1-17 of 17
ASTM International
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

A Systematic Study of the Material Performance of Hot Isostatically Pressed Type 316L Stainless Steel Powder for the Civil Nuclear Sector

William Kyffin, David Gandy, Barry Burdett
Proc. ASME. ICONE26, Volume 2: Plant Systems, Structures, Components, and Materials; Risk Assessments and Management, V002T03A017, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81438
https://doi.org/10.1115/ICONE26-81438
View Paper titled, A Systematic Study of the Material Performance of Hot Isostatically Pressed Type 316L Stainless Steel Powder for the Civil Nuclear Sector
Open the PDF for A Systematic Study of the Material Performance of Hot Isostatically Pressed Type 316L Stainless Steel Powder for the Civil Nuclear Sector in another window
Topics: Stainless steel, Manufacturing, Materials properties, Oxygen, ASTM International, Collaboration, Cycles, Defense industry, Electricity (Physics), Hot pressing
Proceedings Papers

Nuclear Air Cleaning Codes and Standards Development and Use in the United States

Ronald R. Bellamy
Proc. ASME. ICONE24, Volume 2: Smart Grids, Grid Stability, and Offsite and Emergency Power; Advanced and Next Generation Reactors, Fusion Technology; Safety, Security, and Cyber Security; Codes, Standards, Conformity Assessment, Licensing, and Regulatory Issues, V002T08A002, June 26–30, 2016
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-60119
https://doi.org/10.1115/ICONE24-60119
View Paper titled, Nuclear Air Cleaning Codes and Standards Development and Use in the United States
Open the PDF for Nuclear Air Cleaning Codes and Standards Development and Use in the United States in another window
Topics: Engineering standards, Nuclear power stations, Safety, Testing, Accidents, Activated carbon, ASME Standards, ASTM International, Boiling water reactors, Construction
Proceedings Papers

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

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
Open the PDF for Technical Basis of Fatigue Crack Growth Rate Curve for Ni-Base Alloy in BWR Water Environment in another window
Topics: Alloys, Boiling water reactors, Fatigue cracks, Water, Stress, Fitness-for-service, Corrosion, Fracture (Materials), Japan Society of Mechanical Engineers, ASTM International
Proceedings Papers

Introduction to KEPIC (Korea Electric Power Industry Code)

Myoung-Sung Sohn, Hyun-Jae Joo, Hoon-Seok Byun, Jong-Hae Kim
Proc. ASME. ICONE21, Volume 3: Nuclear Safety and Security; Codes, Standards, Licensing and Regulatory Issues; Computational Fluid Dynamics and Coupled Codes, V003T07A026, July 29–August 2, 2013
Publisher: American Society of Mechanical Engineers
Paper No: ICONE21-16827
https://doi.org/10.1115/ICONE21-16827
View Paper titled, Introduction to KEPIC (Korea Electric Power Industry Code)
Open the PDF for Introduction to KEPIC (Korea Electric Power Industry Code) in another window
Topics: Electricity (Physics), Engineering standards, Nuclear power stations, Construction, ASME Boiler and Pressure Vessel Code, Design, Welding, ASTM International, Concretes, Electric fields
Proceedings Papers

Automated, On-Line Loss-on-Ignition (LOI) Sensor

James A. Bickford, Michael Y. Feng, Mitchell Hansberry, Daniel Harjes, Eric Balles, Joe Estrada, Chris Hill, Bill Kirkenir
Proc. ASME. ICONE20-POWER2012, Volume 4: Codes, Standards, Licensing, and Regulatory Issues; Fuel Cycle, Radioactive Waste Management and Decommissioning; Computational Fluid Dynamics (CFD) and Coupled Codes; Instrumentation and Controls; Fuels and Combustion, Materials Handling, Emissions; Advanced Energy Systems and Renewables (Wind, Solar, Geothermal); Performance Testing and Performance Test Codes, 629-638, July 30–August 3, 2012
Publisher: American Society of Mechanical Engineers
Paper No: ICONE20-POWER2012-54238
https://doi.org/10.1115/ICONE20-POWER2012-54238
View Paper titled, Automated, On-Line Loss-on-Ignition (LOI) Sensor
Open the PDF for Automated, On-Line Loss-on-Ignition (LOI) Sensor in another window
Topics: Ignition, Sensors, Engineering prototypes, Fly ash, ASTM International, Coal power, Flue gases, Instrumentation, Power stations, Probes
Proceedings Papers

