U.S. Department of EnergyOffice of Scientific and Technical Information
Properties of V-4Cr-4Ti for application as fusion reactor structural components
Abstract
Vanadium-base alloys are promising candidate materials for application in fusion reactor first-wall and blanket structures because they offer several important advantages, i.e., inherently low irradiation-induced activity, good mechanical properties, good compatibility with lithium, high thermal conductivity, and good resistance to irradiation-induced swelling and damage. As part of a program to screen candidate alloys and develop an optimized vanadium-base alloy, extensive investigations of various V-Ti, V-Cr-Ti, and V-Ti-Si alloys have been conducted after irradiation in lithium in fission reactors. From these investigations, V-4 wt.% Cr-4 wt.% Ti was identified as the most promising alloy. The alloy exhibited attractive mechanical and physical properties that are prerequisites for first-wall and blanket structures, i.e., high tensile strength, high ductility, good creep properties, high impact energy, low ductile-brittle transition temperature before and after irradiation, excellent resistance to irradiation-induced swelling and microstructural instability, and good resistance to corrosion in lithium. In particular, the alloy is virtually immune to irradiation-induced embrittlement, a remarkable property compared to other candidate materials being investigated in the fusion-reactor-materials community. Effects of helium, charged dynamically in simulation of realistic fusion reactor conditions, on tensile, ductile-brittle transition, and swelling properties were insignificant.
- Authors:
- Publication Date:
- Research Org.:
- Argonne National Lab., IL (United States). Energy Technology Div.
- Sponsoring Org.:
- USDOE, Washington, DC (United States)
- OSTI Identifier:
- 10194461
- Report Number(s):
- ANL/ET/CP-81606; CONF-940664-34
ON: DE95002907; TRN: 94:023976
- DOE Contract Number:
- W-31109-ENG-38
- Resource Type:
- Technical Report
- Resource Relation:
- Conference: ISFNT-3: international symposium on fusion nuclear technology,Los Angeles, CA (United States),27 Jun - 1 Jul 1994; Other Information: PBD: Aug 1994
- Country of Publication:
- United States
- Language:
- English
- Subject:
- 36 MATERIALS SCIENCE; 70 PLASMA PHYSICS AND FUSION TECHNOLOGY; VANADIUM BASE ALLOYS; PHYSICAL RADIATION EFFECTS; CHROMIUM ALLOYS; TITANIUM ALLOYS; THERMONUCLEAR REACTOR MATERIALS; TENSILE PROPERTIES; IMPACT STRENGTH; CORROSION RESISTANCE; CHEMICAL COMPOSITION; FRACTURE PROPERTIES; MICROSTRUCTURE; EXPERIMENTAL DATA; 360106; 700480; RADIATION EFFECTS; COMPONENT DEVELOPMENT; MATERIALS STUDIES
Citation Formats
Chung, H M, Loomis, B A, and Smith, D L. Properties of V-4Cr-4Ti for application as fusion reactor structural components. United States: N. p., 1994.
Web. doi:10.2172/10194461.
Chung, H M, Loomis, B A, & Smith, D L. Properties of V-4Cr-4Ti for application as fusion reactor structural components. United States. https://doi.org/10.2172/10194461
Chung, H M, Loomis, B A, and Smith, D L. 1994.
"Properties of V-4Cr-4Ti for application as fusion reactor structural components". United States. https://doi.org/10.2172/10194461. https://www.osti.gov/servlets/purl/10194461.
@article{osti_10194461,
title = {Properties of V-4Cr-4Ti for application as fusion reactor structural components},
author = {Chung, H M and Loomis, B A and Smith, D L},
abstractNote = {Vanadium-base alloys are promising candidate materials for application in fusion reactor first-wall and blanket structures because they offer several important advantages, i.e., inherently low irradiation-induced activity, good mechanical properties, good compatibility with lithium, high thermal conductivity, and good resistance to irradiation-induced swelling and damage. As part of a program to screen candidate alloys and develop an optimized vanadium-base alloy, extensive investigations of various V-Ti, V-Cr-Ti, and V-Ti-Si alloys have been conducted after irradiation in lithium in fission reactors. From these investigations, V-4 wt.% Cr-4 wt.% Ti was identified as the most promising alloy. The alloy exhibited attractive mechanical and physical properties that are prerequisites for first-wall and blanket structures, i.e., high tensile strength, high ductility, good creep properties, high impact energy, low ductile-brittle transition temperature before and after irradiation, excellent resistance to irradiation-induced swelling and microstructural instability, and good resistance to corrosion in lithium. In particular, the alloy is virtually immune to irradiation-induced embrittlement, a remarkable property compared to other candidate materials being investigated in the fusion-reactor-materials community. Effects of helium, charged dynamically in simulation of realistic fusion reactor conditions, on tensile, ductile-brittle transition, and swelling properties were insignificant.},
doi = {10.2172/10194461},
url = {https://www.osti.gov/biblio/10194461},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Mon Aug 01 00:00:00 EDT 1994},
month = {Mon Aug 01 00:00:00 EDT 1994}
}