Published August 1, 2007 | Version v1
Journal article

Biaxial thermal creep of two heats of V4Cr4Ti at 700 and 800 oC in a liquid lithium environment

  • 1. Materials Science and Technology Division, Oak Ridge National Laboratory, P.O. Box 2008, MS 6138, Oak Ridge, TN 37831 (United States)
  • 2. National Institute for Fusion Science, Oroshi, Toki, Gifu 509-5292 (Japan)
  • 3. Nuclear Engineering Department, University of Tennessee, Knoxville, TN 37996 (United States)
  • 4. NPESE, University of Fukui, Bunkyo, Fukui 910-8507 (Japan)
  • 5. Institute for Materials Research, Tohoku University, Katahira, Sendai 980-8577 (Japan)
  • 6. International Research Center for Nuclear Materials Science, Institute for Materials Research, Tohoku University, Oarai, Ibaraki 311-1313 (Japan)

Description

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 oC 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 oC 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

Additional details

Identifiers

DOI
10.1016/j.jnucmat.2007.03.081;
PII
S0022-3115(07)00470-9;

Publishing Information

Journal Title
Journal of Nuclear Materials
Journal Volume
367-370
Journal Page Range
p. 788-793
ISSN
0022-3115
CODEN
JNUMAM

Conference

Title
12. international conference on fusion reactor materials
Acronym
ICFRM-12
Dates
7-12 Dec 2005
Place
Santa Barbara, CA (United States)

INIS

Country of Publication
Netherlands
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
39010271
Subject category
S36: MATERIALS SCIENCE;
Resource subtype / Literary indicator
Conference
Descriptors DEI
CHROMIUM ALLOYS; CREEP; HEAT; LITHIUM; NITROGEN; OXYGEN; RUPTURES; STRESSES; TEMPERATURE RANGE 0400-1000 K; TEMPERATURE RANGE 1000-4000 K; TITANIUM ALLOYS; VANADIUM ALLOYS
Descriptors DEC
ALKALI METALS; ALLOYS; ELEMENTS; ENERGY; FAILURES; MECHANICAL PROPERTIES; METALS; NONMETALS; TEMPERATURE RANGE; TRANSITION ELEMENT ALLOYS

Optional Information

Copyright
Copyright (c) 2007 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.