Review on the EFDA programme on tungsten materials technology and science

Rieth, M.; Boutard, Jean-Louis; Dudarev, S. L.; Ahlgren, T.; Antusch, S.; Baluc, N.; Barthe, M.F.; Becquart, Charlotte; Ciupiński, Ł.; Correia, J.B.; Domain, Christophe; Fikar, Jan; Fortuna, E.; Fu, Chu‐Chun; Gaganidze, E.; Galán, T.L.; Garcı́a-Rosales, C.; Gludovatz, Bernd; Greuner, H.; Heinola, K.; Holstein, N.; Juslin, Niklas; Koch, F.; Krauß, W.; Kurzydłowski, K. J.; Linke, J.; Linsmeier, Ch.; Luzginova, N.V.; Maier, H.; Martinez, Matteo; Missiaen, Jean-Michel; Muhammed, Musemma Kedir; Muñóz, A.; Muzyk, M.; Nordlund, K.; Nguyen-Manh, D.; Norajitra, P.; Opschoor, J.B.; Pintsuk, G.; Pippan, Reinhard; Ritz, G.; Romaner, Lorenz; Rupp, Daniel; Schäublin, R.; Schlösser, J.; Uytdenhouwen, I.; Laan, J.G. van der; Veleva, Lyubomira; Ventelon, Lisa; Wahlberg, Sverker; Willaime, F.; Wurster, Stefan; Yar, Mazher Ahmed

doi:10.1016/j.jnucmat.2011.01.075

Cited by 160 publications

(52 citation statements)

References 14 publications

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“…To check this point the scale formed at 700 °C was detached from the surface and, then, pulver ized. The only phase detected in the powder was WO 3 . This proved that WO 2.92 transformed into WO 3 when oxidation obeys linear kinetics.…”

Section: Discussionmentioning

confidence: 99%

“…Moreover, the influence of impuri ties cannot be ruled out because the reduction kinetics of non sag (NS) doped tungsten blue oxide is affected strongly by small amounts of impurities such K, Al or Si [27]. Usually, the typical yel low color of WO 3 was not observed during short term exposures, up to 6 h, between 500 and 700 °C [14], which would confirm that WO 3 formed once a continuous dark layer was established. Kellet external yellow scale in a sample oxidized 4 h at 700 °C [20].…”

Section: Discussionmentioning

confidence: 99%

“…Microcracking in the WO 3 layer has been sug gested to promote the change from parabolic to linear laws be cause of the formation of transversal cracks throughout the scale [14]. Cracking of the oxide scale could be expected because of the significant volume change resulting from the oxidation of tung sten into any kind of tungsten oxide (Pilling Bedworth ratio of 3.3 for WO 3 ). The high compression stresses arising from oxide growth were stored in the scale and mostly released during cracking events.…”

Section: Discussionmentioning

confidence: 99%

“…Its major drawback, however, is the poor oxi dation resistance which would cause irreversible detrimental effects on physical and chemical characteristics of W based com ponents [3,10]. Even though the PFCs will operate in vacuum con dition, fortuitous scenarios such as a LOCA event (Lost of Coolant Accident) or air ingress as a result of failure of the vessel's integrity, can lead to oxidizing atmospheres which will have harmful impact on the operation of PFCs [11,12].…”

Section: Introductionmentioning

confidence: 99%

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On the oxidation mechanism of pure tungsten in the temperature range 600–800°C

2012

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Abstract:The oxidation behavior of International Thermonuclear Experimental Reactor (ITER) reference tungsten grade has been evaluated in dry air in the temperature range 600 800 °C. At 600 °C, the scale remained protective while the integrity of W 18 O 49 layer was kept. Rapid increase in mass gain resulted from mas sive cracking at local areas in the W 18 O 49 layer. Then, a coarse non protective columnar WO 2.92 scale was developed which favoured rapid inward oxygen transport into the alloy. At 700 and 800 °C, growth stres ses in the scale were released through local cracking. At this stage, WO 2.92 became progressively trans formed into WO 3 when the oxygen partial pressure increased across the scale thickness.

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Section: Discussionmentioning

confidence: 99%

Section: Discussionmentioning

confidence: 99%

Section: Discussionmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

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On the oxidation mechanism of pure tungsten in the temperature range 600–800°C

2012

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“…Itis well established that tungsten has many special advantages as material for plasma facing armour or shield components, such as: high melting point and very low vapor pressure, low sputtering yield, good thermal conductivity, low thermal expansion coefficient, high strength at high temperatures, low retention of tritium and good dimensional stability under neutron irradiation. The designs of the ITER divertor vertical targets and the DEMO helium cooled divertor first wall consider tungsten as the preference candidate material [3].…”

Section: Introductionmentioning

confidence: 99%

Influence of processing route and yttria additions on the oxidation behavior of tungsten

