Swelling and He-Embrittlement of Austenitic Stainless Steels and Ni-Alloys in Nuclear Reactors
Rate theory models have been developed for the swelling and He-embrittlement of austenitic stainless steels and Ni-alloys in nuclear reactors. The models illustrate how microstructure evolution during irradiation affects the rate of change of mechanical properties and the dimensional stability. He-s...
| Main Authors: | , , |
|---|---|
| Format: | Article |
| Language: | English |
| Published: |
MDPI AG
2022-10-01
|
| Series: | Metals |
| Subjects: | |
| Online Access: | https://www.mdpi.com/2075-4701/12/10/1692 |
| _version_ | 1797471374019657728 |
|---|---|
| author | Malcolm Griffiths Steven Xu Juan Eduardo Ramos Nervi |
| author_facet | Malcolm Griffiths Steven Xu Juan Eduardo Ramos Nervi |
| author_sort | Malcolm Griffiths |
| collection | DOAJ |
| description | Rate theory models have been developed for the swelling and He-embrittlement of austenitic stainless steels and Ni-alloys in nuclear reactors. The models illustrate how microstructure evolution during irradiation affects the rate of change of mechanical properties and the dimensional stability. He-stabilised cavity accumulation on grain boundaries, which causes brittle failure at low stresses and strains known as He-embrittlement, is shown to be strongly dependent on the irradiation temperature and the rate of production of Frenkel pairs and He atoms. The results show that the accumulation of cavities on grain boundaries falls into two regimes: (i) that dictated by matrix bubble swelling at low temperatures; and (ii) that dictated by matrix void swelling at high temperatures. |
| first_indexed | 2024-03-09T19:47:33Z |
| format | Article |
| id | doaj.art-abc3ce0fee254f2abeb4a2d894a72bc7 |
| institution | Directory Open Access Journal |
| issn | 2075-4701 |
| language | English |
| last_indexed | 2024-03-09T19:47:33Z |
| publishDate | 2022-10-01 |
| publisher | MDPI AG |
| record_format | Article |
| series | Metals |
| spelling | doaj.art-abc3ce0fee254f2abeb4a2d894a72bc72023-11-24T01:19:12ZengMDPI AGMetals2075-47012022-10-011210169210.3390/met12101692Swelling and He-Embrittlement of Austenitic Stainless Steels and Ni-Alloys in Nuclear ReactorsMalcolm Griffiths0Steven Xu1Juan Eduardo Ramos Nervi2Department of Mechanical and Materials Engineering, Queen’s University, Kingston, ON K7L3N6, CanadaKinectrics Inc., Toronto, ON M8Z 5G5, CanadaDivisión de Materiales y Micromecánica, Gerencia de Ingeniería, Nucleoeléctrica Argentina S.A., Francisco N. Laprida 3163, Villa Martelli B1603AAA, ArgentinaRate theory models have been developed for the swelling and He-embrittlement of austenitic stainless steels and Ni-alloys in nuclear reactors. The models illustrate how microstructure evolution during irradiation affects the rate of change of mechanical properties and the dimensional stability. He-stabilised cavity accumulation on grain boundaries, which causes brittle failure at low stresses and strains known as He-embrittlement, is shown to be strongly dependent on the irradiation temperature and the rate of production of Frenkel pairs and He atoms. The results show that the accumulation of cavities on grain boundaries falls into two regimes: (i) that dictated by matrix bubble swelling at low temperatures; and (ii) that dictated by matrix void swelling at high temperatures.https://www.mdpi.com/2075-4701/12/10/1692austenitic stainless steelNi-alloyshe-embrittlementfractureneutronsradiation damage |
| spellingShingle | Malcolm Griffiths Steven Xu Juan Eduardo Ramos Nervi Swelling and He-Embrittlement of Austenitic Stainless Steels and Ni-Alloys in Nuclear Reactors Metals austenitic stainless steel Ni-alloys he-embrittlement fracture neutrons radiation damage |
| title | Swelling and He-Embrittlement of Austenitic Stainless Steels and Ni-Alloys in Nuclear Reactors |
| title_full | Swelling and He-Embrittlement of Austenitic Stainless Steels and Ni-Alloys in Nuclear Reactors |
| title_fullStr | Swelling and He-Embrittlement of Austenitic Stainless Steels and Ni-Alloys in Nuclear Reactors |
| title_full_unstemmed | Swelling and He-Embrittlement of Austenitic Stainless Steels and Ni-Alloys in Nuclear Reactors |
| title_short | Swelling and He-Embrittlement of Austenitic Stainless Steels and Ni-Alloys in Nuclear Reactors |
| title_sort | swelling and he embrittlement of austenitic stainless steels and ni alloys in nuclear reactors |
| topic | austenitic stainless steel Ni-alloys he-embrittlement fracture neutrons radiation damage |
| url | https://www.mdpi.com/2075-4701/12/10/1692 |
| work_keys_str_mv | AT malcolmgriffiths swellingandheembrittlementofausteniticstainlesssteelsandnialloysinnuclearreactors AT stevenxu swellingandheembrittlementofausteniticstainlesssteelsandnialloysinnuclearreactors AT juaneduardoramosnervi swellingandheembrittlementofausteniticstainlesssteelsandnialloysinnuclearreactors |