cometadata/datacite-titles-descriptions-related-identifiers huggingface dataset:
DOI: 10.5290/2590005
title: Uniaxial creep test data for P91 ar material at 650 °C and a stress of 100 MPa (specimen identifier T11359)

description: Uniaxial creep rupture and creep-fatigue tests have been performed using P91 material in a variety of conditions (ex-service parent metal, new parent metal and ex-service cross-weld specimens). All tests were performed at constant temperature, using machines located at the Australian Nuclear Science and Technology Organisation (ANSTO).
DOI: 10.5290/2590008
title: Uniaxial creep test data for P91 ar material at 630 °C and a stress of 100 MPa (specimen identifier T12060)

description: Uniaxial creep rupture and creep-fatigue tests have been performed using P91 material in a variety of conditions (ex-service parent metal, new parent metal and ex-service cross-weld specimens). All tests were performed at constant temperature, using machines located at the Australian Nuclear Science and Technology Organisation (ANSTO).
DOI: 10.5290/2500001
title: Uniaxial creep test data for P91 ar material at 550 °C and a stress of 230 MPa (specimen identifier MC-08-b)

description: The 2010-2012 implementation plan of the European Sustainable Nuclear Industrial Initiative (ESNII), in the frame of the Sustainable Nuclear Energy Technology Platform (SNE TP), establishes a very tight time schedule for the start of construction of the European Gen IV prototypes; namely the construction of the LFR ETPP (European Technology Pilot Plant) Myrrha will start in 2014 and that of the SFR Prototype ASTRID will start in 2017. The GEN IV reactors pose new challenges to the designers and scientists in terms of higher operating temperature and higher irradiation damage of materials with respect to the present technologies. In this frame, the MATTER (MATerials TEsting and Rules) Project intends to start well targeted researches to perform careful studies of materials behaviors in GEN IV operational conditions and to find out criteria for the correct use of these materials in relevant reactor applications. In that context, the JRC has carried out different tests (LCF, Creep, Small Punch Creep, Small Punch Tensile/Fracture) tests on P91 and 316. The activities were carried out in the frame of the MATTER project (Grant agreement no: 269706).
DOI: 10.5290/2590006
title: Uniaxial creep test data for P91 ar material at 660 °C and a stress of 100 MPa (specimen identifier T11360)

description: Uniaxial creep rupture and creep-fatigue tests have been performed using P91 material in a variety of conditions (ex-service parent metal, new parent metal and ex-service cross-weld specimens). All tests were performed at constant temperature, using machines located at the Australian Nuclear Science and Technology Organisation (ANSTO).
DOI: 10.5290/2590007
title: Uniaxial creep test data for P91 ar material at 670 °C and a stress of 100 MPa (specimen identifier T11361)

description: Uniaxial creep rupture and creep-fatigue tests have been performed using P91 material in a variety of conditions (ex-service parent metal, new parent metal and ex-service cross-weld specimens). All tests were performed at constant temperature, using machines located at the Australian Nuclear Science and Technology Organisation (ANSTO).
DOI: 10.5290/2500002
title: Uniaxial creep test data for P91 ar material at 600 °C and a stress of 155 MPa (specimen identifier MC-06)

description: The 2010-2012 implementation plan of the European Sustainable Nuclear Industrial Initiative (ESNII), in the frame of the Sustainable Nuclear Energy Technology Platform (SNE TP), establishes a very tight time schedule for the start of construction of the European Gen IV prototypes; namely the construction of the LFR ETPP (European Technology Pilot Plant) Myrrha will start in 2014 and that of the SFR Prototype ASTRID will start in 2017. The GEN IV reactors pose new challenges to the designers and scientists in terms of higher operating temperature and higher irradiation damage of materials with respect to the present technologies. In this frame, the MATTER (MATerials TEsting and Rules) Project intends to start well targeted researches to perform careful studies of materials behaviors in GEN IV operational conditions and to find out criteria for the correct use of these materials in relevant reactor applications. In that context, the JRC has carried out different tests (LCF, Creep, Small Punch Creep, Small Punch Tensile/Fracture) tests on P91 and 316. The activities were carried out in the frame of the MATTER project (Grant agreement no: 269706).
DOI: 10.5290/2500046
title: Uniaxial creep test data for P91 ar material at 600 °C and a stress of 155 MPa (specimen identifier AA001)

