Summary of the investigation of low temperature, low dose radiation effects on the V-4Cr-4Ti alloy

Snead, L.L.; Zinkle, S.J.; Alexander, D.J.; Rowcliffe, A.F.; Robertson, J.P.; Eatherly, W.S.

doi:10.2172/335368

Cited by 5 publications

(5 citation statements)

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“…The increase in yield stress (YS) for neutron-irradiated V-4Cr-4Ti alloys. Open symbols show the data for US832665 heat tested at irradiation temperature of around 373 K [22][23][24][25].…”

Section: Discussionmentioning

confidence: 99%

“…All the data for neutron-irradiated V-4Cr-4Ti alloys exhibited pronounced flow localization, with uniform elongations (UE) < 0.2 % in all cases. YSs after irradiation to 0.5 dpa at 373-603 K were independent of the irradiation temperatures [23]. The similarity of YSs of V-4Cr-4Ti alloy irradiated at 603 K to 4-6 dpa [25] and 18 dpa [26] implies that the irradiation hardening at this relatively low temperature (< 673 K) has reached a saturation level already at a dose of ~5 dpa.…”

Section: Fem Modeling Of Ion-irradiated V-4cr-4ti Alloymentioning

confidence: 91%

“…Open symbols show the data for US832665 heat, which is a V-4Cr-4Ti alloy procured by the US Department of Energy [21]. Their tensile properties for US832665 heat tested at irradiation temperature of around 373 K were reported [22][23][24][25]. Closed square shows our data for NIFS-HEAT-2 tested at room temperature.…”

Section: Fem Modeling Of Ion-irradiated V-4cr-4ti Alloymentioning

confidence: 99%

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Evaluation of irradiation hardening of ion-irradiated V–4Cr–4Ti and V–4Cr–4Ti–0.15Y alloys by nanoindentation techniques

Miyazawa

Nagasaka

Kasada

et al. 2014

Journal of Nuclear Materials

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“…The increase in yield stress (YS) for neutron-irradiated V-4Cr-4Ti alloys. Open symbols show the data for US832665 heat tested at irradiation temperature of around 373 K [22][23][24][25].…”

Section: Discussionmentioning

confidence: 99%

Section: Fem Modeling Of Ion-irradiated V-4cr-4ti Alloymentioning

confidence: 91%

Section: Fem Modeling Of Ion-irradiated V-4cr-4ti Alloymentioning

confidence: 99%

See 1 more Smart Citation

Evaluation of irradiation hardening of ion-irradiated V–4Cr–4Ti and V–4Cr–4Ti–0.15Y alloys by nanoindentation techniques

Miyazawa

Nagasaka

Kasada

et al. 2014

Journal of Nuclear Materials

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“…Fig. 6 shows comparison of irradiation hardening to other low activation vanadium alloys, such as US832665, a large heat by US-DOE [8], and VM9401 [9], by a laboratory scale melting. Only the data on the plate before welding, which is equivalent to base metal, are available for the two alloys.…”

Section: Hardening Mechanism At Weld Metalmentioning

confidence: 99%

“…(5) Optimum PWHT temperature for NIFS-HEAT should be placed between 873 and 1223 K, where suitable precipitation size and distribution are expected without causing precipitation hardening, over-coarsening of precipitates or irradiation hardening. Neutron fluence dependence of irradiation hardening of three V-4Cr-4Ti alloys, such as NIFS-HEAT-2 (NH2), US832665[8] and VM9401[9]. Concentrations of C/N/O in US832665 are 80/85/310 wppm, respectively.…”

mentioning

confidence: 99%

Impact properties of NIFS-HEAT-2 (V–4Cr–4Ti) after YAG laser welding and neutron irradiation at 563 K