Case Studies in Nuclear Codes and Standards: A Successful Incorporation of Codes and Standards Into Engineering School Curriculum

Kenneth R. Balkey, G. Gary Elder, Larry R. Foulke, John D. Metzger
Proc. ASME. ICONE20-POWER2012, Volume 4: Codes, Standards, Licensing, and Regulatory Issues; Fuel Cycle, Radioactive Waste Management and Decommissioning; Computational Fluid Dynamics (CFD) and Coupled Codes; Instrumentation and Controls; Fuels and Combustion, Materials Handling, Emissions; Advanced Energy Systems and Renewables (Wind, Solar, Geothermal); Performance Testing and Performance Test Codes, 181-188, July 30–August 3, 2012
Publisher: American Society of Mechanical Engineers
Paper No: ICONE20-POWER2012-54894
https://doi.org/10.1115/ICONE20-POWER2012-54894
View Paper titled, Case Studies in Nuclear Codes and Standards: A Successful Incorporation of Codes and Standards Into Engineering School Curriculum
Open the PDF for Case Studies in Nuclear Codes and Standards: A Successful Incorporation of Codes and Standards Into Engineering School Curriculum in another window
Topics: Engineering standards, ASTM International, Education, Electronics engineers, Homework, Internet, Mechanical engineers, Nuclear power stations, Regulations, Students
Proceedings Papers

Structural Integrity of HDPE Piping and Joints in Nuclear Safety-Related Applications

S. Kalyanam, P. Krishnaswamy, D.-J. Shim, Y. Hioe, E. Focht
Proc. ASME. ICONE20-POWER2012, Volume 4: Codes, Standards, Licensing, and Regulatory Issues; Fuel Cycle, Radioactive Waste Management and Decommissioning; Computational Fluid Dynamics (CFD) and Coupled Codes; Instrumentation and Controls; Fuels and Combustion, Materials Handling, Emissions; Advanced Energy Systems and Renewables (Wind, Solar, Geothermal); Performance Testing and Performance Test Codes, 51-62, July 30–August 3, 2012
Publisher: American Society of Mechanical Engineers
Paper No: ICONE20-POWER2012-54192
https://doi.org/10.1115/ICONE20-POWER2012-54192
View Paper titled, Structural Integrity of HDPE Piping and Joints in Nuclear Safety-Related Applications
Open the PDF for Structural Integrity of HDPE Piping and Joints in Nuclear Safety-Related Applications in another window
Topics: Pipes, Safety, Stress, Nuclear power stations, Service life (Equipment), ASME Boiler and Pressure Vessel Code, ASTM International, Fracture mechanics, Pressure, Rupture
Proceedings Papers

Fracture Toughness Estimation for Small CT Specimen of Austenitic Stainless Steels Using Stretched Zone Width

Tadahiko Torimaru, Masanari Sugiyama, Hiroshi Sakamoto, Shigeaki Tanaka, Tomomi Nakamura
Proc. ASME. ICONE17, Volume 1: Plant Operations, Maintenance, Engineering, Modifications and Life Cycle; Component Reliability and Materials Issues; Next Generation Systems, 375-385, July 12–16, 2009
Publisher: American Society of Mechanical Engineers
Paper No: ICONE17-75233
https://doi.org/10.1115/ICONE17-75233
View Paper titled, Fracture Toughness Estimation for Small CT Specimen of Austenitic Stainless Steels Using Stretched Zone Width
Open the PDF for Fracture Toughness Estimation for Small CT Specimen of Austenitic Stainless Steels Using Stretched Zone Width in another window
Topics: Fracture toughness, Stainless steel, Dimensions, Boiling water reactors, ASTM International, Fatigue cracks, Fluence (Radiation measurement), Fracture (Materials), Fracture (Process), Irradiation (Radiation exposure)
Proceedings Papers

Investigation of the Beltline Welding Seam and Base Metal of the Greifswald WWER-440 Unit 1 Reactor Pressure Vessel

