Development of innovative materials and thermal treatments for DEMO water cooled blanket
One of the options currently taken into account for the realization of the first DEMO reactor is the “water-cooled lanket”. This option implies an irradiation temperature for the blanket material in the range of 280–350 °C. Therefore, in light of the under irradiation behaviour of EUROFER, namely of...
| Main Authors: | , , , , , |
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| Format: | Article |
| Language: | English |
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Elsevier
2019-05-01
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| Series: | Nuclear Materials and Energy |
| Online Access: | http://www.sciencedirect.com/science/article/pii/S2352179117301230 |
| _version_ | 1818411441779113984 |
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| author | L. Pilloni C. Cristalli O. Tassa L. Bozzetto E. Zanin N. Bettocchi |
| author_facet | L. Pilloni C. Cristalli O. Tassa L. Bozzetto E. Zanin N. Bettocchi |
| author_sort | L. Pilloni |
| collection | DOAJ |
| description | One of the options currently taken into account for the realization of the first DEMO reactor is the “water-cooled lanket”. This option implies an irradiation temperature for the blanket material in the range of 280–350 °C. Therefore, in light of the under irradiation behaviour of EUROFER, namely of the DBTT shift toward high temperature due to the low irradiation temperature embrittlement, the target of the hereby reported activities is the development of much tougher alloys, to try to tolerate the embrittlement due to the low irradiation temperature. We report in this paper the work done to optimize the toughness of Eurofer 97, increasing the normalizing temperature and maintaining a small grain size using multiple normalizing treatments. We report also the mechanical behaviour of two 9Cr1WTa type alloys, produced and tested with the same aim to find alloys more resistant to embrittlement at low irradiation temperature. Keywords: EUROFER 97, RAFM steels, Microstructure, Heat treatment, Tensile, Charpy, KLST |
| first_indexed | 2024-12-14T10:31:28Z |
| format | Article |
| id | doaj.art-ef0bfc870818445eb11a49fde42d16ae |
| institution | Directory Open Access Journal |
| issn | 2352-1791 |
| language | English |
| last_indexed | 2024-12-14T10:31:28Z |
| publishDate | 2019-05-01 |
| publisher | Elsevier |
| record_format | Article |
| series | Nuclear Materials and Energy |
| spelling | doaj.art-ef0bfc870818445eb11a49fde42d16ae2022-12-21T23:06:07ZengElsevierNuclear Materials and Energy2352-17912019-05-01197986Development of innovative materials and thermal treatments for DEMO water cooled blanketL. Pilloni0C. Cristalli1O. Tassa2L. Bozzetto3E. Zanin4N. Bettocchi5ENEA, Casaccia, Via Anguillarese 301 00123 S. Maria di Galeria Roma; Corresponding author.ENEA, Brasimone 40032, Camugnano (BO), ItalyCSM, Via di Castel Romano 100, 00128, Rome ItalyCSM, Via di Castel Romano 100, 00128, Rome ItalyCSM, Via di Castel Romano 100, 00128, Rome ItalyENEA, Brasimone 40032, Camugnano (BO), ItalyOne of the options currently taken into account for the realization of the first DEMO reactor is the “water-cooled lanket”. This option implies an irradiation temperature for the blanket material in the range of 280–350 °C. Therefore, in light of the under irradiation behaviour of EUROFER, namely of the DBTT shift toward high temperature due to the low irradiation temperature embrittlement, the target of the hereby reported activities is the development of much tougher alloys, to try to tolerate the embrittlement due to the low irradiation temperature. We report in this paper the work done to optimize the toughness of Eurofer 97, increasing the normalizing temperature and maintaining a small grain size using multiple normalizing treatments. We report also the mechanical behaviour of two 9Cr1WTa type alloys, produced and tested with the same aim to find alloys more resistant to embrittlement at low irradiation temperature. Keywords: EUROFER 97, RAFM steels, Microstructure, Heat treatment, Tensile, Charpy, KLSThttp://www.sciencedirect.com/science/article/pii/S2352179117301230 |
| spellingShingle | L. Pilloni C. Cristalli O. Tassa L. Bozzetto E. Zanin N. Bettocchi Development of innovative materials and thermal treatments for DEMO water cooled blanket Nuclear Materials and Energy |
| title | Development of innovative materials and thermal treatments for DEMO water cooled blanket |
| title_full | Development of innovative materials and thermal treatments for DEMO water cooled blanket |
| title_fullStr | Development of innovative materials and thermal treatments for DEMO water cooled blanket |
| title_full_unstemmed | Development of innovative materials and thermal treatments for DEMO water cooled blanket |
| title_short | Development of innovative materials and thermal treatments for DEMO water cooled blanket |
| title_sort | development of innovative materials and thermal treatments for demo water cooled blanket |
| url | http://www.sciencedirect.com/science/article/pii/S2352179117301230 |
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