Nagasaka

Heo

Muroga

et al. 2004

Journal of Nuclear Materials

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Welded high purity low activation vanadium alloys, such as NIFS-HEATs, have demonstrated good mechanical properties at as-welded condition. In this study, welded NIFS-HEAT-2 were irradiated at a low temperature to investigate the effect of irradiation hardening on impact properties, and to understand the characteristics of radiation defects in welded vanadium alloys.The weld materials were 4 mm-thick plates of NIFS-HEAT-2 (V-4Cr-4Ti) annealed at 1273 K for 2 hr. The samples were made by bead-an-plate welding with a 1.6 kW Y AG laser in a high purity Ar. Input power and welding speed were 290 Jim and 0.33 m I min, respectively. Table I shows concentration of HlCINIO before and after welding. No significant contamination by welding was observed. V -notch impact specimens (1.5 X 1.5 X 20 mm) were machined from the weld metal and the base metal of the welded plate. The notch depth (d) was 0.3 mm. In order to investigate the effect of post weld heat treatment (PWHT), specimens for hardness investigation were prepared and annealed for I hr at 673 K, 873 K and 1223 K. The samples were irradiated in JMTR (Japan Materials Testing Reactor) at 563 K. The neutron f1uence was 4.5 X 10" n m" (0.08 dpa). Figure I shows results of Charpy impact test. Absorbed energy is nonnalized by the function of the specimen size at the V -notch, where specimen width (B) is L5 mm, and ligament (b ~ B -d) is 1.2 mm. Before irradiation, both the base metal (BM) and the weld metal (WM) maintained good ductility at all tested temperatures. Upper shelf energy, Eu, was estimated as 0.4 J m'] After irradiation, upper shelf energy of the base metal and weld metal was around 0.35 J m", which was 10-15 % lower than that before irradiation. In addition, absorbed energy of the weld metal after irradiation showed a remarkable drop at 77 K. Ductile-brittle transition temperature (DBTT) of the weld metal after irradiation was estimated as 113 K, where absorbed energy was expected to be half the upper shelf energy before irradiation. DBTIs determined from the other curves were less than 77 K, Figure 2 shows hardness distribution around the weld bead. From microstructural observations, the width of the weld metal was I mm as indicated in the figure. Base metal regions were determined as 4 mm or farther from the bead center, where the hardness before irradiation was the same as that before welding. Irradiation hardening was estimated as the difference between the average hardness in each region. Irradiation hardening of the weld metal, 64 Hv, was 40 % larger than that ofthe base metal, 46 Hv.The weld metal became brittle at 77 K after irradiation as shown in Fig. I. It is recognized that the large hardening shown in Fig. 2 is responsible for the embrittlement of the weld metal at 77 K. Yield stress is increased due to irradiation hardening, and higher than the stress for cleavage fracture.

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Changes in Mechanical Properties of High-Purity V-4Cr-4Ti-Si, Al, Y Alloys after Neutron Irradiation at Relatively Low Temperatures

Chuto

Satou

Hasegawa

et al. 2004

Effects of Radiation on Materials: 21st International Symposium

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Mechanical properties after neutron irradiation of V-4Cr-4Ti-0.1Si-0.1Al-0.1Y and V-4Cr-4Ti-0.1Si-0.1Al-0.3Y alloys (nominal weight percentage) were studied. Neutron irradiation was carried out at 290°C to 8×1022 n/m2 (E>1 MeV, about 0.014 dpa) in the Japan Materials Testing Reactor (JMTR). Tensile tests were carried out using miniaturized specimens at ambient temperature and irradiation temperature. Charpy impact tests were conducted at temperatures from -196 to 0°C using an instrumented machine. There is little difference in tensile properties after neutron irradiation between the two alloys. Increase in yield stress was relatively small (∼100 MPa), and uniform elongation remained more than 10%. Because of a low concentration of interstitial impurities, good tensile properties could be retained even after neutron irradiation at 290°C. Ductile-to-brittle transition temperature (DBTT) of V-4Cr-4Ti-0.1Si-0.1Al-0.1Y alloys hardly changed, whereas absorbed energy was slightly reduced after neutron irradiation.

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Summary of the investigation of low temperature, low dose radiation effects on the V-4Cr-4Ti alloy

Cited by 5 publications

References 0 publications

Evaluation of irradiation hardening of ion-irradiated V–4Cr–4Ti and V–4Cr–4Ti–0.15Y alloys by nanoindentation techniques

Evaluation of irradiation hardening of ion-irradiated V–4Cr–4Ti and V–4Cr–4Ti–0.15Y alloys by nanoindentation techniques

Impact properties of NIFS-HEAT-2 (V–4Cr–4Ti) after YAG laser welding and neutron irradiation at 563 K

Changes in Mechanical Properties of High-Purity V-4Cr-4Ti-Si, Al, Y Alloys after Neutron Irradiation at Relatively Low Temperatures

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