cometadata/datacite-titles-descriptions-related-identifiers huggingface dataset:
DOI: 10.5290/1100503
title: Uniaxial tensile test data for P91 ar material at 22 °C

description: The European Energy Research Alliance, set-up under the European Strategic Energy Technology Plan, has launched an initiative for a Joint Programme on Nuclear Materials (JPNM). The JPNM aims at establishing key priorities in the area of advanced nuclear materials, identifying funding opportunities and harmonizing this scientific & technical domain at the European level by maximizing complementarities and synergies with the major actors of the field. The JPNM partners propose, through MatISSE, a combination of Collaborative Projects and Coordination and Support Actions to face the challenge of implementing a pan-European integrated research programme with common research activities establishing, at the same time, appropriate strategy and governance structure. Focusing on cross-cutting activities related to materials used in fuel and structural elements of safe and sustainable advanced nuclear systems, the project aims at covering the key priorities identified in the JPNM: pre-normative research in support of ESNII systems, Oxide Dispersed Strengthened steels, refractory composites for the high temperature applications, development of predictive capacities. MatISSE will foster the link between the respective national research programmes through networking and integrating activities on material innovations for advanced nuclear systems, sharing partners best practices and setting-up efficient communication tools. It is expected that, through MatISSE, a real boost toward Joint Programming among the Member States, the European Commission and the main European research actors, will be achieved.
DOI: 10.5290/1100507
title: Uniaxial tensile test data for AISI 316L ar material at 22 °C

description: The European Energy Research Alliance, set-up under the European Strategic Energy Technology Plan, has launched an initiative for a Joint Programme on Nuclear Materials (JPNM). The JPNM aims at establishing key priorities in the area of advanced nuclear materials, identifying funding opportunities and harmonizing this scientific & technical domain at the European level by maximizing complementarities and synergies with the major actors of the field. The JPNM partners propose, through MatISSE, a combination of Collaborative Projects and Coordination and Support Actions to face the challenge of implementing a pan-European integrated research programme with common research activities establishing, at the same time, appropriate strategy and governance structure. Focusing on cross-cutting activities related to materials used in fuel and structural elements of safe and sustainable advanced nuclear systems, the project aims at covering the key priorities identified in the JPNM: pre-normative research in support of ESNII systems, Oxide Dispersed Strengthened steels, refractory composites for the high temperature applications, development of predictive capacities. MatISSE will foster the link between the respective national research programmes through networking and integrating activities on material innovations for advanced nuclear systems, sharing partners best practices and setting-up efficient communication tools. It is expected that, through MatISSE, a real boost toward Joint Programming among the Member States, the European Commission and the main European research actors, will be achieved.
DOI: 10.5290/1100508
title: Uniaxial tensile test data for AISI 316L ar material at 22 °C

description: The European Energy Research Alliance, set-up under the European Strategic Energy Technology Plan, has launched an initiative for a Joint Programme on Nuclear Materials (JPNM). The JPNM aims at establishing key priorities in the area of advanced nuclear materials, identifying funding opportunities and harmonizing this scientific & technical domain at the European level by maximizing complementarities and synergies with the major actors of the field. The JPNM partners propose, through MatISSE, a combination of Collaborative Projects and Coordination and Support Actions to face the challenge of implementing a pan-European integrated research programme with common research activities establishing, at the same time, appropriate strategy and governance structure. Focusing on cross-cutting activities related to materials used in fuel and structural elements of safe and sustainable advanced nuclear systems, the project aims at covering the key priorities identified in the JPNM: pre-normative research in support of ESNII systems, Oxide Dispersed Strengthened steels, refractory composites for the high temperature applications, development of predictive capacities. MatISSE will foster the link between the respective national research programmes through networking and integrating activities on material innovations for advanced nuclear systems, sharing partners best practices and setting-up efficient communication tools. It is expected that, through MatISSE, a real boost toward Joint Programming among the Member States, the European Commission and the main European research actors, will be achieved.
DOI: 10.5290/1100509
title: Uniaxial tensile test data for AISI 316L ar material at 600 °C

