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Synopsis
The high temperature gas-cooled reactor (HTGR) has been selected for the Next Generation Nuclear Plant (NGNP) project. The structural materials of HTGR will serve in the temperature range of 760-950oC and withstand coolant pressure up to 7 MPa for a design life of 60 years. Currently, Ni-based Inconel 617 (Alloy 617) and Haynes 230 (Alloy 230) are considered to be the leading metallic candidate materials for applications in the HTGR due to their favorable mechanical properties at high temperatures. In the present study, focus is placed on the biaxial, long term, high temperature creep behavior for Alloy 617 and Alloy 230.
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About the Author
Wei Lv, studied Nuclear, Plasma and Radiological Engineering at University of Illinois at Urbana-Champaign for master's degree, US, 2011-2013. Nuclear Engineering at Xian Jiaotong University for bachelor's degree, China, 2005-2009
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- PublisherLAP LAMBERT Academic Publishing
- Publication date2013
- ISBN 10 3659481718
- ISBN 13 9783659481710
- BindingPaperback
- LanguageEnglish
- Number of pages64
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High Temperature Creep Behavior Of Inconel 617 And Haynes 230
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LAP LAMBERT Academic Publishing Okt 2013, 2013
ISBN 10: 3659481718
ISBN 13: 9783659481710
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Seller: BuchWeltWeit Ludwig Meier e.K., Bergisch Gladbach, Germany
Seller rating 5 out of 5 stars
Taschenbuch. Condition: Neu. This item is printed on demand - it takes 3-4 days longer - Neuware -The high temperature gas-cooled reactor (HTGR) has been selected for the Next Generation Nuclear Plant (NGNP) project. The structural materials of HTGR will serve in the temperature range of 760-950oC and withstand coolant pressure up to 7 MPa for a design life of 60 years. Currently, Ni-based Inconel 617 (Alloy 617) and Haynes 230 (Alloy 230) are considered to be the leading metallic candidate materials for applications in the HTGR due to their favorable mechanical properties at high temperatures. In the present study, focus is placed on the biaxial, long term, high temperature creep behavior for Alloy 617 and Alloy 230. 64 pp. Englisch. Seller Inventory # 9783659481710
Quantity: 2 available
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High Temperature Creep Behavior Of Inconel 617 And Haynes 230
Published by
LAP LAMBERT Academic Publishing, 2013
ISBN 10: 3659481718
ISBN 13: 9783659481710
New
Taschenbuch
Seller: AHA-BUCH GmbH, Einbeck, Germany
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Taschenbuch. Condition: Neu. nach der Bestellung gedruckt Neuware - Printed after ordering - The high temperature gas-cooled reactor (HTGR) has been selected for the Next Generation Nuclear Plant (NGNP) project. The structural materials of HTGR will serve in the temperature range of 760-950oC and withstand coolant pressure up to 7 MPa for a design life of 60 years. Currently, Ni-based Inconel 617 (Alloy 617) and Haynes 230 (Alloy 230) are considered to be the leading metallic candidate materials for applications in the HTGR due to their favorable mechanical properties at high temperatures. In the present study, focus is placed on the biaxial, long term, high temperature creep behavior for Alloy 617 and Alloy 230. Seller Inventory # 9783659481710
Quantity: 1 available
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High Temperature Creep Behavior Of Inconel 617 And Haynes 230
Published by
LAP LAMBERT Academic Publishing, 2013
ISBN 10: 3659481718
ISBN 13: 9783659481710
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Condition: New. Dieser Artikel ist ein Print on Demand Artikel und wird nach Ihrer Bestellung fuer Sie gedruckt. Autor/Autorin: Lv WeiWei Lv, studied Nuclear, Plasma and Radiological Engineering at University of Illinois at Urbana-Champaign for master s degree, US, 2011-2013. Nuclear Engineering at Xian Jiaotong University for bachelor s degree, China, 2005-2. Seller Inventory # 5158815
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High Temperature Creep Behavior Of Inconel 617 And Haynes 230
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LAP LAMBERT Academic Publishing, 2013
ISBN 10: 3659481718
ISBN 13: 9783659481710
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