Jan Schuhknecht, Hans-Werner Viehrig, Udo Rindelhardt
Proc. ASME. ICONE17, Volume 1: Plant Operations, Maintenance, Engineering, Modifications and Life Cycle; Component Reliability and Materials Issues; Next Generation Systems, 289-295, July 12–16, 2009
Publisher: American Society of Mechanical Engineers
Paper No: ICONE17-75063
https://doi.org/10.1115/ICONE17-75063
View Paper titled, Investigation of the Beltline Welding Seam and Base Metal of the Greifswald WWER-440 Unit 1 Reactor Pressure Vessel
Open the PDF for Investigation of the Beltline Welding Seam and Base Metal of the Greifswald WWER-440 Unit 1 Reactor Pressure Vessel in another window
Topics: Base metals, Reactor vessels, Welding, Metals, Temperature, ASTM International, Irradiation (Radiation exposure), Nuclear power stations, Steel, Testing
Proceedings Papers

Long-Term Strength and Design of Polyethylene Compounds for Pressure Pipe Applications

Stephen J. Boros
Proc. ASME. ICONE17, Volume 4: Codes, Standards, Licensing and Regulatory Issues; Student Paper Competition, 255-265, July 12–16, 2009
Publisher: American Society of Mechanical Engineers
Paper No: ICONE17-76052
https://doi.org/10.1115/ICONE17-76052
View Paper titled, Long-Term Strength and Design of Polyethylene Compounds for Pressure Pipe Applications
Open the PDF for Long-Term Strength and Design of Polyethylene Compounds for Pressure Pipe Applications in another window
Topics: Design, Pressure pipes, Stress, Hydrostatics, Polyethylene pipes, Temperature, Failure, Pipes, Plastics, Testing
Proceedings Papers

A Modern Approach to Condition-Based Maintenance of Reinforced Rubber Cooling System Expansion Joints Utilizing a Microwave Non-Destructive Inspection Method

Jack Little, Robert Stakenborghs
Proc. ASME. ICONE17, Volume 2: Structural Integrity; Safety and Security; Advanced Applications of Nuclear Technology; Balance of Plant for Nuclear Applications, 1003-1009, July 12–16, 2009
Publisher: American Society of Mechanical Engineers
Paper No: ICONE17-75602
https://doi.org/10.1115/ICONE17-75602
View Paper titled, A Modern Approach to Condition-Based Maintenance of Reinforced Rubber Cooling System Expansion Joints Utilizing a Microwave Non-Destructive Inspection Method
Open the PDF for A Modern Approach to Condition-Based Maintenance of Reinforced Rubber Cooling System Expansion Joints Utilizing a Microwave Non-Destructive Inspection Method in another window
Topics: Cooling systems, Expansion joints, Maintenance, Microwaves, Nondestructive evaluation, Rubber, Inspection, Rubber products, ASTM International, Building materials
Proceedings Papers

Weld Material Investigations of a WWER-440 Reactor Pressure Vessel: Results From the First Trepan Taken From the Former Greifswald NPP

Udo Rindelhardt, Hans-Werner Viehrig, Joerg Konheiser, Jan Schuhknecht
Proc. ASME. ICONE16, Volume 1: Plant Operations, Maintenance, Installations and Life Cycle; Component Reliability and Materials Issues; Advanced Applications of Nuclear Technology; Codes, Standards, Licensing and Regulatory Issues, 423-431, May 11–15, 2008
Publisher: American Society of Mechanical Engineers
Paper No: ICONE16-48070
https://doi.org/10.1115/ICONE16-48070
View Paper titled, Weld Material Investigations of a WWER-440 Reactor Pressure Vessel: Results From the First Trepan Taken From the Former Greifswald NPP
Open the PDF for Weld Material Investigations of a WWER-440 Reactor Pressure Vessel: Results From the First Trepan Taken From the Former Greifswald NPP in another window
Topics: Nuclear power stations, Reactor vessels, Fluence (Radiation measurement), Neutrons, Brittleness, Temperature, Cycles, Fracture toughness, Metals, Welded joints
Proceedings Papers

Results on Attenuation of Neutron Embrittlement Effects

Milan Brumovsky´, Milosˇ Kytka, William Server, Naoki Soneda, Jack Spanner
Proc. ASME. ICONE16, Volume 1: Plant Operations, Maintenance, Installations and Life Cycle; Component Reliability and Materials Issues; Advanced Applications of Nuclear Technology; Codes, Standards, Licensing and Regulatory Issues, 671-678, May 11–15, 2008
Publisher: American Society of Mechanical Engineers
Paper No: ICONE16-48710
https://doi.org/10.1115/ICONE16-48710
View Paper titled, Results on Attenuation of Neutron Embrittlement Effects
Open the PDF for Results on Attenuation of Neutron Embrittlement Effects in another window
Topics: Embrittlement, Neutrons, Copper, Steel, ASTM International, Fluence (Radiation measurement), Fracture toughness, Atoms, Damage, Irradiation (Radiation exposure)
Proceedings Papers

