cometadata/datacite-titles-descriptions-related-identifiers huggingface dataset:
DOI: 10.5290/207220006
title: Test data for uniaxial creep on material ALLOY 800H at 900 Celsius and a stress of 30 MPa (repeat test)

description: The creep rupture data in this collection were determined for the high temperature reactor projects (the direct cycle helium turbine project, the nuclear process heat project and the district heating project) of the Federal Republic of Germany and the State of North Rhine Westphalia, the aim being to qualify the candidate constructional alloys for service at temperatures up to 950°C. Several batches of each alloy were investigated and special attention was given to the effects of the service environments (helium containing different impurity gases, such as hydrogen, water vapour, carbon monoxide and methane, all at microbar levels, and methane reforming gas mixture) on the properties. In the test machines, these test environments led to carburisation of test pieces.  However, analysis of the data showed that the stress rupture data for tests in air, in impure helium and in methane reforming gas lay in the same scatterband at each temperatures tested.
 
 The data were used for the formulation of draft nuclear design rules for the high temperature reactor systems, which are summarised in 'Proceedings of the Workshop on Structural Design Criteria for HTR', G Breitbach, F Schubert, H Nickel, Jül-Conf-71, April 1989, Berichte der Kernforschungsanlage Jülich GmbH, ISSN 0344-5798.
DOI: 10.5290/207220007
title: Test data for uniaxial creep on material ALLOY 800H at 900 Celsius and a stress of 30 MPa

description: The creep rupture data in this collection were determined for the high temperature reactor projects (the direct cycle helium turbine project, the nuclear process heat project and the district heating project) of the Federal Republic of Germany and the State of North Rhine Westphalia, the aim being to qualify the candidate constructional alloys for service at temperatures up to 950°C. Several batches of each alloy were investigated and special attention was given to the effects of the service environments (helium containing different impurity gases, such as hydrogen, water vapour, carbon monoxide and methane, all at microbar levels, and methane reforming gas mixture) on the properties. In the test machines, these test environments led to carburisation of test pieces.  However, analysis of the data showed that the stress rupture data for tests in air, in impure helium and in methane reforming gas lay in the same scatterband at each temperatures tested.
 
 The data were used for the formulation of draft nuclear design rules for the high temperature reactor systems, which are summarised in 'Proceedings of the Workshop on Structural Design Criteria for HTR', G Breitbach, F Schubert, H Nickel, Jül-Conf-71, April 1989, Berichte der Kernforschungsanlage Jülich GmbH, ISSN 0344-5798.
DOI: 10.5290/207220008
title: Test data for uniaxial creep on material ALLOY 800H at 800 Celsius and a stress of 75 MPa

description: The creep rupture data in this collection were determined for the high temperature reactor projects (the direct cycle helium turbine project, the nuclear process heat project and the district heating project) of the Federal Republic of Germany and the State of North Rhine Westphalia, the aim being to qualify the candidate constructional alloys for service at temperatures up to 950°C. Several batches of each alloy were investigated and special attention was given to the effects of the service environments (helium containing different impurity gases, such as hydrogen, water vapour, carbon monoxide and methane, all at microbar levels, and methane reforming gas mixture) on the properties. In the test machines, these test environments led to carburisation of test pieces.  However, analysis of the data showed that the stress rupture data for tests in air, in impure helium and in methane reforming gas lay in the same scatterband at each temperatures tested.
 
 The data were used for the formulation of draft nuclear design rules for the high temperature reactor systems, which are summarised in 'Proceedings of the Workshop on Structural Design Criteria for HTR', G Breitbach, F Schubert, H Nickel, Jül-Conf-71, April 1989, Berichte der Kernforschungsanlage Jülich GmbH, ISSN 0344-5798.
DOI: 10.5290/207220009
title: Test data for uniaxial creep on material ALLOY 800H at 800 Celsius and a stress of 60 MPa

description: The creep rupture data in this collection were determined for the high temperature reactor projects (the direct cycle helium turbine project, the nuclear process heat project and the district heating project) of the Federal Republic of Germany and the State of North Rhine Westphalia, the aim being to qualify the candidate constructional alloys for service at temperatures up to 950°C. Several batches of each alloy were investigated and special attention was given to the effects of the service environments (helium containing different impurity gases, such as hydrogen, water vapour, carbon monoxide and methane, all at microbar levels, and methane reforming gas mixture) on the properties. In the test machines, these test environments led to carburisation of test pieces.  However, analysis of the data showed that the stress rupture data for tests in air, in impure helium and in methane reforming gas lay in the same scatterband at each temperatures tested.
 
