| About this Abstract |
| Meeting |
Materials in Nuclear Energy Systems (MiNES) 2021
|
| Symposium
|
Materials in Nuclear Energy Systems (MiNES) 2021
|
| Presentation Title |
The Subtle Effects of Nitrogen on Radiation Effects in Tempered Martensitic Steels |
| Author(s) |
Stuart Andrew Maloy, B Eftink, H Kim, C Rietema, E Aydogan, H Vo |
| On-Site Speaker (Planned) |
Stuart Andrew Maloy |
| Abstract Scope |
The Nuclear Technology R&D program is investigating options to transmute minor actinides. To achieve this goal, new fuels and cladding materials must be developed and tested to high burnup levels (e.g. >20%) requiring cladding to withstand very high doses (greater than 200 dpa) while in contact with the coolant and the fuel. Tempered Martensitic Alloys are the leading candidates for these extreme service conditions. Recent irradiations on tempered martensitic alloys show that slight variations in the composition of one tempered martensitic alloy, HT9, can improve resistance to low temperature embrittlement. This material maintained 5% uniform elongation after irradiation to 6 dpa at 290C while all other alloys exhibited less than 2% uniform elongation. To investigate the reasons behind these significant improvements, controlled alloys were produced while systematically varying the nitrogen concentration between 10 and 500 wppm nitrogen. Ion irradiations performed on these alloys showed that model alloys with higher nitrogen show a higher loop density while heats of HT9 with controlled nitrogen content show lower overall void swelling and a higher density of fine G-phase precipitates.
These results will be summarized along with their correlations with radiation effects in tempered martensitic steels. |
| Proceedings Inclusion? |
Undecided |