Neutron irradiation hardening across ITER diverter tungsten armor

Terentyev, D.; Yin, Chuntao; Dubinko, A.; Chang, Chih‐Cheng; You, J.H.

doi:10.1016/j.ijrmhm.2020.105437

Cited by 22 publications

(18 citation statements)

References 64 publications

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“…This shift is much higher than what is observed here for the samples irradiated up to 0.44-0.67 dpa (being around 300 °C), which can naturally be explained by three reasons: (i) lower dpa damage; (ii) lower amount of transmuted Re and Os; (iii) lower irradiation temperature. The latter factor may play an important role as the results of the hardness tests show that the maximum increase of the hardness occurs at 800 °C [49], which coincides with the peak swelling temperature as well as it goes in line with the theoretical assessments showing that voids are stronger obstacles than dislocation loops (preferentially forming under irradiation below 800 °C) [48].…”

Section: Fracture Toughnesssupporting

confidence: 79%

“…From the set of results presented for the IGP material, we can see that the maximum hardness takes place at 1000 °C. In fact, our earlier study [49] shows that the peak of the hardness is located in the 800-1000 °C temperature region, which corresponds to the peak of the voids swelling. The void growth is limited at T irr below 600 °C, while intensive void coarsening takes place above 1000 °C.…”

Section: Hardness Testsmentioning

confidence: 82%

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Neutron irradiation effects on mechanical properties of ITER specification tungsten

et al. 2021

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In this contribution, we present the results of recent neutron irradiation campaign performed in the material test reactor BR2 (Belgium) on pure tungsten. We have applied various irradiation conditions and sample geometry to assess the effect of neutron irradiation on hardness, bending, tensile and fracture mechanical properties. The investigated material is a commercially pure tungsten plate fabricated according to the international thermonuclear experimental reactor (ITER) specification for the application in the divertor plasma-facing components. The neutron irradiation covers a large span of temperatures and damage doses, ranging from 600 to 1200 °C and 0.1-1 dpa. The obtained mechanical properties were analyzed to deduce the shift of the ductile to brittle transition temperature (DBTT) applying bending, tensile and fracture toughness-testing procedures. Then, a correlation of the fracture toughness with the change of the hardness was established. The obtained results are compared with the already published results on another ITER specification grade produced in the form of a rod. The presented and discussed results show that the performance of the compared grades in terms of the irradiation-induced embrittlement is similar, and that the irradiation in the high-temperature region (600-800 °C) causes a considerable DBTT shift already at 0.2-0.5 dpa.

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Section: Fracture Toughnesssupporting

confidence: 79%

Section: Hardness Testsmentioning

confidence: 82%

Neutron irradiation effects on mechanical properties of ITER specification tungsten

et al. 2021

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“…The microstructure of “as-delivered” material was detailed characterized and published in refs. 15 , 26 . The investigated tungsten shows an average grain structure with a size of 88 µm.…”

Section: Resultsmentioning

confidence: 99%

New insights into microstructure of neutron-irradiated tungsten

Dürrschnabel

Klimenkov

Jäntsch

et al. 2021

Sci Rep

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The development of appropriate materials for fusion reactors that can sustain high neutron fluence at elevated temperatures remains a great challenge. Tungsten is one of the promising candidate materials for plasma-facing components of future fusion reactors, due to several favorable properties as for example a high melting point, a high sputtering resistivity, and a low coefficient of thermal expansion. The microstructural details of a tungsten sample with a 1.25 dpa (displacements per atom) damage dose after neutron irradiation at 800 °C were examined by transmission electron microscopy. Three types of radiation-induced defects were observed, analyzed and characterized: (1) voids with sizes ranging from 10 to 65 nm, (2) dislocation loops with a size of up to 10 nm and (3) W–Re–Os containing σ- and χ-type precipitates. The distribution of voids as well as the nature of the occurring dislocation loops were studied in detail. In addition, nano-chemical analyses revealed that the σ- and χ-type precipitates, which are sometimes attached to voids, are surrounded by a solid solution cloud enriched with Re. For the first time the crystallographic orientation relationship of the σ- and χ-phases to the W-matrix was specified. Furthermore, electron energy-loss spectroscopy could not unambiguously verify the presence of He within individual voids.

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“…The microstructure of "as-delivered" material was detailed characterized and published in refs. 16,17 . The investigated tungsten shows an average grain structure with a size of 88µm.…”

Section: Resultsmentioning

confidence: 99%

New microstructural insights into neutron-irradiated tungsten

Dürrschnabel¹,

Klimenkov²,

Jäntsch³

et al. 2020

Preprint

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The development of appropriate materials for fusion reactors that can sustain high neutron fluencies at elevated temperatures remains a great challenge. Tungsten is one of the promising candidate materials for plasma-facing components of future fusion reactors, due to several favorable properties as for example a high melting point, a high sputtering resistivity, and a low coefficient of thermal expansion. The microstructural details of a tungsten sample with a 1.25 dpa (displacements per atom) damage dose after irradiation at 800°C were examined by transmission electron microscopy (TEM). Three types of radiation-induced defects were observed, analyzed and characterized: (i) voids with sizes ranging from 10 nm to 65 nm, (ii) dislocation loops with a size of up to 10 nm and (iii) W-Re-Os containing σ- and χ-type precipitates. The distribution of voids as well as the nature of the occurring dislocation loops were studied in detail. In addition, nano-chemical analyses revealed that the σ- and χ-type precipitates, which are sometimes attached to voids, are surrounded by a solid solution cloud enriched with Re. For the first time the crystallographic orientation relationship of the σ- and χ-phases to the W-matrix was specified. Furthermore, electron energy-loss spectroscopy could not unambiguously verify the presence of He within individual cavities.

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Neutron irradiation hardening across ITER diverter tungsten armor

Cited by 22 publications

References 64 publications

Neutron irradiation effects on mechanical properties of ITER specification tungsten

Neutron irradiation effects on mechanical properties of ITER specification tungsten

New insights into microstructure of neutron-irradiated tungsten

New microstructural insights into neutron-irradiated tungsten

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