Manufacture of semifinished items of alloys V-4Ti-4Cr and V-10Ti-5Cr for use as a structural material in fusion applications

Потапенко, М. М.; Drobishev, V.A.; Fil'kin, V.Ya.; Gubkin, I.N.; Myasnikov, V.V.; Никулин, А.Д.; Shingarev, É. N.; Vedernikov, G.P.; Votinov, S. N.; Zurabov, V. S.; Zolotarev, A.B.

doi:10.1016/s0022-3115(96)00285-1

Cited by 13 publications

(4 citation statements)

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“…The vanadium alloy reacts readily with oxygen at elevated temperatures even in a low gas pressure environment [21]. Owing to this behavior, the alloy is usually covered with an alloy jacket (e.g., steel) to avoid oxidation during the hot processing [22]. Since we wished to study the diffusion bonding of the V-4Cr-4Ti alloy to commercially pure Ti metal, a V-4Cr-4Ti alloy rod and a Ti metal pipe as the covering jacket were employed for the bonding (see Figure 1a).…”

Section: Methodsmentioning

confidence: 99%

Interface Characteristics of Ti-Clad V–4Cr–4Ti Alloy Diffusion-Bonded Joint Produced by Hot Forging

Zhang

Han

et al. 2018

Applied Sciences

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Diffusion bonding of V-4Cr-4Ti alloy to pure titanium (Ti) was carried out by hot forging in the temperature range between 1150 • C and 950 • C. The microstructure and mechanical properties of the bonded joint were determined by using light optical microscopy (OM), scanning electron microscopy (SEM), energy dispersive spectroscopy (EDS), micro-hardness measurements, and shear tests. The results indicate that the sound dissimilar joint can be obtained through hot forging processes. The interface has a width of about 100 µm and can be divided into two distinctive zones: a Widmanstatten structure zone and a β-Ti phase structure zone. According to the micro-hardness distribution profile across the substrates and the interface, the largest hardness of 332 HV was measured in a narrow region between the Ti substrate and the joint, which is remarkably higher than that of the substrates (Ti of 190 HV and V-4Cr-4Ti alloy of 258 HV). The lowest hardness of only 182 HV was found in a region in the V-4Cr-4Ti substrate adjacent to the joint. The shear test showed that the joint has a bonding strength higher than 165 MPa and a fracture of the joint took place in the region with the highest hardness.

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Section: Methodsmentioning

confidence: 99%

Interface Characteristics of Ti-Clad V–4Cr–4Ti Alloy Diffusion-Bonded Joint Produced by Hot Forging

Zhang

Han

et al. 2018

Applied Sciences

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“…Corresponding calculations were performed at the Center for Nuclear Data of SSC RF IPPE [13,14]. Here the calculations are presented (figures 14-17, tables 2-4) for natural iron and steel RUSFER-EK-181 with recommended composition Fe-opt with technologically minimal impurity content, natural vanadium and V-4Ti-4Cr alloy with recommended composition VV1 with technologically minimal impurity content [11][12][13][14] for an irradiation time of 560 days (major campaign of BN-600) in typical neutron spectra from different sources (neutron (cm s −1 ), E > 0): BN-600 (6.5 × 10 15 ); The difference in neutron spectra (different primary recoil spectra) is also a problem of the radiation influence on the material properties. The R&D of the levels of nuclear transmutations (H, He, others), radiation damage (dpa, H/dpa, He/dpa), nuclear data base for transmutation and damage are parts of the RF irradiation material science.…”