 The data were used for the formulation of draft nuclear design rules for the high temperature reactor systems, which are summarised in 'Proceedings of the Workshop on Structural Design Criteria for HTR', G Breitbach, F Schubert, H Nickel, Jül-Conf-71, April 1989, Berichte der Kernforschungsanlage Jülich GmbH, ISSN 0344-5798.
DOI: 10.5290/207220010
title: Test data for uniaxial creep on material ALLOY 800H at 800 Celsius and a stress of 45 MPa

description: The creep rupture data in this collection were determined for the high temperature reactor projects (the direct cycle helium turbine project, the nuclear process heat project and the district heating project) of the Federal Republic of Germany and the State of North Rhine Westphalia, the aim being to qualify the candidate constructional alloys for service at temperatures up to 950°C. Several batches of each alloy were investigated and special attention was given to the effects of the service environments (helium containing different impurity gases, such as hydrogen, water vapour, carbon monoxide and methane, all at microbar levels, and methane reforming gas mixture) on the properties. In the test machines, these test environments led to carburisation of test pieces.  However, analysis of the data showed that the stress rupture data for tests in air, in impure helium and in methane reforming gas lay in the same scatterband at each temperatures tested.
 
 The data were used for the formulation of draft nuclear design rules for the high temperature reactor systems, which are summarised in 'Proceedings of the Workshop on Structural Design Criteria for HTR', G Breitbach, F Schubert, H Nickel, Jül-Conf-71, April 1989, Berichte der Kernforschungsanlage Jülich GmbH, ISSN 0344-5798.
DOI: 10.5290/4700000
title: Uniaxial tensile test data for A533B  wm material at 25 °C

description: The Network for Evaluating Structural Components (NESC) coordinated extensive materials testing and fracture analyses performed by a group of twenty European organizations. The NESC-IV project addressed the transferability of fracture toughness data from laboratory specimens to applications that assess the integrity of reactor pressure vessels subjected to upset and normal loading transients. The coordinated experimental and analytical program drew from major elements of the biaxial features testing program conducted by the Heavy Section Steel Technology Program at the Oak Ridge National Laboratory. In this context, the JRC performed impact and tensile tests in the temperature range -90 to 80ºC on type A533B ferritic steel.
DOI: 10.5290/4700001
title: Impact test data for A533B  wm material at -2 °C and a notch impact energy of 80 J

description: The Network for Evaluating Structural Components (NESC) coordinated extensive materials testing and fracture analyses performed by a group of twenty European organizations. The NESC-IV project addressed the transferability of fracture toughness data from laboratory specimens to applications that assess the integrity of reactor pressure vessels subjected to upset and normal loading transients. The coordinated experimental and analytical program drew from major elements of the biaxial features testing program conducted by the Heavy Section Steel Technology Program at the Oak Ridge National Laboratory. In this context, the JRC performed impact and tensile tests in the temperature range -90 to 80ºC on type A533B ferritic steel.
DOI: 10.5290/4700002
title: Uniaxial tensile test data for A533B  wm material at -30 °C

description: The Network for Evaluating Structural Components (NESC) coordinated extensive materials testing and fracture analyses performed by a group of twenty European organizations. The NESC-IV project addressed the transferability of fracture toughness data from laboratory specimens to applications that assess the integrity of reactor pressure vessels subjected to upset and normal loading transients. The coordinated experimental and analytical program drew from major elements of the biaxial features testing program conducted by the Heavy Section Steel Technology Program at the Oak Ridge National Laboratory. In this context, the JRC performed impact and tensile tests in the temperature range -90 to 80ºC on type A533B ferritic steel.
DOI: 10.5290/4700003
title: Uniaxial tensile test data for A533B  wm material at -10 °C