description: The 2010-2012 implementation plan of the European Sustainable Nuclear Industrial Initiative (ESNII), in the frame of the Sustainable Nuclear Energy Technology Platform (SNE TP), establishes a very tight time schedule for the start of construction of the European Gen IV prototypes; namely the construction of the LFR ETPP (European Technology Pilot Plant) Myrrha will start in 2014 and that of the SFR Prototype ASTRID will start in 2017. The GEN IV reactors pose new challenges to the designers and scientists in terms of higher operating temperature and higher irradiation damage of materials with respect to the present technologies. In this frame, the MATTER (MATerials TEsting and Rules) Project intends to start well targeted researches to perform careful studies of materials behaviors in GEN IV operational conditions and to find out criteria for the correct use of these materials in relevant reactor applications. In that context, the JRC has carried out different tests (LCF, Creep, Small Punch Creep, Small Punch Tensile/Fracture) tests on P91 and 316. The activities were carried out in the frame of the MATTER project (Grant agreement no: 269706).
DOI: 10.5290/2500076
title: Uniaxial creep test data for P91 ar material at 500 °C and a stress of 171 MPa (specimen identifier MC-01)

description: The 2010-2012 implementation plan of the European Sustainable Nuclear Industrial Initiative (ESNII), in the frame of the Sustainable Nuclear Energy Technology Platform (SNE TP), establishes a very tight time schedule for the start of construction of the European Gen IV prototypes; namely the construction of the LFR ETPP (European Technology Pilot Plant) Myrrha will start in 2014 and that of the SFR Prototype ASTRID will start in 2017. The GEN IV reactors pose new challenges to the designers and scientists in terms of higher operating temperature and higher irradiation damage of materials with respect to the present technologies. In this frame, the MATTER (MATerials TEsting and Rules) Project intends to start well targeted researches to perform careful studies of materials behaviors in GEN IV operational conditions and to find out criteria for the correct use of these materials in relevant reactor applications. In that context, the JRC has carried out different tests (LCF, Creep, Small Punch Creep, Small Punch Tensile/Fracture) tests on P91 and 316. The activities were carried out in the frame of the MATTER project (Grant agreement no: 269706).
DOI: 10.5290/2500077
title: Uniaxial creep test data for P91 ar material at 450 °C and a stress of 280 MPa (specimen identifier MC-02)

description: The 2010-2012 implementation plan of the European Sustainable Nuclear Industrial Initiative (ESNII), in the frame of the Sustainable Nuclear Energy Technology Platform (SNE TP), establishes a very tight time schedule for the start of construction of the European Gen IV prototypes; namely the construction of the LFR ETPP (European Technology Pilot Plant) Myrrha will start in 2014 and that of the SFR Prototype ASTRID will start in 2017. The GEN IV reactors pose new challenges to the designers and scientists in terms of higher operating temperature and higher irradiation damage of materials with respect to the present technologies. In this frame, the MATTER (MATerials TEsting and Rules) Project intends to start well targeted researches to perform careful studies of materials behaviors in GEN IV operational conditions and to find out criteria for the correct use of these materials in relevant reactor applications. In that context, the JRC has carried out different tests (LCF, Creep, Small Punch Creep, Small Punch Tensile/Fracture) tests on P91 and 316. The activities were carried out in the frame of the MATTER project (Grant agreement no: 269706).
DOI: 10.5290/2500078
title: Uniaxial creep test data for P91 ar material at 425 °C and a stress of 330 MPa (specimen identifier MC-03)

description: The 2010-2012 implementation plan of the European Sustainable Nuclear Industrial Initiative (ESNII), in the frame of the Sustainable Nuclear Energy Technology Platform (SNE TP), establishes a very tight time schedule for the start of construction of the European Gen IV prototypes; namely the construction of the LFR ETPP (European Technology Pilot Plant) Myrrha will start in 2014 and that of the SFR Prototype ASTRID will start in 2017. The GEN IV reactors pose new challenges to the designers and scientists in terms of higher operating temperature and higher irradiation damage of materials with respect to the present technologies. In this frame, the MATTER (MATerials TEsting and Rules) Project intends to start well targeted researches to perform careful studies of materials behaviors in GEN IV operational conditions and to find out criteria for the correct use of these materials in relevant reactor applications. In that context, the JRC has carried out different tests (LCF, Creep, Small Punch Creep, Small Punch Tensile/Fracture) tests on P91 and 316. The activities were carried out in the frame of the MATTER project (Grant agreement no: 269706).
DOI: 10.5290/2500079
title: Uniaxial creep test data for P91 ar material at 400 °C and a stress of 380 MPa (specimen identifier MC-05)

