Full metadata record
DC Field | Value | Language |
---|---|---|
dc.contributor.author | 김선진 | - |
dc.date.accessioned | 2019-11-26T01:27:41Z | - |
dc.date.available | 2019-11-26T01:27:41Z | - |
dc.date.issued | 2017-06 | - |
dc.identifier.citation | NUCLEAR ENGINEERING AND TECHNOLOGY, v. 49, no. 4, page. 752-759 | en_US |
dc.identifier.issn | 1738-5733 | - |
dc.identifier.uri | https://www.sciencedirect.com/science/article/pii/S1738573317300967?via%3Dihub | - |
dc.identifier.uri | https://repository.hanyang.ac.kr/handle/20.500.11754/114395 | - |
dc.description.abstract | The fatigue crack growth behavior of Type 347 (S347) and Type 347N (S347N) stainless steel was evaluated under the operating conditions of a pressurized water reactor (PWR). These two materials showed different fatigue crack growth rates (FCGRs) according to the changes in dissolved oxygen content and frequency. Under the simulated PWR conditions for normal operation, the FCGR of S347N was lower than that of S347 and insensitive to the changes in PWR water conditions. The higher yield strength and better corrosion resistance of the nitrogen-alloyed Type 347 stainless steel might be a main cause of slower FCGR and more stable properties against changes in environmental conditions. (C) 2017 Korean Nuclear Society, Published by Elsevier Korea LLC. | en_US |
dc.description.sponsorship | This work was supported by grant No. NRF-2017M2A8A4015156 funded by the Korean government (MSIP). | en_US |
dc.language.iso | en_US | en_US |
dc.publisher | KOREAN NUCLEAR SOC | en_US |
dc.subject | Dissolved Oxygen | en_US |
dc.subject | Environmental fatigue | en_US |
dc.subject | Fatigue Crack Growth Rate | en_US |
dc.subject | Pressurized Water Reactor Environment | en_US |
dc.subject | Type 347 Stainless Steel | en_US |
dc.title | Fatigue crack growth characteristics of nitrogen-alloyed type 347 stainless steel under operating conditions of a pressurized water reactor | en_US |
dc.type | Article | en_US |
dc.relation.no | 4 | - |
dc.relation.volume | 49 | - |
dc.identifier.doi | 10.1016/j.net.2017.01.019 | - |
dc.relation.page | 752-759 | - |
dc.relation.journal | NUCLEAR ENGINEERING AND TECHNOLOGY | - |
dc.contributor.googleauthor | Min, Ki-Deuk | - |
dc.contributor.googleauthor | Hong, Seokmin | - |
dc.contributor.googleauthor | Kim, Dae-Whan | - |
dc.contributor.googleauthor | Lee, Bong-Sang | - |
dc.contributor.googleauthor | Kim, Seon-Jin | - |
dc.relation.code | 2017011088 | - |
dc.sector.campus | S | - |
dc.sector.daehak | COLLEGE OF ENGINEERING[S] | - |
dc.sector.department | DIVISION OF MATERIALS SCIENCE AND ENGINEERING | - |
dc.identifier.pid | alloylab | - |
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