Transmutation and induced radioactivity of W in the armor and first wall of fusion reactors

Noda, Tetsuji; Fujita, Masaya; Okada, Masatoshi

doi:10.1016/s0022-3115(98)00088-9

Cited by 48 publications

(21 citation statements)

References 3 publications

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“…The nominal compositions of the examined alloys are shown in Table 1. They were selected basing compositional change predicted by calculation of transmutation 1) in the solid solution area of W-xReyOs alloys. Model alloy fabrications were carried out using an argon arc furnace.…”

Section: Methodsmentioning

confidence: 99%

Precipitation of Solid Transmutation Elements in Irradiated Tungsten Alloys

et al. 2008

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Tungsten-based model alloys were fabricated to simulate compositional changes by neutron irradiation, performed in the JOYO fast test reactor. The irradiation damage range was 0.17-1.54 dpa and irradiation temperatures were 400, 500 and 750 C. After irradiation, microstructural observations and electrical resistivity measurements were carried out. A number of precipitates were observed after 1.54 dpa irradiation. Rhenium and osmium were precipitated by irradiation, which suppressed the formation of dislocation loops and voids. Structures induced by irradiation were not observed so much after 0.17 dpa irradiation. Electrical resistivity measurements showed that the effects of osmium on the electrical resistivity, related to impurity solution content, were larger than that of rhenium. Measurements of electrical resistivity of ternary alloys showed that the precipitation behavior was similar to that in binary alloys.

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Section: Methodsmentioning

confidence: 99%

Precipitation of Solid Transmutation Elements in Irradiated Tungsten Alloys

et al. 2008

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“…Furthermore, irradiation of W with fusion neutrons creates several radioactive isotopes of tungsten and rhenium (Re). There has been a number of studies trying to predict the amount of Re accumulated in W during fusion power plant operation [1][2][3][4]. The most recent forecast by Gilbert and Sublet [4] gives 0.18 at.% of Re for 14 years of ITER operation and 3.8 at.% of Re for 5 years of DEMO operation.…”

Section: Introductionmentioning

confidence: 99%

“…For W materials exposed to low-energy, high flux hydrogen plasmas, local plastic deformation caused by hydrogen super-saturation within the nearsurface layer [8] is suggested as a mechanism for formation of intergranular and intragranular cracks, and, at long-term plasma exposure, for gas-filled void formation at depths up to several micrometers and, as consequence, for blistering [9][10][11]. It is known that an addition of Re not only improves the low temperature ductility of the tungsten material, but also increases 1 The term 'low-energy ions' means that the ion energy is below the displacement threshold. 2 its high temperature creep strength 2 [12][13][14].…”

Section: Introductionmentioning

confidence: 99%

Surface morphology and deuterium retention in tungsten and tungsten–rhenium alloy exposed to low-energy, high flux D plasma

Alimov

Hatano

Sugiyama

et al. 2014

Journal of Nuclear Materials

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Surface topography and deuterium retention in polycrystalline warm-rolled W and W-5%Re depending on the exposure temperature, are formed on the W and W-5%Re surfaces. In the W-5%Re, the deuterium retention demonstrates its maximum at exposure temperature of 463 K, while in the W this maximum is shifted to 523 K. A difference in the temperature dependence of the D retention for the W and W-5%Re is explained, as a rough approximation, by temperature dependences of the ductility of these materials.

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“…7) Nuclear transmutation resulting from high-fluence neutron irradiation is also predicted to occur in a fusion reactor. 8) Rhenium (Re) is one of the major solid transmutation elements of W. Bolt et al predicted that the Re concentration and displacement damage of pure W in a DEMO reactor would be 6% and 30 displacement per atom (dpa), respectively, at the first wall and 3% and 15 dpa, respectively, at the divertor during five year operation period.…”

Section: Introductionmentioning

confidence: 99%

Effects of Re Content and Fabrication Process on Microstructural Changes and Hardening in Neutron Irradiated Tungsten

et al. 2012

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The effects of the material fabrication process and rhenium (Re) content on the irradiation-induced changes in the microstructure and hardness of pure tungsten (W) and WRe alloys were investigated. Neutron irradiation of pure W and WRe alloys (Re concentration 326%) was carried out in the experimental fast reactor JOYO. The irradiation conditions were 0.44 displacement per atom (dpa) at 531°C and 0.47 dpa at 583°C for pure W and WRe alloys, respectively. After irradiation, microstructural observations using a transmission electron microscope (TEM) and Vickers microhardness tests were performed.Voids and dislocation loops were observed in both pure W and WRe alloys after irradiation. The number density of voids in pure W was higher than that in W3%Re, W5%Re and W10%Re. Only in the case of W26%Re irradiated to 0.47 dpa at 583°C were there no voids observed, but irradiation-induced fine precipitates and a few dislocation loops were observed. The irradiation hardening of pure W was greater than that of the WRe alloys. It was considered that irradiation hardening of pure W was caused mainly by the higher number density of voids. The addition of Re suppressed void formation and irradiation hardening of the WRe alloys. Irradiation hardening of W was also suppressed in hot-rolled W compared with arc-melted as-cast W.

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Transmutation and induced radioactivity of W in the armor and first wall of fusion reactors

Cited by 48 publications

References 3 publications

Precipitation of Solid Transmutation Elements in Irradiated Tungsten Alloys

Precipitation of Solid Transmutation Elements in Irradiated Tungsten Alloys

Surface morphology and deuterium retention in tungsten and tungsten–rhenium alloy exposed to low-energy, high flux D plasma

Effects of Re Content and Fabrication Process on Microstructural Changes and Hardening in Neutron Irradiated Tungsten

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