Section: Nuclear Activation and Transmutation For Different Neutron S...mentioning

confidence: 99%

“…The final choice of DEMO concepts (and therefore the choice of the structural material or vice versa the R&D level of the structural materials will determine the concept of the fusion power reactor) will be made, with high probability, on the basis of the results of the DEMO-test blanket programmes for ITER (2015-2020) and the high dose results for structural materials in the fast breeder reactors (FBRs, BN-600 [4], BN-800 [5], others) and neutron source IFMIF [6]. The RF structural materials R&D programme is a part of the RF programmes (materials parts) of controlled fusion power (1990)(1991)(1992)(1993)(1994)(1995)(1996)(1997)(1998)(1999)(2000)(2001)(2002)(2003)(2004)(2005)(2006)(2007)2008-2015-under preparation) [1][2][3] and the FBR programmes [2][3][7][8][9][10][11][12][13][14]. As the requirements of structural core materials and conditions of their exploitation in fusion reactors and FBRs are very similar, the RF FBRs (BOR-60, BN-350, BN-600) experience for materials science is important for the development of advanced steels and alloys for fusion applications.…”

Section: Introductionmentioning

confidence: 99%

Structural materials for fusion power reactors—the RF R&D activities

Чернов¹,

Leont’eva-Smirnova²,

Потапенко³

et al. 2007

Nucl. Fusion

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Recent progress in the RF low activation structural materials R&D road map towards DEMO via the FBR tests (BOR-60, BN-600, BN-800) and the TBM tests in ITER is overviewed. The properties of the RAFMS RUSFER-EK-181 (Fe-12Cr-2W-Ta-V-B-C) and the V-4Ti-4Cr alloys are presented. The next important steps include further studies on the influence of high dose and high-temperature irradiation on the properties of base structural materials and joints. Activation, transmutation and radiation damage of the materials in BN-600 and DEMO-RF (Kurchatov Institute project) neutron spectra are calculated. The results of the application of the internal friction (ultrasonic) non-destructive method to research the DBTT are in good agreement with the results of the destructive impact method. The important influence of boron on the heat resistance of materials and the He concentration level under irradiation are calculated. The new special regimes of the heat treatments of the alloys are suggested to widen the temperature windows of the applications. The results of the BOR-60 examinations of RUSFER-EK-181 (irradiation temperature 320-340 • C and doses up to 15 dpa) are presented. The BN-600 projects for the high dose and high-temperature irradiation tests of manufactured alloys are presented.

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“…US: C, N, O: not specified, others: GD-MS [4]. RF and SWIP: not specified [5,6]. CEAJ-57: Cr, Ti: ICP-OES, Co, Ni, Mo: GD-MS, others: specified just as ICP [7].…”

Section: Introductionmentioning

confidence: 99%

High-temperature creep properties of NIFS-HEAT-2 high-purity low-activation vanadium alloy

et al. 2019

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A low-activation vanadium alloy with the composition of V-4 mass% Cr-4 mass% Ti is an alternative to reduced activation ferritic/martensitic steels for blanket structural material in fusion reactors. The NIFS-HEAT-2 (NH2) is the world’s highest-purity V–4Cr–4Ti alloy among over 30 kg scale heats. The processes to purify this heat have successfully enhanced workability, weldability and low-activation characteristics, however degradation of high-temperature strength was a concern due to possible purification softening. Therefore, the present study evaluated high-temperature creep properties of NH2 at around the operation temperature, 700 °C–800°C. The degradation of creep properties, such as shorter rupture time and enhanced creep rate, were observed for NH2, compared with a conventional US heat in the stress range of 150–200 MPa. On the other hand, it was revealed that these creep properties were comparable to those of the US heat in the lower applied stress of 100 MPa, though only short term rupture data are available at this moment. Since design stress for fusion blankets is expected below 100 MPa, purification up to the level of NH2 will induce no negative impact on the blanket service conditions.

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Manufacture of semifinished items of alloys V-4Ti-4Cr and V-10Ti-5Cr for use as a structural material in fusion applications

Cited by 13 publications

References 1 publication

Interface Characteristics of Ti-Clad V–4Cr–4Ti Alloy Diffusion-Bonded Joint Produced by Hot Forging

Interface Characteristics of Ti-Clad V–4Cr–4Ti Alloy Diffusion-Bonded Joint Produced by Hot Forging

Structural materials for fusion power reactors—the RF R&D activities

High-temperature creep properties of NIFS-HEAT-2 high-purity low-activation vanadium alloy

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