Helium and hydrogen release measurements on various alloys irradiated in SINQ

Oliver, B.M.; Dai, Yong; Causey, R.A.

doi:10.1016/j.jnucmat.2006.05.025

Cited by 27 publications

(12 citation statements)

References 8 publications

(11 reference statements)

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“…These types of peak shift on hydrogen gas release behavior for high energy proton irradiated F82H alloy was also seen on the former studies on gas release measurement and microstructural investigation of STIP irradiated materials [5,6]. According to these studies, the desorption stage which should be attributed to the release of hydrogen gases from helium babbles appears more clearly on the specimens irradiated to 20.3 dpa at around 400°C where formation of high-density small helium bubbles occurs, compared to that irradiated to the lower dose of 10 dpa at around 100°C where no visible helium bubble formation was observed, which consequently appears as a peak shift.…”

Section: Deuterium Trapping Behavior On He Irradiated Specimenssupporting

confidence: 77%

The trapping behavior of deuterium in F82H ferritic/martensitic steel

Hamaguchi

Iwakiri

Kawamura

et al. 2009

Journal of Nuclear Materials

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For the development of fusion reactor materials, the characterization of trapping and releasing behavior of hydrogen and its isotopes is one of the key issues considering the influences on plasma parameters and tritium inventory.Low activated F82H ferritic/martensitic steel is one of a candidate alloys for the first wall of fusion reactors as well as for the beam window of spallation target for ADS. In this study, trapping behavior of deuterium in F82H under low energy helium irradiation was studied by means of thermal desorption spectrometry (TDS) and TEM in order to characterize the trapping behavior of deuterium on irradiated materials.The reduced activated F82H ferritic/martensitic steel used in this study was IEA-heat 4-20 prepared for Japanese fusion reactor material program. The samples with a dimension of 6�10mm were mechanically cut to the thickness of around 2mm. Then the surfaces of the samples were mechanically polished up to buff polishing with 0.03�m colloidal silica for low energy ion irradiations. Some samples were prepared from a tempered material at 790 ºC for 30 minutes in order to reduce the influence of deuterium trapping by dislocations for comparison with the normalized materials. The tempering condition was estimated form former studies. Low energy helium and deuteron irradiations were performed at Research Institute for Applied Mechanics, Kyushu University. The specimens were first irradiated with 5keV He + ions at 600ºC followed by the additional irradiations with 0.5keV D 2 + ions at RT. The deuteron irradiation energy of 0.5keV is that without any introduction of displacement damage into Fe-based alloys.After the irradiations, thermal desorption of D 2 and He under heating with a ramping rate of 1 K/s were measured with high resolution quadruple mass spectrometer. This high resolution spectrometer enables to distinguish slight differences in the mass between He (m=4.0026) atom and D 2 (m=4.0282) gas. The desorption rates of He and D 2 were quantitatively calibrated by using standard He leak with specific relative ionization efficiency. At the same time, the samples for the microstructural study by TEM were prepared using focused ion beam system (FIB) from the same specimens.Thermal desorption spectra of deuterium from tempered and normalized specimens are given in fig.1. Note that the deuterium ion irradiation was carried out with very low energy of 0.5keV, where no displacement damage will be introduced in Fe-based alloys. The microstructures for these specimens are shown in fig.2. There were two desorption stages for deuterium observed for F82H. One appears between the temperatures from 350K to 500K and the other from around 800K to 1000K. These stages were seen on both tempered and normalized specimens. Desorption stage at lower temperature is typical for Fe-Cr based alloy. This stage is assumed to be a release of deuterium mainly trapped on dislocations, since the stage also appears on the cold worked Fe-9Cr alloy though it disappears after annealing. On the other hand, the stage ...

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Section: Deuterium Trapping Behavior On He Irradiated Specimenssupporting

confidence: 77%

The trapping behavior of deuterium in F82H ferritic/martensitic steel

Hamaguchi

Iwakiri

Kawamura

et al. 2009

Journal of Nuclear Materials

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“…The irradiation parameters such as proton and neutron fluences, displacement damage (dpa) and helium (He) and hydrogen (H) values were calculated with the MCNPX code using the profile of the accumulated proton fluence evaluated by gammamapping performed on the beam entrance area of the AlMg 3 container. To validate the calculated values, He and H contents were measured from a number of specimens at the Pacific Northwest National Laboratory (USA) [4,5]. The results indicated that the measured He values agreed roughly with the calculated ones.…”

Section: Irradiationmentioning

confidence: 73%

Stressed capsules of austenitic and martensitic steels irradiated in SINQ Target-4 in contact with liquid lead–bismuth eutectic

Dai

Gavillet

Restani

2008

Journal of Nuclear Materials

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“…The proton and neutron fluences received by each specimen, the corresponding dpa values and helium and hydrogen concentrations are calculated with the MCNPX code using this distribution profile. The calculated He concentrations have been corrected based on gas measurements performed at the Pacific Northwest National Laboratory, USA [10,11]. The H concentration cannot be well reproduced because the measured H values show large differences from the calculated values.…”

Section: Stip Irradiation Conditionsmentioning

confidence: 99%