description: The European Energy Research Alliance, set-up under the European Strategic Energy Technology Plan, has launched an initiative for a Joint Programme on Nuclear Materials (JPNM). The JPNM aims at establishing key priorities in the area of advanced nuclear materials, identifying funding opportunities and harmonizing this scientific & technical domain at the European level by maximizing complementarities and synergies with the major actors of the field. The JPNM partners propose, through MatISSE, a combination of Collaborative Projects and Coordination and Support Actions to face the challenge of implementing a pan-European integrated research programme with common research activities establishing, at the same time, appropriate strategy and governance structure. Focusing on cross-cutting activities related to materials used in fuel and structural elements of safe and sustainable advanced nuclear systems, the project aims at covering the key priorities identified in the JPNM: pre-normative research in support of ESNII systems, Oxide Dispersed Strengthened steels, refractory composites for the high temperature applications, development of predictive capacities. MatISSE will foster the link between the respective national research programmes through networking and integrating activities on material innovations for advanced nuclear systems, sharing partners best practices and setting-up efficient communication tools. It is expected that, through MatISSE, a real boost toward Joint Programming among the Member States, the European Commission and the main European research actors, will be achieved.
DOI: 10.5290/1210001
title: Nanoindentation (multi cycle) test data for Model Alloy (Fe) material at 25 °C

description: Data created at the NCBJ, Poland during the H2020 project on multiscale modeling for fusion and fission materials. The research leading to these results has been carried out in the frame of EERA Joint Program for Nuclear Materials and is funded from the Euratom research and training programme 2014-2018 under grant agreement No. 755039.
DOI: 10.5290/1210003
title: Nanoindentation (multi cycle) test data for Model Alloy (Fe) material at 25 °C (first nominally repeat test)

description: Data created at the NCBJ, Poland during the H2020 project on multiscale modeling for fusion and fission materials. The research leading to these results has been carried out in the frame of EERA Joint Program for Nuclear Materials and is funded from the Euratom research and training programme 2014-2018 under grant agreement No. 755039.
DOI: 10.5290/1210002
title: Nanoindentation (multi cycle) test data for Model Alloy (Fe) material at 25 °C (first nominally repeat test)

description: Data created at the NCBJ, Poland during the H2020 project on multiscale modeling for fusion and fission materials. The research leading to these results has been carried out in the frame of EERA Joint Program for Nuclear Materials and is funded from the Euratom research and training programme 2014-2018 under grant agreement No. 755039.
DOI: 10.5290/1210004
title: Nanoindentation (multi cycle) test data for Model Alloy (Fe) material at 25 °C (first nominally repeat test)

description: Data created at the NCBJ, Poland during the H2020 project on multiscale modeling for fusion and fission materials. The research leading to these results has been carried out in the frame of EERA Joint Program for Nuclear Materials and is funded from the Euratom research and training programme 2014-2018 under grant agreement No. 755039.
DOI: 10.5290/1210005
title: Nanoindentation (multi cycle) test data for Model Alloy (Fe) material at 25 °C (first nominally repeat test)

description: Data created at the NCBJ, Poland during the H2020 project on multiscale modeling for fusion and fission materials. The research leading to these results has been carried out in the frame of EERA Joint Program for Nuclear Materials and is funded from the Euratom research and training programme 2014-2018 under grant agreement No. 755039.
DOI: 10.5290/1210006
title: Nanoindentation (multi cycle) test data for Model Alloy (Fe) material at 25 °C (first nominally repeat test)

description: Data created at the NCBJ, Poland during the H2020 project on multiscale modeling for fusion and fission materials. The research leading to these results has been carried out in the frame of EERA Joint Program for Nuclear Materials and is funded from the Euratom research and training programme 2014-2018 under grant agreement No. 755039.
DOI: 10.5290/1210007
title: Nanoindentation (multi cycle) test data for Model Alloy (Fe) material at 25 °C (first nominally repeat test)

description: Data created at the NCBJ, Poland during the H2020 project on multiscale modeling for fusion and fission materials. The research leading to these results has been carried out in the frame of EERA Joint Program for Nuclear Materials and is funded from the Euratom research and training programme 2014-2018 under grant agreement No. 755039.
DOI: 10.5290/1210008
title: Nanoindentation (multi cycle) test data for Model Alloy (Fe) material at 25 °C (first nominally repeat test)

description: Data created at the NCBJ, Poland during the H2020 project on multiscale modeling for fusion and fission materials. The research leading to these results has been carried out in the frame of EERA Joint Program for Nuclear Materials and is funded from the Euratom research and training programme 2014-2018 under grant agreement No. 755039.
DOI: 10.5290/1210009
title: Nanoindentation (multi cycle) test data for Model Alloy (Fe) material at 25 °C (first nominally repeat test)

description: Data created at the NCBJ, Poland during the H2020 project on multiscale modeling for fusion and fission materials. The research leading to these results has been carried out in the frame of EERA Joint Program for Nuclear Materials and is funded from the Euratom research and training programme 2014-2018 under grant agreement No. 755039.
DOI: 10.5290/1210010
title: Nanoindentation (multi cycle) test data for Model Alloy (Fe) material at 25 °C (first nominally repeat test)

description: Data created at the NCBJ, Poland during the H2020 project on multiscale modeling for fusion and fission materials. The research leading to these results has been carried out in the frame of EERA Joint Program for Nuclear Materials and is funded from the Euratom research and training programme 2014-2018 under grant agreement No. 755039.
DOI: 10.5290/1210011
title: Nanoindentation (multi cycle) test data for Model Alloy (Fe) material at 25 °C (first nominally repeat test)

description: Data created at the NCBJ, Poland during the H2020 project on multiscale modeling for fusion and fission materials. The research leading to these results has been carried out in the frame of EERA Joint Program for Nuclear Materials and is funded from the Euratom research and training programme 2014-2018 under grant agreement No. 755039.
DOI: 10.5290/1210012
title: Nanoindentation (multi cycle) test data for Model Alloy (Fe) material at 25 °C (first nominally repeat test)

description: Data created at the NCBJ, Poland during the H2020 project on multiscale modeling for fusion and fission materials. The research leading to these results has been carried out in the frame of EERA Joint Program for Nuclear Materials and is funded from the Euratom research and training programme 2014-2018 under grant agreement No. 755039.
DOI: 10.5290/1210013
title: Nanoindentation (multi cycle) test data for Model Alloy (Fe) material at 25 °C (first nominally repeat test)

description: Data created at the NCBJ, Poland during the H2020 project on multiscale modeling for fusion and fission materials. The research leading to these results has been carried out in the frame of EERA Joint Program for Nuclear Materials and is funded from the Euratom research and training programme 2014-2018 under grant agreement No. 755039.
DOI: 10.5290/1210014
title: Nanoindentation (multi cycle) test data for Model Alloy (Fe) material at 25 °C (first nominally repeat test)

description: Data created at the NCBJ, Poland during the H2020 project on multiscale modeling for fusion and fission materials. The research leading to these results has been carried out in the frame of EERA Joint Program for Nuclear Materials and is funded from the Euratom research and training programme 2014-2018 under grant agreement No. 755039.
DOI: 10.5290/1210016
title: Nanoindentation (multi cycle) test data for Model Alloy (Fe) material at 25 °C (first nominally repeat test)

description: Data created at the NCBJ, Poland during the H2020 project on multiscale modeling for fusion and fission materials. The research leading to these results has been carried out in the frame of EERA Joint Program for Nuclear Materials and is funded from the Euratom research and training programme 2014-2018 under grant agreement No. 755039.
DOI: 10.5290/1210015
title: Nanoindentation (multi cycle) test data for Model Alloy (Fe) material at 25 °C (first nominally repeat test)

