IRRADIATION EFFECTS OF HT-9 MARTENSITIC STEEL
High-Cr martensitic steel HT-9 is one of the candidate materials for advanced nuclear energy systems. Thanks to its excellent thermal conductivity and irradiation resistance, ferritic/martensitic steels such as HT-9 are considered for in-core applications of advanced nuclear reactors. The harsh neut...
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| Format: | Article |
| Language: | English |
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Elsevier
2013-06-01
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| Series: | Nuclear Engineering and Technology |
| Subjects: | |
| Online Access: | http://www.sciencedirect.com/science/article/pii/S1738573315300176 |
| _version_ | 1819208012635570176 |
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| author | YIREN CHEN |
| author_facet | YIREN CHEN |
| author_sort | YIREN CHEN |
| collection | DOAJ |
| description | High-Cr martensitic steel HT-9 is one of the candidate materials for advanced nuclear energy systems. Thanks to its excellent thermal conductivity and irradiation resistance, ferritic/martensitic steels such as HT-9 are considered for in-core applications of advanced nuclear reactors. The harsh neutron irradiation environments at the reactor core region pose a unique challenge for structural and cladding materials. Microstructural and microchemical changes resulting from displacement damage are anticipated for structural materials after prolonged neutron exposure. Consequently, various irradiation effects on the service performance of in-core materials need to be understood. In this work, the fundamentals of radiation damage and irradiation effects of the HT-9 martensitic steel are reviewed. The objective of this paper is to provide a background introduction of displacement damage, microstructural evolution, and subsequent effects on mechanical properties of the HT-9 martensitic steel under neutron irradiations. Mechanical test results of the irradiated HT-9 steel obtained from previous fast reactor and fusion programs are summarized along with the information of irradiated microstructure. This review can serve as a starting point for additional investigations on the in-core applications of ferritic/martensitic steels in advanced nuclear reactors. |
| first_indexed | 2024-12-23T05:32:37Z |
| format | Article |
| id | doaj.art-f6eb630d92014786970db34167bbd2b5 |
| institution | Directory Open Access Journal |
| issn | 1738-5733 |
| language | English |
| last_indexed | 2024-12-23T05:32:37Z |
| publishDate | 2013-06-01 |
| publisher | Elsevier |
| record_format | Article |
| series | Nuclear Engineering and Technology |
| spelling | doaj.art-f6eb630d92014786970db34167bbd2b52022-12-21T17:58:26ZengElsevierNuclear Engineering and Technology1738-57332013-06-0145331132210.5516/NET.07.2013.706IRRADIATION EFFECTS OF HT-9 MARTENSITIC STEELYIREN CHENHigh-Cr martensitic steel HT-9 is one of the candidate materials for advanced nuclear energy systems. Thanks to its excellent thermal conductivity and irradiation resistance, ferritic/martensitic steels such as HT-9 are considered for in-core applications of advanced nuclear reactors. The harsh neutron irradiation environments at the reactor core region pose a unique challenge for structural and cladding materials. Microstructural and microchemical changes resulting from displacement damage are anticipated for structural materials after prolonged neutron exposure. Consequently, various irradiation effects on the service performance of in-core materials need to be understood. In this work, the fundamentals of radiation damage and irradiation effects of the HT-9 martensitic steel are reviewed. The objective of this paper is to provide a background introduction of displacement damage, microstructural evolution, and subsequent effects on mechanical properties of the HT-9 martensitic steel under neutron irradiations. Mechanical test results of the irradiated HT-9 steel obtained from previous fast reactor and fusion programs are summarized along with the information of irradiated microstructure. This review can serve as a starting point for additional investigations on the in-core applications of ferritic/martensitic steels in advanced nuclear reactors.http://www.sciencedirect.com/science/article/pii/S1738573315300176High-Cr Martenistic steelsHT-9Irradiation EffectsRadiation DamageIrradiation Embrittlement |
| spellingShingle | YIREN CHEN IRRADIATION EFFECTS OF HT-9 MARTENSITIC STEEL Nuclear Engineering and Technology High-Cr Martenistic steels HT-9 Irradiation Effects Radiation Damage Irradiation Embrittlement |
| title | IRRADIATION EFFECTS OF HT-9 MARTENSITIC STEEL |
| title_full | IRRADIATION EFFECTS OF HT-9 MARTENSITIC STEEL |
| title_fullStr | IRRADIATION EFFECTS OF HT-9 MARTENSITIC STEEL |
| title_full_unstemmed | IRRADIATION EFFECTS OF HT-9 MARTENSITIC STEEL |
| title_short | IRRADIATION EFFECTS OF HT-9 MARTENSITIC STEEL |
| title_sort | irradiation effects of ht 9 martensitic steel |
| topic | High-Cr Martenistic steels HT-9 Irradiation Effects Radiation Damage Irradiation Embrittlement |
| url | http://www.sciencedirect.com/science/article/pii/S1738573315300176 |
| work_keys_str_mv | AT yirenchen irradiationeffectsofht9martensiticsteel |