Radiation-induced defect clusters in fully stabilized zirconia irradiated with ions and/or electrons

Yasuda, Kazuhiro; Kinoshita, Chiken; Matsumura, Shuichi; Ryazanov, A. I.

doi:10.1016/s0022-3115(03)00136-3

Cited by 56 publications

(35 citation statements)

References 25 publications

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“…Yasuda et al 22 studied this microstructure change mechanism and concluded, based on earlier works from Baufeld et al, 42 that defects created in the first stage of the irradiation process are seeds for dislocation loops. More precisely, the following mechanism was proposed: 22,42 It is worth mentioning that the mechanism for the transformation of partial into perfect dislocation loops has also been reported in irradiated ceria (see Ref. 43 and references therein).…”

Section: à2mentioning

confidence: 98%

“…43 and references therein). Both Baufeld et al 42 and Yasuda et al 22 postulated the existence of a critical defect size above which the actual defect is not stable anymore and turn into a new, stable one. This assumption has been supported by a theoretical model developed by Ryazanov et al 44 taking into account the charge state of the dislocation loops to explain their instability (hence their transformation into dislocation lines) above a critical size.…”

Section: à2mentioning

confidence: 99%

“…temperature (RT) and only very few studies were devoted to the investigation of the damage produced above RT. 15,21,22 Exceptions are the works that dealt with the particular topic of gas bubble precipitation. 23,24 The present paper aims at studying the effect of the irradiation temperature on the behavior of cubic zirconia.…”

Section: Introductionmentioning

confidence: 99%

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Comprehensive study of the effect of the irradiation temperature on the behavior of cubic zirconia

Debelle

Channagiri

Thomé

et al. 2014

Journal of Applied Physics

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High-temperature stability of ion-implanted zirconia and spinel J. