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 degrees 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.

Pilloni, L., Cristalli, C., Tassa, O., Bozzetto, L., Zanin, E., Bettocchi, N. (2019). Development of innovative materials and thermal treatments for DEMO water cooled blanket. NUCLEAR MATERIALS AND ENERGY, 19, 79-86 [10.1016/j.nme.2019.01.026].

Development of innovative materials and thermal treatments for DEMO water cooled blanket

Cristalli, C.;
2019

Abstract

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 degrees 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.
2019
Pilloni, L., Cristalli, C., Tassa, O., Bozzetto, L., Zanin, E., Bettocchi, N. (2019). Development of innovative materials and thermal treatments for DEMO water cooled blanket. NUCLEAR MATERIALS AND ENERGY, 19, 79-86 [10.1016/j.nme.2019.01.026].
Pilloni, L.; Cristalli, C.; Tassa, O.; Bozzetto, L.; Zanin, E.; Bettocchi, N.
File in questo prodotto:
File Dimensione Formato  
1-s2.0-S2352179117301230-main.pdf

accesso aperto

Tipo: Versione (PDF) editoriale
Licenza: Creative commons
Dimensione 6 MB
Formato Adobe PDF
6 MB Adobe PDF Visualizza/Apri

I documenti in IRIS sono protetti da copyright e tutti i diritti sono riservati, salvo diversa indicazione.

Utilizza questo identificativo per citare o creare un link a questo documento: https://hdl.handle.net/11585/753991
Citazioni
  • ???jsp.display-item.citation.pmc??? ND
  • Scopus 11
  • ???jsp.display-item.citation.isi??? 9
social impact