description: The 2010-2012 implementation plan of the European Sustainable Nuclear Industrial Initiative (ESNII), in the frame of the Sustainable Nuclear Energy Technology Platform (SNE TP), establishes a very tight time schedule for the start of construction of the European Gen IV prototypes; namely the construction of the LFR ETPP (European Technology Pilot Plant) Myrrha will start in 2014 and that of the SFR Prototype ASTRID will start in 2017. The GEN IV reactors pose new challenges to the designers and scientists in terms of higher operating temperature and higher irradiation damage of materials with respect to the present technologies. In this frame, the MATTER (MATerials TEsting and Rules) Project intends to start well targeted researches to perform careful studies of materials behaviors in GEN IV operational conditions and to find out criteria for the correct use of these materials in relevant reactor applications. In that context, the JRC has carried out different tests (LCF, Creep, Small Punch Creep, Small Punch Tensile/Fracture) tests on P91 and 316. The activities were carried out in the frame of the MATTER project (Grant agreement no: 269706).
DOI: 10.5290/2520004
title: Low cycle fatigue - strain control test data for AISI 316 L ar material at 600 °C (specimen identifier 316L-S9 test)

description: The data set contains strain controlled low cycle fatigue data with or without hold periods for austenitic stainless steel 316L and ferritic-martensitic steel P91. The total strain range for tests is from 0.5% to 1.0% and the temperature range is from 823K to 873K. The hold period length is from 0 to 1800 sec. For 316L the hold period is applied both in tension and compression for all tests, whereas for P91 data set includes tests with hold period only in tension, only in compression and both.
DOI: 10.5290/2500080
title: Uniaxial creep test data for P91 ar material at 375 °C and a stress of 415 MPa (specimen identifier MC-07)

description: The 2010-2012 implementation plan of the European Sustainable Nuclear Industrial Initiative (ESNII), in the frame of the Sustainable Nuclear Energy Technology Platform (SNE TP), establishes a very tight time schedule for the start of construction of the European Gen IV prototypes; namely the construction of the LFR ETPP (European Technology Pilot Plant) Myrrha will start in 2014 and that of the SFR Prototype ASTRID will start in 2017. The GEN IV reactors pose new challenges to the designers and scientists in terms of higher operating temperature and higher irradiation damage of materials with respect to the present technologies. In this frame, the MATTER (MATerials TEsting and Rules) Project intends to start well targeted researches to perform careful studies of materials behaviors in GEN IV operational conditions and to find out criteria for the correct use of these materials in relevant reactor applications. In that context, the JRC has carried out different tests (LCF, Creep, Small Punch Creep, Small Punch Tensile/Fracture) tests on P91 and 316. The activities were carried out in the frame of the MATTER project (Grant agreement no: 269706).
DOI: 10.5290/2500081
title: Uniaxial creep test data for P91 ar material at 600 °C and a stress of 155 MPa (specimen identifier AE001)

description: The 2010-2012 implementation plan of the European Sustainable Nuclear Industrial Initiative (ESNII), in the frame of the Sustainable Nuclear Energy Technology Platform (SNE TP), establishes a very tight time schedule for the start of construction of the European Gen IV prototypes; namely the construction of the LFR ETPP (European Technology Pilot Plant) Myrrha will start in 2014 and that of the SFR Prototype ASTRID will start in 2017. The GEN IV reactors pose new challenges to the designers and scientists in terms of higher operating temperature and higher irradiation damage of materials with respect to the present technologies. In this frame, the MATTER (MATerials TEsting and Rules) Project intends to start well targeted researches to perform careful studies of materials behaviors in GEN IV operational conditions and to find out criteria for the correct use of these materials in relevant reactor applications. In that context, the JRC has carried out different tests (LCF, Creep, Small Punch Creep, Small Punch Tensile/Fracture) tests on P91 and 316. The activities were carried out in the frame of the MATTER project (Grant agreement no: 269706).
DOI: 10.5290/2520005
title: Low cycle fatigue - strain control test data for AISI 316 L ar material at 600 °C (specimen identifier 316L-S5 test)

