Properties of V-4Cr-4Ti for application as fusion reactor structural components
- Argonne National Lab., IL (United States); and others
Vanadium-base alloys are promising candidate material for application in fusion reactor first wall and blanket structure because of 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 tensile properties, ductile-brittle-transition characteristics, swelling behavior, and microstructural evolution of various V-Ti, V-Cr-Ti, and V-Ti-Si alloys have been conducted after irradiation in lithium in the Fast Flux Test Facility (FFTF) at 420-600{degrees}C up to 120 dpa. From these investigations, V-Cr-Ti alloys containing {approximately}4-5 wt. % Cr. 3-5 wt. % Ti, 400-1000 wt. ppm Si, and <1000 wt. ppm O+N+C were identified as most promising alloys. Consequently, V-4Cr-4Ti has been selected for comprehensive tests and examination, in particular effects of high-dose irradiation and dynamically charged helium on tensile, ductile-brittle-transition, irradiation-induced density change, and thermal creep behavior, and results of the comprehensive set of investigations are presented in this paper. The alloy exhibited the most attractive combination of mechanical and physical properties that are prerequisite to serve as first wall and blanket structure, i.e., tensile properties, impact energy, swelling resistance, and ductile-brittle-transition temperature (DBTT) before and after irradiation.
- OSTI ID:
- 197875
- Report Number(s):
- CONF-940664-; TRN: 95:005767-0185
- Resource Relation:
- Conference: ISFNT-3: international symposium on fusion nuclear technology, Los Angeles, CA (United States), 27 Jun - 1 Jul 1994; Other Information: PBD: 1994; Related Information: Is Part Of Third international symposium on fusion nuclear technology; PB: 362 p.
- Country of Publication:
- United States
- Language:
- English
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