Scratch Tip Radius Effects on K -Controlled Slow Crack Growth in PE Pipe

Carlos R. Corleto, Brian B. Cole
Proc. ASME. ICONE16, Volume 1: Plant Operations, Maintenance, Installations and Life Cycle; Component Reliability and Materials Issues; Advanced Applications of Nuclear Technology; Codes, Standards, Licensing and Regulatory Issues, 981-985, May 11–15, 2008
Publisher: American Society of Mechanical Engineers
Paper No: ICONE16-48577
https://doi.org/10.1115/ICONE16-48577
View Paper titled, Scratch Tip Radius Effects on K -Controlled Slow Crack Growth in PE Pipe
Open the PDF for Scratch Tip Radius Effects on K -Controlled Slow Crack Growth in PE Pipe in another window
Topics: Fracture (Materials), Polyethylene pipes, Pipes, Finite element analysis, Hoop stress, Stress, ASTM International, Failure, High temperature, Pipe and tube industry
Proceedings Papers

J Resistance Curve Estimation of Inhomogeneous CT Specimen

Kiminobu Hojo, Kazutoshi Ohoto, Itaru Muroya
Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 1, 461-482, April 14–18, 2002
Publisher: American Society of Mechanical Engineers
Paper No: ICONE10-22047
https://doi.org/10.1115/ICONE10-22047
View Paper titled, J Resistance Curve Estimation of Inhomogeneous CT Specimen
Open the PDF for J Resistance Curve Estimation of Inhomogeneous CT Specimen in another window
Topics: ASTM International, Finite element analysis, Fracture toughness, Plane strain, Stress
Proceedings Papers

Simulations of Thermal Performance for One- and Two-Dimensional Insulation and Aluminum Foil Fire Barriers

Mauricio A. Sa´nchez, William H. Sutton, Carlos A. Sa´nchez
Proc. ASME. ICONE12, 12th International Conference on Nuclear Engineering, Volume 3, 89-95, April 25–29, 2004
Publisher: American Society of Mechanical Engineers
Paper No: ICONE12-49265
https://doi.org/10.1115/ICONE12-49265
View Paper titled, Simulations of Thermal Performance for One- and Two-Dimensional Insulation and Aluminum Foil Fire Barriers
Open the PDF for Simulations of Thermal Performance for One- and Two-Dimensional Insulation and Aluminum Foil Fire Barriers in another window
Topics: Aluminum foil, Engineering simulation, Fire, Insulation, Simulation, Computer simulation, Concretes, Corners (Structural elements), Approximation, ASTM International
Proceedings Papers

Statistical Analyses for Probabilistic Assessments of the Reactor Pressure Vessel Structural Integrity: Building a Master Curve on an Extract of the “Euro” Fracture Toughness Dataset, Controlling Statistical Uncertainty for Both Mono-Temperature and Multi-Temperature Tests

Florent Josse, Yannick Lefebvre, Patrick Todeschini, Silvia Turato, Eric Meister
Proc. ASME. ICONE14, Volume 1: Plant Operations, Maintenance and Life Cycle; Component Reliability and Materials Issues; Codes, Standards, Licensing and Regulatory Issues; Fuel Cycle and High Level Waste Management, 553-561, July 17–20, 2006
Publisher: American Society of Mechanical Engineers
Paper No: ICONE14-89481
https://doi.org/10.1115/ICONE14-89481
View Paper titled, Statistical Analyses for Probabilistic Assessments of the Reactor Pressure Vessel Structural Integrity: Building a Master Curve on an Extract of the “Euro” Fracture Toughness Dataset, Controlling Statistical Uncertainty for Both Mono-Temperature and Multi-Temperature Tests
Open the PDF for Statistical Analyses for Probabilistic Assessments of the Reactor Pressure Vessel Structural Integrity: Building a Master Curve on an Extract of the “Euro” Fracture Toughness Dataset, Controlling Statistical Uncertainty for Both Mono-Temperature and Multi-Temperature Tests in another window
Topics: Fracture toughness, Reactor vessels, Statistical analysis, Temperature, Uncertainty, Steel, Pressure vessels, Temperature effects, ASME Standards, ASTM International