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Title: Biaxial Thermal Creep of Two Heats of V 4Cr 4Ti at 700 and 800 C in a Liquid Lithium Environment

Abstract

This paper presents biaxial thermal creep results for the vanadium alloy V4Cr4Ti in liquid lithium using US Heat 832665 and two batches of tubing made from NIFS-Heat-2. The tests were performed at 700 and 800 C over a stress range of 30-120 MPa using pressurized tube specimens. Lithium environments changed C, N and O concentrations in V4Cr4Ti. Oxygen removal from the alloy to lithium was small when there was a significant pickup of nitrogen during exposures. The creep response of V4Cr4Ti was characterized by an inverted primary creep followed by a secondary creep or an accelerating creep up to creep rupture. A normal primary creep was also observed in US Heat 832665 when tested at 700 C and 120 MPa. Improved creep rupture properties were observed in the JP-NIFS-Heat-2 specimens compared to the US-NIFS-Heat-2 specimens. Creep response of V4Cr4Ti is apparently dependent on the heat, tubing production, and stress and temperature conditions.

Authors:
 [1];  [2];  [1];  [1];  [1];  [2];  [3];  [4];  [5]
  1. ORNL
  2. National Institute for Fusion Science, Toki, Japan
  3. University of Fukui, Fukui, Japan
  4. Institute for Materials Research, Tohoku University, Sendai, Japan
  5. Tohoku University, Ibaraki, Japan
Publication Date:
Research Org.:
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Sponsoring Org.:
USDOE Office of Science (SC)
OSTI Identifier:
966068
DOE Contract Number:  
DE-AC05-00OR22725
Resource Type:
Journal Article
Resource Relation:
Journal Name: Journal of Nuclear Materials; Journal Volume: 367-370; Journal Issue: 1
Country of Publication:
United States
Language:
English
Subject:
36 MATERIALS SCIENCE; ALLOYS; CREEP; LITHIUM; NITROGEN; OXYGEN; PRODUCTION; REMOVAL; RUPTURES; VANADIUM ALLOYS

Citation Formats

Li, Meimei, Nagasaka, Takuya, Hoelzer, David T, Grossbeck, Martin L, Zinkle, Steven J, Muroga, Takeo, Fukumoto, Ken-ichi, Matsui, Hideki, and Narui, Manoru. Biaxial Thermal Creep of Two Heats of V4Cr4Ti at 700 and 800 C in a Liquid Lithium Environment. United States: N. p., 2007. Web. doi:10.1016/j.jnucmat.2007.03.081.
Li, Meimei, Nagasaka, Takuya, Hoelzer, David T, Grossbeck, Martin L, Zinkle, Steven J, Muroga, Takeo, Fukumoto, Ken-ichi, Matsui, Hideki, & Narui, Manoru. Biaxial Thermal Creep of Two Heats of V4Cr4Ti at 700 and 800 C in a Liquid Lithium Environment. United States. doi:10.1016/j.jnucmat.2007.03.081.
Li, Meimei, Nagasaka, Takuya, Hoelzer, David T, Grossbeck, Martin L, Zinkle, Steven J, Muroga, Takeo, Fukumoto, Ken-ichi, Matsui, Hideki, and Narui, Manoru. Mon . "Biaxial Thermal Creep of Two Heats of V4Cr4Ti at 700 and 800 C in a Liquid Lithium Environment". United States. doi:10.1016/j.jnucmat.2007.03.081.
@article{osti_966068,
title = {Biaxial Thermal Creep of Two Heats of V4Cr4Ti at 700 and 800 C in a Liquid Lithium Environment},
author = {Li, Meimei and Nagasaka, Takuya and Hoelzer, David T and Grossbeck, Martin L and Zinkle, Steven J and Muroga, Takeo and Fukumoto, Ken-ichi and Matsui, Hideki and Narui, Manoru},
abstractNote = {This paper presents biaxial thermal creep results for the vanadium alloy V4Cr4Ti in liquid lithium using US Heat 832665 and two batches of tubing made from NIFS-Heat-2. The tests were performed at 700 and 800 C over a stress range of 30-120 MPa using pressurized tube specimens. Lithium environments changed C, N and O concentrations in V4Cr4Ti. Oxygen removal from the alloy to lithium was small when there was a significant pickup of nitrogen during exposures. The creep response of V4Cr4Ti was characterized by an inverted primary creep followed by a secondary creep or an accelerating creep up to creep rupture. A normal primary creep was also observed in US Heat 832665 when tested at 700 C and 120 MPa. Improved creep rupture properties were observed in the JP-NIFS-Heat-2 specimens compared to the US-NIFS-Heat-2 specimens. Creep response of V4Cr4Ti is apparently dependent on the heat, tubing production, and stress and temperature conditions.},
doi = {10.1016/j.jnucmat.2007.03.081},
journal = {Journal of Nuclear Materials},
number = 1,
volume = 367-370,
place = {United States},
year = {Mon Jan 01 00:00:00 EST 2007},
month = {Mon Jan 01 00:00:00 EST 2007}
}