Technology Application, V003T02A037, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66951
https://doi.org/10.1115/ICONE25-66951
View Paper titled, Microstructure and Properties of New Zirconium Alloys for CAP1400 Fuel Assembly
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Topics: Fuels, Manufacturing, Zirconium alloys, Alloys, Corrosion resistance, Creep, Mechanical properties, Design, Temperature, Water chemistry
Proceedings Papers

The Chemistry Experience Summary During the Engineering Commissioning Period of Fujian Ningde Nuclear Power Plant

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Heng Liu, Yue Chen, Fuping Li, Hui Liu, Shunlong Yang
Proc. ASME. ICONE25, Volume 1: Operations and Maintenance, Engineering, Modifications, Life Extension, Life Cycle and Balance of Plant; I&C, Digital Controls, and Influence of Human Factors, V001T01A029, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-67040
https://doi.org/10.1115/ICONE25-67040
View Paper titled, The Chemistry Experience Summary During the Engineering Commissioning Period of Fujian Ningde Nuclear Power Plant
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Topics: Chemistry, Nuclear power stations, Construction, Instrumentation, Maintenance, Water chemistry, Water pollution, Aluminum, Design, Fuels
Proceedings Papers

Radiation-Induced Electrolytic Corrosion of LWRS: (Part 2) — Verification of In- and Out-Core Redox Potential Differences

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Genn Saji
Proc. ASME. ICONE24, Volume 1: Operations and Maintenance, Aging Management and Plant Upgrades; Nuclear Fuel, Fuel Cycle, Reactor Physics and Transport Theory; Plant Systems, Structures, Components and Materials; I&C, Digital Controls, and Influence of Human Factors, V001T03A028, June 26–30, 2016
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-60895
https://doi.org/10.1115/ICONE24-60895
View Paper titled, Radiation-Induced Electrolytic Corrosion of LWRS: (Part 2) — Verification of In- and Out-Core Redox Potential Differences
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Topics: Electrolytic corrosion, Light water reactors, Radiation (Physics), Water, Boiling water reactors, Equilibrium (Physics), Fittings, Pressurized water reactors, Reactive-ion etching, Water chemistry
Proceedings Papers

Corrosion of Hot-Dip Galvanized Containment Installations: A Potential Cause for Thermal-Hydraulic Effects After LOCA in PWR?

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Holger Kryk, Ulrich Harm, Uwe Hampel
Proc. ASME. ICONE24, Volume 3: Thermal-Hydraulics, V003T09A013, June 26–30, 2016
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-60273
https://doi.org/10.1115/ICONE24-60273
View Paper titled, Corrosion of Hot-Dip Galvanized Containment Installations: A Potential Cause for Thermal-Hydraulic Effects After LOCA in PWR?
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Topics: Containment, Corrosion, Pressurized water reactors, Coolants, Precipitation, Chemistry, Temperature, Test facilities, Cladding systems (Building), Cycles
Proceedings Papers

Radiation-Induced Electrolytic Corrosion of LWRS: (Part 1) — Basic Mechanism and Implications in Degradation Phenomena

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Genn Saji
Proc. ASME. ICONE24, Volume 1: Operations and Maintenance, Aging Management and Plant Upgrades; Nuclear Fuel, Fuel Cycle, Reactor Physics and Transport Theory; Plant Systems, Structures, Components and Materials; I&C, Digital Controls, and Influence of Human Factors, V001T03A027, June 26–30, 2016
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-60894
https://doi.org/10.1115/ICONE24-60894
View Paper titled, Radiation-Induced Electrolytic Corrosion of LWRS: (Part 1) — Basic Mechanism and Implications in Degradation Phenomena
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Topics: Electrolytic corrosion, Light water reactors, Radiation (Physics), Water, Boiling water reactors, Pressurized water reactors, Water chemistry, Flow (Dynamics), Reactive-ion etching, Corrosion
Proceedings Papers

Water Chemistry Technology of Methanol Addition in PWR Primary Systems: Radiolysis of Methanol Solution at 320 °C

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Masafumi Domae, Kosho Hojo, Wataru Sugino
Proc. ASME. ICONE22, Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle and Balance of Plant; Nuclear Fuel and Materials; Plant Systems, Structures and Components; Codes, Standards, Licensing and Regulatory Issues, V001T02A024, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-30954
https://doi.org/10.1115/ICONE22-30954
View Paper titled, Water Chemistry Technology of Methanol Addition in PWR Primary Systems: Radiolysis of Methanol Solution at 320 °C
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Topics: Methanol, Pressurized water reactors, Water chemistry, Irradiation (Radiation exposure), Carbon dioxide, Fuels, Hydrogen, Corrosion, Polymerization, Water
Proceedings Papers