Cifuentes¹,

Muñóz²,

Monge³

et al. 2013

Journal of Nuclear Materials

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Abstract:The oxidation resistance in dry air of pure tungsten and tungsten reinforced with a dispersion of 0.6 wt.%Y 2 O 3 nanoparticles has been evaluated between 873 and 1073 K, temperature range that divertor in fusion power plants should endure during long-term times in the case of loss of coolant accident and/or air ingress in the vessel. Both materials were prepared by a powder metallurgy route involving hot iso-static pressing of ball milled tungsten powders and tungsten with dispersed Y 2 O 3 nanoparticles. The results have been compared with those of pure tungsten processed by conventional techniques. Thermo-gravimetric tests at 873 K revealed that the processing route as well as yttria addition considerably affected the oxidation resistance of pure tungsten. Mass gain of W-0.6Y 2 O 3 at 873 K was five and two times lower than that of pure tungsten prepared by conventional processing techniques and by powder metallurgy, respectively. This different behavior was related to changes in the structure and composition of the oxide scale. Above 873 K, the kinetics were significantly accelerated for all materials due to the development of a non-protective oxide scale from the earliest oxidation stages, although the kinetics of Y 2 O 3 -containing material were still the slowest, specially at 973 K. It was analyzed how yttria additions modify the oxidation mechanism of tungsten.

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Plasma‐material Interactions Problems and Dust Creation and Re‐suspension in Case of Accidents in Nuclear Fusion Plants: A New Challenge for Reactors like ITER and DEMO

Malizia

Poggi

Ciparisse

et al. 2016

Advanced Surface Engineering Materials

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Given the urgent need to converge on precise guidelines for accident management\ud in nuclear fusion plants, in this paper, the authors will analyze the problem\ud related to the choice of possible candidate materials for the nuclear fusion plants\ud like International Thermonuclear Experimental Reactor (ITER), DEMOnstration\ud power plant (DEMO), or PROTOtype power plant (PROTO). Fusion power is\ud a promising long-term candidate to supply the energy needs of humanity. From\ud the safety point of view, nuclear fusion holds inherent and potential safety advantages\ud over other energy sources. In magnetic confinement devices, the plasma\ud edge and surrounding material surfaces provide a buffer zone between the hightemperature\ud conditions in the plasma core and the normal “terrestrial” environment.\ud The interaction between the plasma edge and the surrounding surfaces\ud profoundly influences the conditions in the plasma core and is the principal key\ud engineering issue. Robust solutions to plasma–material interactions (PMIs) issues\ud are required to realize a commercially attractive fusion reactor. PMIs critically\ud affect tokamak operation in many ways. Erosion by the plasma determines the\ud lifetime of plasma-facing components (PFCs) and generates a source of impurities,which cool and dilute the plasma. Deposition of material onto PFCs alters their\ud surface composition and can lead to long-term accumulation of large in-vessel\ud tritium inventories. Retention and recycling of hydrogen from PFCs affect fueling\ud efficiency, plasma density control, and the density of neutral hydrogen in the\ud plasma boundary, which impacts particle and energy transport. Dusts are currently\ud produced in the existing plants like JET (and will also be in the future ones\ud like ITER, DEMO, and PROTO) by PMIs. Thus, the issues related to the PFCs of\ud the first wall of the nuclear fusion plants area topic that the Quantum Electronics\ud and Plasma Physics Research Group have been studying for more than a decade.\ud Regarding the selection of PFCs, there are two strong school of thoughts that\ud work on fusion plants materials for the first wall: (1) one composed by experts\ud working mainly on nuclear fusion and that are focusing their attention on certain\ud materials (like tungsten, beryllium, carbon, tritium, stainless steel, and other),\ud and (2) the other one composed of experts working mainly on the fission plants\ud that want to demonstrate the “dual-use” characteristics of the “fission materials”\ud for fusion plants applications. In this review paper, the authors will (1) review\ud both the approaches mentioned above comparing the main characteristics of all\ud the proposed and tested materials, (2) analyze the consequences (experimentally\ud revealed and numerically predicted) of PMIs that provokes serious damages to the\ud plants and dangerous consequences like radioactive/toxic dust production, and\ud (3) analyze (also thanks to our experimental activities on STARDUST-Upgrade\ud facility) the risks (for th...

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Review on the EFDA programme on tungsten materials technology and science

Cited by 160 publications

References 14 publications

On the oxidation mechanism of pure tungsten in the temperature range 600–800°C

On the oxidation mechanism of pure tungsten in the temperature range 600–800°C

Influence of processing route and yttria additions on the oxidation behavior of tungsten

Plasma‐material Interactions Problems and Dust Creation and Re‐suspension in Case of Accidents in Nuclear Fusion Plants: A New Challenge for Reactors like ITER and DEMO

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