Abstract:High heat flux tests with central heat flux of 10.5 MW/m 2 using helium neutral beams have been carried out on rolled tungsten. The energy of helium particles is 33 keV and the particle flux is 2×10 21 m -2 s -1 . An 80×65×3 mm 3 rolled tungsten plate is firstly exposed to a 4.6 s pulse resulting in partially molten surfaces. Thereafter the tungsten plate is irradiated by several helium pulses with fluences of 1.2-2.5×10 22 /m 2 and peak temperatures from 1450 to 2590 °C . The experiments show that: (1) helium… Show more
“…1 summarizes the results reported in Ref. [2], [5] and [7], and shows the observed relationship between surface modification, fluence and peak surface temperature. The mechanism for the formation of these surface morphologies is, however, not fully understood, especially the effects of temperature dependence.…”
Section: Introductionmentioning
confidence: 78%
“…The mechanism for the formation of these surface morphologies is, however, not fully understood, especially the effects of temperature dependence. In addition, some studies have found an orientation dependence for He-induced damage [3,5,8]. This is interesting as it may provide a way to optimize the plasma facing material by control of the crystallographic texture.…”
Section: Introductionmentioning
confidence: 98%
“…During such usage it will be exposed to both particle irradiation and high heat flux loads. Particle irradiation from the fusion plasma, especially helium (He) bombardment, is expected to lead to performance degradation of W components due to the development of significant changes in surface morphology, such as the formation of blisters, holes, fiber-form nanostructures and coral-like structures [2][3][4][5][6][7]. In addition, synergistic effects between heat loading and particle irradiation can accelerate such surface damage [2].…”
Section: Introductionmentioning
confidence: 99%
“…In addition, synergistic effects between heat loading and particle irradiation can accelerate such surface damage [2]. The performance of W under the combined action of both heat and a particle flux has therefore been studied keenly in recent years [2,5]. In fusion devices during steady-state heat flux conditions active cooling of the plasma facing components ensures that the surface temperature is kept at a relatively low level.…”
The effect of combined heating and helium particle flux on annealed tungsten samples has been studied in the neutral beam facility GLADIS. He beams with power densities of 2.4 MW/m 2 and 9.5 MW/m 2 were used to adiabatically load the samples to peak surface temperatures from ~ 950 °C (1223 K) to ~ 2700 °C (2973 K). Changes in the surface morphology resulting from combined heat and the flux exposure were studied for He fluences up to 3×10 22 /m 2 . Typical structures for the sample loaded at ~ 950 °C (1223 K) were blisters with a clear grain orientation dependence and the largest blisters formed on grains with <001> surface normal. However at higher temperatures, blistering was more easily suppressed for grains near this orientation because the growth of larger blister takes place more slowly. An evolution from a "porous structure" to a "coral-like structure" with increasing fluence was observed on the samples loaded at the highest temperature. Based on these results mechanisms for surface modification at different temperatures are discussed and a texture with <001> parallel to the normal direction of the grains is suggested to optimize the plasma facing material due to their stronger resistance to early stage blistering.
“…1 summarizes the results reported in Ref. [2], [5] and [7], and shows the observed relationship between surface modification, fluence and peak surface temperature. The mechanism for the formation of these surface morphologies is, however, not fully understood, especially the effects of temperature dependence.…”
Section: Introductionmentioning
confidence: 78%
“…The mechanism for the formation of these surface morphologies is, however, not fully understood, especially the effects of temperature dependence. In addition, some studies have found an orientation dependence for He-induced damage [3,5,8]. This is interesting as it may provide a way to optimize the plasma facing material by control of the crystallographic texture.…”
Section: Introductionmentioning
confidence: 98%
“…During such usage it will be exposed to both particle irradiation and high heat flux loads. Particle irradiation from the fusion plasma, especially helium (He) bombardment, is expected to lead to performance degradation of W components due to the development of significant changes in surface morphology, such as the formation of blisters, holes, fiber-form nanostructures and coral-like structures [2][3][4][5][6][7]. In addition, synergistic effects between heat loading and particle irradiation can accelerate such surface damage [2].…”
Section: Introductionmentioning
confidence: 99%
“…In addition, synergistic effects between heat loading and particle irradiation can accelerate such surface damage [2]. The performance of W under the combined action of both heat and a particle flux has therefore been studied keenly in recent years [2,5]. In fusion devices during steady-state heat flux conditions active cooling of the plasma facing components ensures that the surface temperature is kept at a relatively low level.…”
The effect of combined heating and helium particle flux on annealed tungsten samples has been studied in the neutral beam facility GLADIS. He beams with power densities of 2.4 MW/m 2 and 9.5 MW/m 2 were used to adiabatically load the samples to peak surface temperatures from ~ 950 °C (1223 K) to ~ 2700 °C (2973 K). Changes in the surface morphology resulting from combined heat and the flux exposure were studied for He fluences up to 3×10 22 /m 2 . Typical structures for the sample loaded at ~ 950 °C (1223 K) were blisters with a clear grain orientation dependence and the largest blisters formed on grains with <001> surface normal. However at higher temperatures, blistering was more easily suppressed for grains near this orientation because the growth of larger blister takes place more slowly. An evolution from a "porous structure" to a "coral-like structure" with increasing fluence was observed on the samples loaded at the highest temperature. Based on these results mechanisms for surface modification at different temperatures are discussed and a texture with <001> parallel to the normal direction of the grains is suggested to optimize the plasma facing material due to their stronger resistance to early stage blistering.
“…The saturation of helium atoms leads to the formation of bubbles as well. Depending on the irradiation conditions, bubbles ranging from several tens of nanometers up to micron in size can develop in the material [9,10]. Moreover, with increasing temperature (above 700°C) and fl uence approximately 10 25 m -2 a nanostructure called helium/tungsten 'fuzz' starts to develop [11].…”
Abstract. Tungsten is a prime choice for armor material in future nuclear fusion devices. For the realization of fusion, it is necessary to address issues related to the plasma-armor interactions. In this work, several types of tungsten material were studied, i.e. tungsten prepared by spark plasma sintering (SPS) and by water stabilized plasma spraying (WSP) technique. An intended surface porosity was created in the samples to model hydrogen/ helium bubbles. The samples were subjected to a laser heat loading and a radiation loading of deuterium plasma to simulate edge plasma conditions of a nuclear fusion device (power density of 10 8 W/cm 2 and 10 7 W/cm 2 , respectively, in the pulse intervals up to 200 ns). Thermally induced changes in the morphology and the damage to the studied surfaces are described. Possible consequences for the fusion device operation are pointed out.
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