description: Data created at the NCBJ, Poland during the H2020 project on multiscale modeling for fusion and fission materials. The research leading to these results has been carried out in the frame of EERA Joint Program for Nuclear Materials and is funded from the Euratom research and training programme 2014-2018 under grant agreement No. 755039.
DOI: 10.5281/zenodo.5807375
title: InnoRate_Multi-component web-based survey_Dataset4_2021.12.28_v1

description: This dataset has been collected by deploying an online survey to gather insight and analyse the needs and preferences of potential users and stakeholders of the InnoRate Platform of the InnoRate Project (H2020 GA 821518). We have gathered responses from 3 main stakeholder groups, namely innovators, investors and innovation intermediaries. The surveys for each stakeholder group (.docx format), along with the respective anonymised version of their responses (.xlsx format) are uploaded on Zenodo.
DOI: 10.5281/zenodo.5807374
title: InnoRate_Multi-component web-based survey_Dataset4_2021.12.28_v1

description: This dataset has been collected by deploying an online survey to gather insight and analyse the needs and preferences of potential users and stakeholders of the InnoRate Platform of the InnoRate Project (H2020 GA 821518). We have gathered responses from 3 main stakeholder groups, namely innovators, investors and innovation intermediaries. The surveys for each stakeholder group (.docx format), along with the respective anonymised version of their responses (.xlsx format) are uploaded on Zenodo.
DOI: 10.5290/8400005
title: High cycle fatigue test data for IN 718 material at 20 °C

description: The FP7 project "In Space Propulsion 1" was set up to improve the fundamental knowledge and the techniques which are necessary to allow Europe to implement new ambitious space programs involving cryogenic propulsion. It concentrates on liquid oxygen, liquid hydrogen, and liquid methane propellants, and the anticipated progress will address - LOX methane combustion - heat and propellant management - materials tribology, compatibility, and hydrogen embrittlement. The data included here were generated in the part of the project relating to hydrogen embrittlement. In a frist step, materials of interest were screened through a literature research and by carrying out tensile tests in gaseous hydrogen (GH2) and Ar. Finally, two alloys (Inconel 718 and A-286) were selected as being the most interesting for the actual test campaign. For these two materials the influence of hydrogen on the fatigue behaviour in High Cycle Fatigue (HCF) tests was studied in high pressure GH2 and Argon.
DOI: 10.5290/8400006
title: High cycle fatigue test data for IN 718 material at 20 °C

description: The FP7 project "In Space Propulsion 1" was set up to improve the fundamental knowledge and the techniques which are necessary to allow Europe to implement new ambitious space programs involving cryogenic propulsion. It concentrates on liquid oxygen, liquid hydrogen, and liquid methane propellants, and the anticipated progress will address - LOX methane combustion - heat and propellant management - materials tribology, compatibility, and hydrogen embrittlement. The data included here were generated in the part of the project relating to hydrogen embrittlement. In a frist step, materials of interest were screened through a literature research and by carrying out tensile tests in gaseous hydrogen (GH2) and Ar. Finally, two alloys (Inconel 718 and A-286) were selected as being the most interesting for the actual test campaign. For these two materials the influence of hydrogen on the fatigue behaviour in High Cycle Fatigue (HCF) tests was studied in high pressure GH2 and Argon.
DOI: 10.5290/8400004
title: High cycle fatigue test data for IN 718 material at 20 °C

description: The FP7 project "In Space Propulsion 1" was set up to improve the fundamental knowledge and the techniques which are necessary to allow Europe to implement new ambitious space programs involving cryogenic propulsion. It concentrates on liquid oxygen, liquid hydrogen, and liquid methane propellants, and the anticipated progress will address - LOX methane combustion - heat and propellant management - materials tribology, compatibility, and hydrogen embrittlement. The data included here were generated in the part of the project relating to hydrogen embrittlement. In a frist step, materials of interest were screened through a literature research and by carrying out tensile tests in gaseous hydrogen (GH2) and Ar. Finally, two alloys (Inconel 718 and A-286) were selected as being the most interesting for the actual test campaign. For these two materials the influence of hydrogen on the fatigue behaviour in High Cycle Fatigue (HCF) tests was studied in high pressure GH2 and Argon.
DOI: 10.5290/8400007
title: High cycle fatigue test data for IN 718 material at 20 °C

