Experimental results on the irradiation of nuclear fusion relevant materials at the dense plasma focus 'Bora' device

Samples of materials counted as perspective ones for use in the first-wall and construction elements in nuclear fusion reactors (FRs) with magnetic and inertial plasma confinement (W, Ti, Al, low-activated ferritic steel 'Eurofer' and some alloys) were irradiated in the dense plasma focus...

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Veröffentlicht in:Nuclear fusion 2015-06, Vol.55 (6), p.63037-7
Hauptverfasser: Cicuttin, A., Crespo, M.L., Gribkov, V.A., Niemela, J., Tuniz, C., Zanolli, C., Chernyshova, M., Demina, E.V., Latyshev, S.V., Pimenov, V.N., Talab, A.A.
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container_end_page 7
container_issue 6
container_start_page 63037
container_title Nuclear fusion
container_volume 55
creator Cicuttin, A.
Crespo, M.L.
Gribkov, V.A.
Niemela, J.
Tuniz, C.
Zanolli, C.
Chernyshova, M.
Demina, E.V.
Latyshev, S.V.
Pimenov, V.N.
Talab, A.A.
description Samples of materials counted as perspective ones for use in the first-wall and construction elements in nuclear fusion reactors (FRs) with magnetic and inertial plasma confinement (W, Ti, Al, low-activated ferritic steel 'Eurofer' and some alloys) were irradiated in the dense plasma focus (DPF) device 'Bora' having a bank energy of 5 kJ. The device generates hot dense (T ∼ 1 keV, n ∼ 1019 cm−3) deuterium plasma, powerful plasma streams (v ∼ 3 × 107 cm s−1) and fast (E ∼ 0.1 ... 1.0 MeV) deuterons of power flux densities q up to 1010 and 1012 W cm−2 correspondingly. 'Damage factor' F = q × τ0.5 ensures an opportunity to simulate radiation loads (predictable for both reactors types) by the plasma/ion streams, which have the same nature and namely those parameters as expected in the FR modules. Before and after irradiation we provided investigations of our samples by means of a number of analytical techniques. Among them we used optical and scanning electron microscopy to understand character and parameters of damageability of the surface layers of the samples. Atomic force microscopy was applied to measure roughness of the surface after irradiation. These characteristics are quite important for understanding mechanisms and values of dust production in FR that may relate to tritium retention and emergency situations in FR facilities. We also applied two new techniques. For the surface we elaborated the portable x-ray diffractometer that combines x-ray single photon detection with high spectroscopic and angular resolutions. For bulk damageability investigations we applied an x-ray microCT system where x-rays were produced by a Hamamatsu microfocus source (150 kV, 500 µA, 5 µm minimum focal spot size). The detector was a Hamamatsu CMOS flat panel coupled to a fibre optic plate under the GOS scintillator. The reconstruction of three-dimensional data was run with Cobra 7.4 and DIGIX CT software while VG Studio Max 2.1, and Amira 5.3 were used for segmentation and rendering. We have also provided numerical simulation of the fast ion beam action. The paper contains results on the investigations of modifications of the elemental contents, structure and properties of the materials.
doi_str_mv 10.1088/0029-5515/55/6/063037
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The device generates hot dense (T ∼ 1 keV, n ∼ 1019 cm−3) deuterium plasma, powerful plasma streams (v ∼ 3 × 107 cm s−1) and fast (E ∼ 0.1 ... 1.0 MeV) deuterons of power flux densities q up to 1010 and 1012 W cm−2 correspondingly. 'Damage factor' F = q × τ0.5 ensures an opportunity to simulate radiation loads (predictable for both reactors types) by the plasma/ion streams, which have the same nature and namely those parameters as expected in the FR modules. Before and after irradiation we provided investigations of our samples by means of a number of analytical techniques. Among them we used optical and scanning electron microscopy to understand character and parameters of damageability of the surface layers of the samples. Atomic force microscopy was applied to measure roughness of the surface after irradiation. These characteristics are quite important for understanding mechanisms and values of dust production in FR that may relate to tritium retention and emergency situations in FR facilities. We also applied two new techniques. For the surface we elaborated the portable x-ray diffractometer that combines x-ray single photon detection with high spectroscopic and angular resolutions. For bulk damageability investigations we applied an x-ray microCT system where x-rays were produced by a Hamamatsu microfocus source (150 kV, 500 µA, 5 µm minimum focal spot size). The detector was a Hamamatsu CMOS flat panel coupled to a fibre optic plate under the GOS scintillator. The reconstruction of three-dimensional data was run with Cobra 7.4 and DIGIX CT software while VG Studio Max 2.1, and Amira 5.3 were used for segmentation and rendering. We have also provided numerical simulation of the fast ion beam action. 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Fusion</addtitle><date>2015-06-01</date><risdate>2015</risdate><volume>55</volume><issue>6</issue><spage>63037</spage><epage>7</epage><pages>63037-7</pages><issn>0029-5515</issn><eissn>1741-4326</eissn><coden>NUFUAU</coden><abstract>Samples of materials counted as perspective ones for use in the first-wall and construction elements in nuclear fusion reactors (FRs) with magnetic and inertial plasma confinement (W, Ti, Al, low-activated ferritic steel 'Eurofer' and some alloys) were irradiated in the dense plasma focus (DPF) device 'Bora' having a bank energy of 5 kJ. The device generates hot dense (T ∼ 1 keV, n ∼ 1019 cm−3) deuterium plasma, powerful plasma streams (v ∼ 3 × 107 cm s−1) and fast (E ∼ 0.1 ... 1.0 MeV) deuterons of power flux densities q up to 1010 and 1012 W cm−2 correspondingly. 'Damage factor' F = q × τ0.5 ensures an opportunity to simulate radiation loads (predictable for both reactors types) by the plasma/ion streams, which have the same nature and namely those parameters as expected in the FR modules. Before and after irradiation we provided investigations of our samples by means of a number of analytical techniques. Among them we used optical and scanning electron microscopy to understand character and parameters of damageability of the surface layers of the samples. Atomic force microscopy was applied to measure roughness of the surface after irradiation. These characteristics are quite important for understanding mechanisms and values of dust production in FR that may relate to tritium retention and emergency situations in FR facilities. We also applied two new techniques. For the surface we elaborated the portable x-ray diffractometer that combines x-ray single photon detection with high spectroscopic and angular resolutions. For bulk damageability investigations we applied an x-ray microCT system where x-rays were produced by a Hamamatsu microfocus source (150 kV, 500 µA, 5 µm minimum focal spot size). The detector was a Hamamatsu CMOS flat panel coupled to a fibre optic plate under the GOS scintillator. The reconstruction of three-dimensional data was run with Cobra 7.4 and DIGIX CT software while VG Studio Max 2.1, and Amira 5.3 were used for segmentation and rendering. We have also provided numerical simulation of the fast ion beam action. The paper contains results on the investigations of modifications of the elemental contents, structure and properties of the materials.</abstract><pub>IOP Publishing</pub><doi>10.1088/0029-5515/55/6/063037</doi><tpages>7</tpages></addata></record>
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source IOP Publishing Journals; Institute of Physics (IOP) Journals - HEAL-Link
subjects Aluminum
Damage
dense plasma focus 'Bora'
Dense plasmas
Devices
Inertial
Irradiation
materials for nuclear fusion reactor
Nuclear fusion
Nuclear reactor components
radiation tests
surface and bulk damageability
title Experimental results on the irradiation of nuclear fusion relevant materials at the dense plasma focus 'Bora' device
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