Characterization of In-Core Water Chemistry for Corrosion Control of LWRs

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Genn Saji
Proc. ASME. ICONE22, Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle and Balance of Plant; Nuclear Fuel and Materials; Plant Systems, Structures and Components; Codes, Standards, Licensing and Regulatory Issues, V001T02A025, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-30990
https://doi.org/10.1115/ICONE22-30990
View Paper titled, Characterization of In-Core Water Chemistry for Corrosion Control of LWRs
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Topics: Corrosion protection, Light water reactors, Water chemistry, Radiation (Physics), Boiling water reactors, Corrosion, Fittings, Hydrogen, Pressurized water reactors, Chemistry
Proceedings Papers

The Role of CHECWORKS™ in an Effective FAC Program

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David Smith, Jeffrey Horowitz
Proc. ASME. ICONE22, Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle and Balance of Plant; Nuclear Fuel and Materials; Plant Systems, Structures and Components; Codes, Standards, Licensing and Regulatory Issues, V001T01A016, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-30854
https://doi.org/10.1115/ICONE22-30854
View Paper titled, The Role of CHECWORKS™ in an Effective FAC Program
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Topics: Accidents, Carbon steel, Computer software, Condensed matter, Corrosion, Engineers, Failure, Flow (Dynamics), Fossil fuels, Inspection
Proceedings Papers

Technical Basis of Fatigue Crack Growth Rate Curve for Ni-Base Alloy in BWR Water Environment

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Takuya Ogawa, Masao Itatani, Toshiyuki Saito, Hiroshi Nagase, Satoru Aoike, Hideki Yoneda
Proc. ASME. ICONE22, Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle and Balance of Plant; Nuclear Fuel and Materials; Plant Systems, Structures and Components; Codes, Standards, Licensing and Regulatory Issues, V001T07A017, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-31143
https://doi.org/10.1115/ICONE22-31143
View Paper titled, Technical Basis of Fatigue Crack Growth Rate Curve for Ni-Base Alloy in BWR Water Environment
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Topics: Alloys, Boiling water reactors, Fatigue cracks, Water, Stress, Fitness-for-service, Corrosion, Fracture (Materials), Japan Society of Mechanical Engineers, ASTM International
Proceedings Papers

Water Chemistry Sensitivity on Fibrous Debris Bypass Through a Containment Sump Strainer

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Saya Lee, Yassin A. Hassan, Rodolfo Vaghetto, Suhaeb Abdulsattar, Matthew Kappes
Proc. ASME. ICONE22, Volume 2B: Thermal Hydraulics, V02BT09A055, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-31176
https://doi.org/10.1115/ICONE22-31176
View Paper titled, Water Chemistry Sensitivity on Fibrous Debris Bypass Through a Containment Sump Strainer
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Topics: Containment, Water chemistry, Vessels, Accidents, Coolants, Electrical conductivity, Flow (Dynamics), Glass fiber insulation, Insulation, Nuclear power
Proceedings Papers

Corrosion Behavior of Zircaloy-4 in Methanol Solution at 320 °C Under Gamma-Irradiation

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Masafumi Domae, Kosho Hojo, Wataru Sugino
Proc. ASME. ICONE21, Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle and Balance of Plant; Nuclear Fuel and Materials; Radiation Protection and Nuclear Technology Applications, V001T02A009, July 29–August 2, 2013
Publisher: American Society of Mechanical Engineers
Paper No: ICONE21-15309
https://doi.org/10.1115/ICONE21-15309
View Paper titled, Corrosion Behavior of Zircaloy-4 in Methanol Solution at 320 °C Under Gamma-Irradiation
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Topics: Corrosion, Irradiation (Radiation exposure), Methanol, Hydrogen, Water, Carbon dioxide, Countermeasures, Graphite, Hydrogen storage, Organic compounds
Proceedings Papers

Effects of Prior-Deformation and Water Chemistry on Stress Corrosion Cracking of Austenitic Alloys in High Temperature Water