description: The data set contains strain controlled low cycle fatigue data with or without hold periods for austenitic stainless steel 316L and ferritic-martensitic steel P91. The total strain range for tests is from 0.5% to 1.0% and the temperature range is from 823K to 873K. The hold period length is from 0 to 1800 sec. For 316L the hold period is applied both in tension and compression for all tests, whereas for P91 data set includes tests with hold period only in tension, only in compression and both.
DOI: 10.5290/2520007
title: Low cycle fatigue - strain control test data for AISI 316 L ar material at 600 °C (specimen identifier 316L-S10 test)

description: The data set contains strain controlled low cycle fatigue data with or without hold periods for austenitic stainless steel 316L and ferritic-martensitic steel P91. The total strain range for tests is from 0.5% to 1.0% and the temperature range is from 823K to 873K. The hold period length is from 0 to 1800 sec. For 316L the hold period is applied both in tension and compression for all tests, whereas for P91 data set includes tests with hold period only in tension, only in compression and both.
DOI: 10.5290/2520008
title: Low cycle fatigue - strain control test data for AISI 316 L ar material at 600 °C (specimen identifier 316L-S11 test)

description: The data set contains strain controlled low cycle fatigue data with or without hold periods for austenitic stainless steel 316L and ferritic-martensitic steel P91. The total strain range for tests is from 0.5% to 1.0% and the temperature range is from 823K to 873K. The hold period length is from 0 to 1800 sec. For 316L the hold period is applied both in tension and compression for all tests, whereas for P91 data set includes tests with hold period only in tension, only in compression and both.
DOI: 10.5290/2520006
title: Low cycle fatigue - strain control test data for AISI 316 L ar material at 600 °C (specimen identifier 316L-S8 test)

description: The data set contains strain controlled low cycle fatigue data with or without hold periods for austenitic stainless steel 316L and ferritic-martensitic steel P91. The total strain range for tests is from 0.5% to 1.0% and the temperature range is from 823K to 873K. The hold period length is from 0 to 1800 sec. For 316L the hold period is applied both in tension and compression for all tests, whereas for P91 data set includes tests with hold period only in tension, only in compression and both.
DOI: 10.5290/2520009
title: Low cycle fatigue - strain control test data for AISI 316 L ar material at 600 °C (specimen identifier 316L-S1 test)

description: The data set contains strain controlled low cycle fatigue data with or without hold periods for austenitic stainless steel 316L and ferritic-martensitic steel P91. The total strain range for tests is from 0.5% to 1.0% and the temperature range is from 823K to 873K. The hold period length is from 0 to 1800 sec. For 316L the hold period is applied both in tension and compression for all tests, whereas for P91 data set includes tests with hold period only in tension, only in compression and both.
DOI: 10.5290/2520010
title: Low cycle fatigue - strain control test data for AISI 316 L ar material at 600 °C (specimen identifier 316L-S3 test)

description: The data set contains strain controlled low cycle fatigue data with or without hold periods for austenitic stainless steel 316L and ferritic-martensitic steel P91. The total strain range for tests is from 0.5% to 1.0% and the temperature range is from 823K to 873K. The hold period length is from 0 to 1800 sec. For 316L the hold period is applied both in tension and compression for all tests, whereas for P91 data set includes tests with hold period only in tension, only in compression and both.
DOI: 10.5290/2520011
title: Low cycle fatigue - strain control test data for AISI 316 L ar material at 600 °C (specimen identifier 316L-S4 test)

description: The data set contains strain controlled low cycle fatigue data with or without hold periods for austenitic stainless steel 316L and ferritic-martensitic steel P91. The total strain range for tests is from 0.5% to 1.0% and the temperature range is from 823K to 873K. The hold period length is from 0 to 1800 sec. For 316L the hold period is applied both in tension and compression for all tests, whereas for P91 data set includes tests with hold period only in tension, only in compression and both.
DOI: 10.5290/2520012
title: Low cycle fatigue - strain control test data for AISI 316 L ar material at 600 °C (specimen identifier 316L-S6 test)

