Abstract
Austenitic stainless steels are extensively used in reactor component technology for both fission and fusion reactor systems. Although well characterized from many aspects, their fracture behavior upon irradiation is often poorly characterized. Literature data show that the most drastic changes resulting
from irradiation damage are located in the low dose range, typically below 5 dpa. On the other hand, the experimental data scatter is large because of the variety of materials, their irradiation and their testing conditions. In the present work, the focus is on the range between 0 and 1 dpa where data are missing. We irradiated the SA 316L stainless steel in the high flux BR2 reactor at about 290°C to different neutron dose levels ranging from 0 to less than about 1 dpa. Tensile and precracked Charpy specimens were tested before and after irradiation at room and irradiation temperature. The test results are critically analyzed to provide better understanding of irradiation effects on the flow and fracture properties of austenitic stainless steels.
from irradiation damage are located in the low dose range, typically below 5 dpa. On the other hand, the experimental data scatter is large because of the variety of materials, their irradiation and their testing conditions. In the present work, the focus is on the range between 0 and 1 dpa where data are missing. We irradiated the SA 316L stainless steel in the high flux BR2 reactor at about 290°C to different neutron dose levels ranging from 0 to less than about 1 dpa. Tensile and precracked Charpy specimens were tested before and after irradiation at room and irradiation temperature. The test results are critically analyzed to provide better understanding of irradiation effects on the flow and fracture properties of austenitic stainless steels.
Original language | English |
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Title of host publication | International Symposium Contribution of Materials Investigations and Operating Experience to LWRs’ Safety, Performance and Reliability |
Subtitle of host publication | Fontevraud-10 |
Pages | 1-14 |
Number of pages | 14 |
Edition | 2022 |
State | Accepted/In press - 5 Oct 2022 |
Event | 2022 - FONTEVRAUD 10: Contribution of Materials Investigations and Operating Experience to LWRs’ Safety, Performance and Reliability - Palais des Papes, Avignon Duration: 19 Sep 2022 → 22 Sep 2022 https://www.sfen.org/evenement/fontevraud-10/ |
Conference
Conference | 2022 - FONTEVRAUD 10 |
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Abbreviated title | Fontevraud 10 |
Country/Territory | France |
City | Avignon |
Period | 2022-09-19 → 2022-09-22 |
Internet address |