description: The Network for Evaluating Structural Components (NESC) coordinated extensive materials testing and fracture analyses performed by a group of twenty European organizations. The NESC-IV project addressed the transferability of fracture toughness data from laboratory specimens to applications that assess the integrity of reactor pressure vessels subjected to upset and normal loading transients. The coordinated experimental and analytical program drew from major elements of the biaxial features testing program conducted by the Heavy Section Steel Technology Program at the Oak Ridge National Laboratory. In this context, the JRC performed impact and tensile tests in the temperature range -90 to 80ºC on type A533B ferritic steel.
DOI: 10.5290/4700004
title: Uniaxial tensile test data for A533B  wm material at -50 °C

description: The Network for Evaluating Structural Components (NESC) coordinated extensive materials testing and fracture analyses performed by a group of twenty European organizations. The NESC-IV project addressed the transferability of fracture toughness data from laboratory specimens to applications that assess the integrity of reactor pressure vessels subjected to upset and normal loading transients. The coordinated experimental and analytical program drew from major elements of the biaxial features testing program conducted by the Heavy Section Steel Technology Program at the Oak Ridge National Laboratory. In this context, the JRC performed impact and tensile tests in the temperature range -90 to 80ºC on type A533B ferritic steel.
DOI: 10.5290/4700005
title: Uniaxial tensile test data for A533B  wm material at -70 °C

description: The Network for Evaluating Structural Components (NESC) coordinated extensive materials testing and fracture analyses performed by a group of twenty European organizations. The NESC-IV project addressed the transferability of fracture toughness data from laboratory specimens to applications that assess the integrity of reactor pressure vessels subjected to upset and normal loading transients. The coordinated experimental and analytical program drew from major elements of the biaxial features testing program conducted by the Heavy Section Steel Technology Program at the Oak Ridge National Laboratory. In this context, the JRC performed impact and tensile tests in the temperature range -90 to 80ºC on type A533B ferritic steel.
DOI: 10.5290/4700006
title: Impact test data for A533B  wm material at -25 °C and a notch impact energy of 54 J

description: The Network for Evaluating Structural Components (NESC) coordinated extensive materials testing and fracture analyses performed by a group of twenty European organizations. The NESC-IV project addressed the transferability of fracture toughness data from laboratory specimens to applications that assess the integrity of reactor pressure vessels subjected to upset and normal loading transients. The coordinated experimental and analytical program drew from major elements of the biaxial features testing program conducted by the Heavy Section Steel Technology Program at the Oak Ridge National Laboratory. In this context, the JRC performed impact and tensile tests in the temperature range -90 to 80ºC on type A533B ferritic steel.
DOI: 10.5290/4700007
title: Impact test data for A533B  wm material at -2 °C and a notch impact energy of 75 J

description: The Network for Evaluating Structural Components (NESC) coordinated extensive materials testing and fracture analyses performed by a group of twenty European organizations. The NESC-IV project addressed the transferability of fracture toughness data from laboratory specimens to applications that assess the integrity of reactor pressure vessels subjected to upset and normal loading transients. The coordinated experimental and analytical program drew from major elements of the biaxial features testing program conducted by the Heavy Section Steel Technology Program at the Oak Ridge National Laboratory. In this context, the JRC performed impact and tensile tests in the temperature range -90 to 80ºC on type A533B ferritic steel.
DOI: 10.5290/4700008
title: Impact test data for A533B  wm material at 22 °C and a notch impact energy of 114 J

