Tensile property of low activation vanadium alloy after liquid lithium exposure

Takuya Nagasaka; Takeo Muroga; Meimei Li; David T. Hoelzer; Steven J. Zinkle; Martin L. Grossbeck; Hideki Matsui

doi:10.1016/j.fusengdes.2005.09.029

Tensile property of low activation vanadium alloy after liquid lithium exposure

Takuya Nagasaka, Takeo Muroga, Meimei Li, David T. Hoelzer, Steven J. Zinkle, Martin L. Grossbeck, Hideki Matsui

Alloy Behavior & Design

Research output: Contribution to journal › Conference article › peer-review

21 Scopus citations

Abstract

A candidate low activation vanadium (V) alloy, V-4Cr-4Ti (NIFS-HEAT-2), was exposed to liquid lithium (Li) at 973 and 1073 K for up to 1963 h. Contamination by carbon (C) and nitrogen (N) from the Li on the order of thousands of wppm were observed. Oxygen (O) levels were reduced to the several 10 wppm level by Li exposure at 1073 K, but not at 973 K. The Li exposure caused strength degradation as measured by tensile tests at 973 and 1073 K. On the other hand, good ductility was demonstrated after the Li exposure even with the significant contamination of C and N. From microstructural observations, C and N are likely to be scavenged by Ti-C-N type precipitates. Reduction of O was attributed to disappearance of Ti-C-O type precipitates.

Original language	English
Pages (from-to)	307-313
Number of pages	7
Journal	Fusion Engineering and Design
Volume	81 A
Issue number	1-4
DOIs	https://doi.org/10.1016/j.fusengdes.2005.09.029
State	Published - Feb 2006
Event	Proceedings of the Seventh International Symposium on Fusion Nuclear Technology ISFNT-7 Part A - Duration: May 22 2005 → May 27 2005

Funding

This study was supported by National Institute for Fusion Science budget code NIFS05UCFF005, JUPITER-II program (Japan-USA Program of Irradiation Test for Fusion Research), and the inter-university cooperative research program of the Irradiation Experimental Facility, Institute for Materials Research, Tohoku University.

Funders	Funder number
Institute for Materials Research, Tohoku University

Keywords

First wall/blanket materials
Impurity effect
Mechanical property

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10.1016/j.fusengdes.2005.09.029

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title = "Tensile property of low activation vanadium alloy after liquid lithium exposure",

abstract = "A candidate low activation vanadium (V) alloy, V-4Cr-4Ti (NIFS-HEAT-2), was exposed to liquid lithium (Li) at 973 and 1073 K for up to 1963 h. Contamination by carbon (C) and nitrogen (N) from the Li on the order of thousands of wppm were observed. Oxygen (O) levels were reduced to the several 10 wppm level by Li exposure at 1073 K, but not at 973 K. The Li exposure caused strength degradation as measured by tensile tests at 973 and 1073 K. On the other hand, good ductility was demonstrated after the Li exposure even with the significant contamination of C and N. From microstructural observations, C and N are likely to be scavenged by Ti-C-N type precipitates. Reduction of O was attributed to disappearance of Ti-C-O type precipitates.",

keywords = "First wall/blanket materials, Impurity effect, Mechanical property",

author = "Takuya Nagasaka and Takeo Muroga and Meimei Li and Hoelzer, {David T.} and Zinkle, {Steven J.} and Grossbeck, {Martin L.} and Hideki Matsui",

year = "2006",

month = feb,

doi = "10.1016/j.fusengdes.2005.09.029",

language = "English",

volume = "81 A",

pages = "307--313",

journal = "Fusion Engineering and Design",

issn = "0920-3796",

publisher = "Elsevier",

number = "1-4",

note = "Proceedings of the Seventh International Symposium on Fusion Nuclear Technology ISFNT-7 Part A ; Conference date: 22-05-2005 Through 27-05-2005",

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TY - JOUR

T1 - Tensile property of low activation vanadium alloy after liquid lithium exposure

AU - Nagasaka, Takuya

AU - Muroga, Takeo

AU - Li, Meimei

AU - Hoelzer, David T.

AU - Zinkle, Steven J.

AU - Grossbeck, Martin L.

AU - Matsui, Hideki

PY - 2006/2

Y1 - 2006/2

N2 - A candidate low activation vanadium (V) alloy, V-4Cr-4Ti (NIFS-HEAT-2), was exposed to liquid lithium (Li) at 973 and 1073 K for up to 1963 h. Contamination by carbon (C) and nitrogen (N) from the Li on the order of thousands of wppm were observed. Oxygen (O) levels were reduced to the several 10 wppm level by Li exposure at 1073 K, but not at 973 K. The Li exposure caused strength degradation as measured by tensile tests at 973 and 1073 K. On the other hand, good ductility was demonstrated after the Li exposure even with the significant contamination of C and N. From microstructural observations, C and N are likely to be scavenged by Ti-C-N type precipitates. Reduction of O was attributed to disappearance of Ti-C-O type precipitates.

AB - A candidate low activation vanadium (V) alloy, V-4Cr-4Ti (NIFS-HEAT-2), was exposed to liquid lithium (Li) at 973 and 1073 K for up to 1963 h. Contamination by carbon (C) and nitrogen (N) from the Li on the order of thousands of wppm were observed. Oxygen (O) levels were reduced to the several 10 wppm level by Li exposure at 1073 K, but not at 973 K. The Li exposure caused strength degradation as measured by tensile tests at 973 and 1073 K. On the other hand, good ductility was demonstrated after the Li exposure even with the significant contamination of C and N. From microstructural observations, C and N are likely to be scavenged by Ti-C-N type precipitates. Reduction of O was attributed to disappearance of Ti-C-O type precipitates.

KW - First wall/blanket materials

KW - Impurity effect

KW - Mechanical property

UR - http://www.scopus.com/inward/record.url?scp=31844436963&partnerID=8YFLogxK

U2 - 10.1016/j.fusengdes.2005.09.029

DO - 10.1016/j.fusengdes.2005.09.029

M3 - Conference article

AN - SCOPUS:31844436963

SN - 0920-3796

VL - 81 A

SP - 307

EP - 313

JO - Fusion Engineering and Design

JF - Fusion Engineering and Design

IS - 1-4

T2 - Proceedings of the Seventh International Symposium on Fusion Nuclear Technology ISFNT-7 Part A

Y2 - 22 May 2005 through 27 May 2005

ER -

Tensile property of low activation vanadium alloy after liquid lithium exposure

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