Preliminary consideration of alloys 617 and 230 for generation IV nuclear reactor applications

Weiju Ren; Robert Swlmdeman

doi:10.1115/PVP2007-26091

Preliminary consideration of alloys 617 and 230 for generation IV nuclear reactor applications

Weiju Ren, Robert Swlmdeman

Advanced Nuclear Materials

Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review

8 Scopus citations

Abstract

Alloys 617 and 230 are currently identified as two leading candidate metallic materials in the down selection for applications at temperatures above 760°C in the Gen IV Nuclear Reactor Systems. Qualifying the materials requires significant information related to Codification, mechanical behavior modeling, metallurgical stability, environmental resistance, and many other aspects. In the present paper, material requirements for the Gen IV Nuclear Reactor Systems are discussed; certain available information regarding the two alloys under consideration for the intended applications are reviewed and analyzed. Suggestions are presented for further R&D activities for the materials selection.

Original language	English
Title of host publication	2007 Proceedings of the ASME Pressure Vessels and Piping Conference - Materials and Fabrication
Pages	371-384
Number of pages	14
DOIs	https://doi.org/10.1115/PVP2007-26091
State	Published - 2008
Event	2007 ASME Pressure Vessels and Piping Conference, PVP 2007 - San Antonio, TX, United States Duration: Jul 22 2007 → Jul 26 2007

Publication series

Name	American Society of Mechanical Engineers, Pressure Vessels and Piping Division (Publication) PVP
Volume	6
ISSN (Print)	0277-027X

Conference

Conference	2007 ASME Pressure Vessels and Piping Conference, PVP 2007
Country/Territory	United States
City	San Antonio, TX
Period	07/22/07 → 07/26/07

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10.1115/PVP2007-26091

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Ren, W., & Swlmdeman, R. (2008). Preliminary consideration of alloys 617 and 230 for generation IV nuclear reactor applications. In 2007 Proceedings of the ASME Pressure Vessels and Piping Conference - Materials and Fabrication (pp. 371-384). (American Society of Mechanical Engineers, Pressure Vessels and Piping Division (Publication) PVP; Vol. 6). https://doi.org/10.1115/PVP2007-26091

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title = "Preliminary consideration of alloys 617 and 230 for generation IV nuclear reactor applications",

abstract = "Alloys 617 and 230 are currently identified as two leading candidate metallic materials in the down selection for applications at temperatures above 760°C in the Gen IV Nuclear Reactor Systems. Qualifying the materials requires significant information related to Codification, mechanical behavior modeling, metallurgical stability, environmental resistance, and many other aspects. In the present paper, material requirements for the Gen IV Nuclear Reactor Systems are discussed; certain available information regarding the two alloys under consideration for the intended applications are reviewed and analyzed. Suggestions are presented for further R&D activities for the materials selection.",

author = "Weiju Ren and Robert Swlmdeman",

year = "2008",

doi = "10.1115/PVP2007-26091",

language = "English",

isbn = "0791842843",

series = "American Society of Mechanical Engineers, Pressure Vessels and Piping Division (Publication) PVP",

pages = "371--384",

booktitle = "2007 Proceedings of the ASME Pressure Vessels and Piping Conference - Materials and Fabrication",

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Ren, W & Swlmdeman, R 2008, Preliminary consideration of alloys 617 and 230 for generation IV nuclear reactor applications. in 2007 Proceedings of the ASME Pressure Vessels and Piping Conference - Materials and Fabrication. American Society of Mechanical Engineers, Pressure Vessels and Piping Division (Publication) PVP, vol. 6, pp. 371-384, 2007 ASME Pressure Vessels and Piping Conference, PVP 2007, San Antonio, TX, United States, 07/22/07. https://doi.org/10.1115/PVP2007-26091

Preliminary consideration of alloys 617 and 230 for generation IV nuclear reactor applications. / Ren, Weiju; Swlmdeman, Robert.
2007 Proceedings of the ASME Pressure Vessels and Piping Conference - Materials and Fabrication. 2008. p. 371-384 (American Society of Mechanical Engineers, Pressure Vessels and Piping Division (Publication) PVP; Vol. 6).

Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review

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AB - Alloys 617 and 230 are currently identified as two leading candidate metallic materials in the down selection for applications at temperatures above 760°C in the Gen IV Nuclear Reactor Systems. Qualifying the materials requires significant information related to Codification, mechanical behavior modeling, metallurgical stability, environmental resistance, and many other aspects. In the present paper, material requirements for the Gen IV Nuclear Reactor Systems are discussed; certain available information regarding the two alloys under consideration for the intended applications are reviewed and analyzed. Suggestions are presented for further R&D activities for the materials selection.

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Preliminary consideration of alloys 617 and 230 for generation IV nuclear reactor applications

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