description: The FP7 project "In Space Propulsion 1" was set up to improve the fundamental knowledge and the techniques which are necessary to allow Europe to implement new ambitious space programs involving cryogenic propulsion. It concentrates on liquid oxygen, liquid hydrogen, and liquid methane propellants, and the anticipated progress will address - LOX methane combustion - heat and propellant management - materials tribology, compatibility, and hydrogen embrittlement. The data included here were generated in the part of the project relating to hydrogen embrittlement. In a frist step, materials of interest were screened through a literature research and by carrying out tensile tests in gaseous hydrogen (GH2) and Ar. Finally, two alloys (Inconel 718 and A-286) were selected as being the most interesting for the actual test campaign. For these two materials the influence of hydrogen on the fatigue behaviour in High Cycle Fatigue (HCF) tests was studied in high pressure GH2 and Argon.
DOI: 10.5290/8400008
title: High cycle fatigue test data for IN 718 material at 20 °C

description: The FP7 project "In Space Propulsion 1" was set up to improve the fundamental knowledge and the techniques which are necessary to allow Europe to implement new ambitious space programs involving cryogenic propulsion. It concentrates on liquid oxygen, liquid hydrogen, and liquid methane propellants, and the anticipated progress will address - LOX methane combustion - heat and propellant management - materials tribology, compatibility, and hydrogen embrittlement. The data included here were generated in the part of the project relating to hydrogen embrittlement. In a frist step, materials of interest were screened through a literature research and by carrying out tensile tests in gaseous hydrogen (GH2) and Ar. Finally, two alloys (Inconel 718 and A-286) were selected as being the most interesting for the actual test campaign. For these two materials the influence of hydrogen on the fatigue behaviour in High Cycle Fatigue (HCF) tests was studied in high pressure GH2 and Argon.
DOI: 10.5290/8400009
title: High cycle fatigue test data for IN 718 material at 20 °C

description: The FP7 project "In Space Propulsion 1" was set up to improve the fundamental knowledge and the techniques which are necessary to allow Europe to implement new ambitious space programs involving cryogenic propulsion. It concentrates on liquid oxygen, liquid hydrogen, and liquid methane propellants, and the anticipated progress will address - LOX methane combustion - heat and propellant management - materials tribology, compatibility, and hydrogen embrittlement. The data included here were generated in the part of the project relating to hydrogen embrittlement. In a frist step, materials of interest were screened through a literature research and by carrying out tensile tests in gaseous hydrogen (GH2) and Ar. Finally, two alloys (Inconel 718 and A-286) were selected as being the most interesting for the actual test campaign. For these two materials the influence of hydrogen on the fatigue behaviour in High Cycle Fatigue (HCF) tests was studied in high pressure GH2 and Argon.
DOI: 10.5290/8400010
title: High cycle fatigue test data for IN 718 material at 20 °C

description: The FP7 project "In Space Propulsion 1" was set up to improve the fundamental knowledge and the techniques which are necessary to allow Europe to implement new ambitious space programs involving cryogenic propulsion. It concentrates on liquid oxygen, liquid hydrogen, and liquid methane propellants, and the anticipated progress will address - LOX methane combustion - heat and propellant management - materials tribology, compatibility, and hydrogen embrittlement. The data included here were generated in the part of the project relating to hydrogen embrittlement. In a frist step, materials of interest were screened through a literature research and by carrying out tensile tests in gaseous hydrogen (GH2) and Ar. Finally, two alloys (Inconel 718 and A-286) were selected as being the most interesting for the actual test campaign. For these two materials the influence of hydrogen on the fatigue behaviour in High Cycle Fatigue (HCF) tests was studied in high pressure GH2 and Argon.