description: The Network for Evaluating Structural Components (NESC) coordinated extensive materials testing and fracture analyses performed by a group of twenty European organizations. The NESC-IV project addressed the transferability of fracture toughness data from laboratory specimens to applications that assess the integrity of reactor pressure vessels subjected to upset and normal loading transients. The coordinated experimental and analytical program drew from major elements of the biaxial features testing program conducted by the Heavy Section Steel Technology Program at the Oak Ridge National Laboratory. In this context, the JRC performed impact and tensile tests in the temperature range -90 to 80ºC on type A533B ferritic steel.
DOI: 10.5290/4700009
title: Impact test data for A533B  wm material at -50 °C and a notch impact energy of 29 J

description: The Network for Evaluating Structural Components (NESC) coordinated extensive materials testing and fracture analyses performed by a group of twenty European organizations. The NESC-IV project addressed the transferability of fracture toughness data from laboratory specimens to applications that assess the integrity of reactor pressure vessels subjected to upset and normal loading transients. The coordinated experimental and analytical program drew from major elements of the biaxial features testing program conducted by the Heavy Section Steel Technology Program at the Oak Ridge National Laboratory. In this context, the JRC performed impact and tensile tests in the temperature range -90 to 80ºC on type A533B ferritic steel.
DOI: 10.5290/4700010
title: Impact test data for A533B  wm material at 50 °C and a notch impact energy of 120 J

description: The Network for Evaluating Structural Components (NESC) coordinated extensive materials testing and fracture analyses performed by a group of twenty European organizations. The NESC-IV project addressed the transferability of fracture toughness data from laboratory specimens to applications that assess the integrity of reactor pressure vessels subjected to upset and normal loading transients. The coordinated experimental and analytical program drew from major elements of the biaxial features testing program conducted by the Heavy Section Steel Technology Program at the Oak Ridge National Laboratory. In this context, the JRC performed impact and tensile tests in the temperature range -90 to 80ºC on type A533B ferritic steel.
DOI: 10.5290/4700011
title: Impact test data for A533B  wm material at -60 °C and a notch impact energy of 11 J

description: The Network for Evaluating Structural Components (NESC) coordinated extensive materials testing and fracture analyses performed by a group of twenty European organizations. The NESC-IV project addressed the transferability of fracture toughness data from laboratory specimens to applications that assess the integrity of reactor pressure vessels subjected to upset and normal loading transients. The coordinated experimental and analytical program drew from major elements of the biaxial features testing program conducted by the Heavy Section Steel Technology Program at the Oak Ridge National Laboratory. In this context, the JRC performed impact and tensile tests in the temperature range -90 to 80ºC on type A533B ferritic steel.
DOI: 10.5290/4700012
title: Impact test data for A533B  wm material at 60 °C and a notch impact energy of 114 J

description: The Network for Evaluating Structural Components (NESC) coordinated extensive materials testing and fracture analyses performed by a group of twenty European organizations. The NESC-IV project addressed the transferability of fracture toughness data from laboratory specimens to applications that assess the integrity of reactor pressure vessels subjected to upset and normal loading transients. The coordinated experimental and analytical program drew from major elements of the biaxial features testing program conducted by the Heavy Section Steel Technology Program at the Oak Ridge National Laboratory. In this context, the JRC performed impact and tensile tests in the temperature range -90 to 80ºC on type A533B ferritic steel.
DOI: 10.5290/4700013
title: Impact test data for A533B  wm material at -70 °C and a notch impact energy of 8 J

description: The Network for Evaluating Structural Components (NESC) coordinated extensive materials testing and fracture analyses performed by a group of twenty European organizations. The NESC-IV project addressed the transferability of fracture toughness data from laboratory specimens to applications that assess the integrity of reactor pressure vessels subjected to upset and normal loading transients. The coordinated experimental and analytical program drew from major elements of the biaxial features testing program conducted by the Heavy Section Steel Technology Program at the Oak Ridge National Laboratory. In this context, the JRC performed impact and tensile tests in the temperature range -90 to 80ºC on type A533B ferritic steel.
DOI: 10.5290/4700014
title: Impact test data for A533B  wm material at -35 °C and a notch impact energy of 20 J