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Zhanpeng Lu, Tetsuo Shoji, Shuang Xia, Meiyi Yao, Bangxin Zhou
Proc. ASME. ICONE21, Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle and Balance of Plant; Nuclear Fuel and Materials; Radiation Protection and Nuclear Technology Applications, V001T02A036, July 29–August 2, 2013
Publisher: American Society of Mechanical Engineers
Paper No: ICONE21-16328
https://doi.org/10.1115/ICONE21-16328
View Paper titled, Effects of Prior-Deformation and Water Chemistry on Stress Corrosion Cracking of Austenitic Alloys in High Temperature Water
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Topics: Alloys, Deformation, High temperature, Stress corrosion cracking, Water, Water chemistry, Electrodes, Coolants, Equilibrium (Physics), Fracture (Materials)
Proceedings Papers

Ongoing Research of Water Chemistry Effect on SCC Properties of Candidate Materials for SCWR

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Bin Gong, Yan-ping Huang, E Jang, Jin-Hua Liu, Xiao-jiao Xia, Yong-Fu Zhao
Proc. ASME. ICONE21, Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle and Balance of Plant; Nuclear Fuel and Materials; Radiation Protection and Nuclear Technology Applications, V001T02A029, July 29–August 2, 2013
Publisher: American Society of Mechanical Engineers
Paper No: ICONE21-15876
https://doi.org/10.1115/ICONE21-15876
View Paper titled, Ongoing Research of Water Chemistry Effect on SCC Properties of Candidate Materials for SCWR
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Topics: Corrosion, Oxidation, Supercritical water reactors, Water, Water chemistry
Proceedings Papers

Scientific Bases of Water Chemistry for Corrosion Control of NPPs by Integration of Radiation- and Electro-Chemistry

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Genn Saji
Proc. ASME. ICONE21, Volume 2: Plant Systems, Construction, Structures and Components; Next Generation Reactors and Advanced Reactors, V002T03A053, July 29–August 2, 2013
Publisher: American Society of Mechanical Engineers
Paper No: ICONE21-16525
https://doi.org/10.1115/ICONE21-16525
View Paper titled, Scientific Bases of Water Chemistry for Corrosion Control of NPPs by Integration of Radiation- and Electro-Chemistry
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Topics: Corrosion, Corrosion protection, Electrochemistry, Nuclear power stations, Radiation (Physics), Water, Water chemistry
Proceedings Papers

Scientific Bases of Corrosion Control for Water-Cooled Fusion Reactors Such as ITER

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Genn Saji
Proc. ASME. ICONE20-POWER2012, Volume 5: Fusion Engineering; Student Paper Competition; Design Basis and Beyond Design Basis Events; Simple and Combined Cycles, 29-39, July 30–August 3, 2012
Publisher: American Society of Mechanical Engineers
Paper No: ICONE20-POWER2012-55046
https://doi.org/10.1115/ICONE20-POWER2012-55046
View Paper titled, Scientific Bases of Corrosion Control for Water-Cooled Fusion Reactors Such as ITER
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Topics: Cooling systems, Corrosion protection, Electrochemistry, Fusion reactors, Radiation (Physics), Water, Water chemistry, Corrosion, Chemistry, Light water reactors
Proceedings Papers

Supercritical-Water Experimental Setup for In-Pile Operation

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M. Miletić, M. Růžičková, R. Fukač, I. Pioro, W. Peiman
Proc. ASME. ICONE20-POWER2012, Volume 5: Fusion Engineering; Student Paper Competition; Design Basis and Beyond Design Basis Events; Simple and Combined Cycles, 401-410, July 30–August 3, 2012
Publisher: American Society of Mechanical Engineers
Paper No: ICONE20-POWER2012-54686
https://doi.org/10.1115/ICONE20-POWER2012-54686
View Paper titled, Supercritical-Water Experimental Setup for In-Pile Operation
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Topics: Nuclear fuels, Supercritical water reactors, Water, Design, Industrial research, Light water reactors, Advanced materials, Coolants, Corrosion, Energy generation
Proceedings Papers

Characterization of LWR Cores by Radiation- and Electro-Chemical Approaches for Corrosion Studies

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Genn Saji
Proc. ASME. ICONE20-POWER2012, Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle, and Balance of Plant; Component Reliability and Materials Issues; Steam Generator Technology Applications and Innovations; Advanced Reactors and Near-Term Deployment; Reactor Physics, Neutronics, and Transport Theory; Nuclear Education, Human Resources, and Public Acceptance, 517-530, July 30–August 3, 2012
Publisher: American Society of Mechanical Engineers
Paper No: ICONE20-POWER2012-55047
https://doi.org/10.1115/ICONE20-POWER2012-55047
View Paper titled, Characterization of LWR Cores by Radiation- and Electro-Chemical Approaches for Corrosion Studies
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Topics: Chemistry, Corrosion, Light water reactors, Radiation (Physics), Water, Water chemistry