description: The data set contains strain controlled low cycle fatigue data with or without hold periods for austenitic stainless steel 316L and ferritic-martensitic steel P91. The total strain range for tests is from 0.5% to 1.0% and the temperature range is from 823K to 873K. The hold period length is from 0 to 1800 sec. For 316L the hold period is applied both in tension and compression for all tests, whereas for P91 data set includes tests with hold period only in tension, only in compression and both.
DOI: 10.5290/2520028
title: Low cycle fatigue - strain control test data for P91 material at 600 °C (specimen identifier P91-S2)

description: The data set contains strain controlled low cycle fatigue data with or without hold periods for austenitic stainless steel 316L and ferritic-martensitic steel P91. The total strain range for tests is from 0.5% to 1.0% and the temperature range is from 823K to 873K. The hold period length is from 0 to 1800 sec. For 316L the hold period is applied both in tension and compression for all tests, whereas for P91 data set includes tests with hold period only in tension, only in compression and both.
DOI: 10.5290/2520013
title: Low cycle fatigue - strain control test data for AISI 316 L ar material at 600 °C (specimen identifier 316L-S12 test)

description: The data set contains strain controlled low cycle fatigue data with or without hold periods for austenitic stainless steel 316L and ferritic-martensitic steel P91. The total strain range for tests is from 0.5% to 1.0% and the temperature range is from 823K to 873K. The hold period length is from 0 to 1800 sec. For 316L the hold period is applied both in tension and compression for all tests, whereas for P91 data set includes tests with hold period only in tension, only in compression and both.
DOI: 10.5290/2520014
title: Low cycle fatigue - strain control test data for AISI 316 L ar material at 600 °C (specimen identifier 316L-S13 test)

description: The data set contains strain controlled low cycle fatigue data with or without hold periods for austenitic stainless steel 316L and ferritic-martensitic steel P91. The total strain range for tests is from 0.5% to 1.0% and the temperature range is from 823K to 873K. The hold period length is from 0 to 1800 sec. For 316L the hold period is applied both in tension and compression for all tests, whereas for P91 data set includes tests with hold period only in tension, only in compression and both.
DOI: 10.5290/2520031
title: Low cycle fatigue - strain control test data for P91 material at 600 °C (specimen identifier P91-S5)

description: The data set contains strain controlled low cycle fatigue data with or without hold periods for austenitic stainless steel 316L and ferritic-martensitic steel P91. The total strain range for tests is from 0.5% to 1.0% and the temperature range is from 823K to 873K. The hold period length is from 0 to 1800 sec. For 316L the hold period is applied both in tension and compression for all tests, whereas for P91 data set includes tests with hold period only in tension, only in compression and both.
DOI: 10.5290/2520029
title: Low cycle fatigue - strain control test data for P91 material at 600 °C (specimen identifier P91-S3)

description: The data set contains strain controlled low cycle fatigue data with or without hold periods for austenitic stainless steel 316L and ferritic-martensitic steel P91. The total strain range for tests is from 0.5% to 1.0% and the temperature range is from 823K to 873K. The hold period length is from 0 to 1800 sec. For 316L the hold period is applied both in tension and compression for all tests, whereas for P91 data set includes tests with hold period only in tension, only in compression and both.
DOI: 10.5290/2520032
title: Low cycle fatigue - strain control test data for P91 material at 600 °C (specimen identifier P91-S4)

description: The data set contains strain controlled low cycle fatigue data with or without hold periods for austenitic stainless steel 316L and ferritic-martensitic steel P91. The total strain range for tests is from 0.5% to 1.0% and the temperature range is from 823K to 873K. The hold period length is from 0 to 1800 sec. For 316L the hold period is applied both in tension and compression for all tests, whereas for P91 data set includes tests with hold period only in tension, only in compression and both.
DOI: 10.5290/2520033
title: Low cycle fatigue - strain control test data for P91 material at 550 °C (specimen identifier P91-S6)

description: The data set contains strain controlled low cycle fatigue data with or without hold periods for austenitic stainless steel 316L and ferritic-martensitic steel P91. The total strain range for tests is from 0.5% to 1.0% and the temperature range is from 823K to 873K. The hold period length is from 0 to 1800 sec. For 316L the hold period is applied both in tension and compression for all tests, whereas for P91 data set includes tests with hold period only in tension, only in compression and both.