description: The Network for Evaluating Structural Components (NESC) coordinated extensive materials testing and fracture analyses performed by a group of twenty European organizations. The NESC-IV project addressed the transferability of fracture toughness data from laboratory specimens to applications that assess the integrity of reactor pressure vessels subjected to upset and normal loading transients. The coordinated experimental and analytical program drew from major elements of the biaxial features testing program conducted by the Heavy Section Steel Technology Program at the Oak Ridge National Laboratory. In this context, the JRC performed impact and tensile tests in the temperature range -90 to 80ºC on type A533B ferritic steel.
DOI: 10.5290/4700015
title: Impact test data for A533B  wm material at 10 °C and a notch impact energy of 90 J

description: The Network for Evaluating Structural Components (NESC) coordinated extensive materials testing and fracture analyses performed by a group of twenty European organizations. The NESC-IV project addressed the transferability of fracture toughness data from laboratory specimens to applications that assess the integrity of reactor pressure vessels subjected to upset and normal loading transients. The coordinated experimental and analytical program drew from major elements of the biaxial features testing program conducted by the Heavy Section Steel Technology Program at the Oak Ridge National Laboratory. In this context, the JRC performed impact and tensile tests in the temperature range -90 to 80ºC on type A533B ferritic steel.
DOI: 10.5290/4700016
title: Impact test data for A533B  wm material at -15 °C and a notch impact energy of 24 J

description: The Network for Evaluating Structural Components (NESC) coordinated extensive materials testing and fracture analyses performed by a group of twenty European organizations. The NESC-IV project addressed the transferability of fracture toughness data from laboratory specimens to applications that assess the integrity of reactor pressure vessels subjected to upset and normal loading transients. The coordinated experimental and analytical program drew from major elements of the biaxial features testing program conducted by the Heavy Section Steel Technology Program at the Oak Ridge National Laboratory. In this context, the JRC performed impact and tensile tests in the temperature range -90 to 80ºC on type A533B ferritic steel.
DOI: 10.5290/4700017
title: Impact test data for A533B  wm material at 35 °C and a notch impact energy of 111 J

description: The Network for Evaluating Structural Components (NESC) coordinated extensive materials testing and fracture analyses performed by a group of twenty European organizations. The NESC-IV project addressed the transferability of fracture toughness data from laboratory specimens to applications that assess the integrity of reactor pressure vessels subjected to upset and normal loading transients. The coordinated experimental and analytical program drew from major elements of the biaxial features testing program conducted by the Heavy Section Steel Technology Program at the Oak Ridge National Laboratory. In this context, the JRC performed impact and tensile tests in the temperature range -90 to 80ºC on type A533B ferritic steel.
DOI: 10.5290/4700018
title: Impact test data for A533B  wm material at -15 °C and a notch impact energy of 71 J

description: The Network for Evaluating Structural Components (NESC) coordinated extensive materials testing and fracture analyses performed by a group of twenty European organizations. The NESC-IV project addressed the transferability of fracture toughness data from laboratory specimens to applications that assess the integrity of reactor pressure vessels subjected to upset and normal loading transients. The coordinated experimental and analytical program drew from major elements of the biaxial features testing program conducted by the Heavy Section Steel Technology Program at the Oak Ridge National Laboratory. In this context, the JRC performed impact and tensile tests in the temperature range -90 to 80ºC on type A533B ferritic steel.
DOI: 10.5290/4700019
title: Impact test data for A533B  wm material at 10 °C and a notch impact energy of 91 J

description: The Network for Evaluating Structural Components (NESC) coordinated extensive materials testing and fracture analyses performed by a group of twenty European organizations. The NESC-IV project addressed the transferability of fracture toughness data from laboratory specimens to applications that assess the integrity of reactor pressure vessels subjected to upset and normal loading transients. The coordinated experimental and analytical program drew from major elements of the biaxial features testing program conducted by the Heavy Section Steel Technology Program at the Oak Ridge National Laboratory. In this context, the JRC performed impact and tensile tests in the temperature range -90 to 80ºC on type A533B ferritic steel.