Swelling in neutron irradiated tungsten and tungsten-25 percent rhenium

Matolich, J.; Nahm, H.; Moteff, J.

doi:10.1016/0036-9748(74)90304-4

Cited by 88 publications

(49 citation statements)

References 8 publications

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“…Our results indicate that Re establishes attractive interactions with both vacancies and self interstitials. These results are in very good agreement with the general finding that under irradiation, radiation induced precipitation of WRe alloys are observed [19][20][21][22] even if it needs to be comforted by the determination of the corresponding migration energies.…”

Section: Reactionsupporting

confidence: 92%

An object Kinetic Monte Carlo Simulation of the dynamics of helium and point defects in tungsten

Becquart¹,

Domain²

2009

Journal of Nuclear Materials

173

127

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Section: Reactionsupporting

confidence: 92%

An object Kinetic Monte Carlo Simulation of the dynamics of helium and point defects in tungsten

Becquart¹,

Domain²

2009

Journal of Nuclear Materials

173

127

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“…However, at <0.01%, our calculations yield swelling levels in pure W that are very low, of the order of three orders of magnitude lower than those measured experimentally in similar conditions [5]. Peak swelling in our calculations is attained in the 550∼600 • C interval, below experimental measurements of around 800 • C. Moreover, in our calculations we find that swelling and hardening abruptly decrease after 600 • C, irrespective of conditions.…”

Section: Discussionmentioning

confidence: 36%

“…Indeed, irradiations in EBR-II up to 9 dpa have revealed the absence of swelling in W-25%Re [5] and W-10%Re [6] compared to values of close to 2% in pure W. Matolich measured the temperature at which peak swelling occurs in pure W at approximately 750 • [5]. In a series of recent papers, Hasegawa and collaborators have shown that Re precipitation suppresses void and dislocation loop density accumulation and size growth [7,8,9], although they observe that subsaturated Re precipitation above 1 dpa gives rise to very dramatic hardening increases.…”

Section: Introductionmentioning

confidence: 99%

Modeling fast neutron irradiation damage accumulation in tungsten

Marian

Hoang

2012

Journal of Nuclear Materials

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Due to its advantageous physical properties, tungsten (W) is being considered as a candidate structural material in fusion applications. In this paper, we perform stochastic cluster dynamics calculations of irradiation damage accumulation in pure W under fast neutron spectra in up to doses of 1.5 dpa in the 400∼600 • C interval. Our calculations suggest that He bubbles and dislocation loops accumulate under fusion conditions, but not under fast fission spectra. We study the temperature dependence of swelling and find that it is maximum in the 550∼590 • C temperature range, falling precipitously above 600 • C. Swelling levels are very low, never surpassing a fraction of a percentage point. We also provide hardening estimates based on the accumulation of sessile dislocation loops under fusion conditions and show that they are moderate, ranging between 70 and 137 MPa at 400 • C.

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“…1) As a result of neutron irradiation, the microstructure and material properties change because of displacement damage and nuclear transmutation. Several researchers have studied the effects of irradiation on W. For example, void swelling, 2,3) irradiation hardening, 46) and an increase in the ductilebrittle transition temperature (DBTT) after fission-neutron irradiation have been reported. 7) Nuclear transmutation resulting from high-fluence neutron irradiation is also predicted to occur in a fusion reactor.…”

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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Swelling in neutron irradiated tungsten and tungsten-25 percent rhenium

Cited by 88 publications

References 8 publications

An object Kinetic Monte Carlo Simulation of the dynamics of helium and point defects in tungsten

An object Kinetic Monte Carlo Simulation of the dynamics of helium and point defects in tungsten

Modeling fast neutron irradiation damage accumulation in tungsten

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

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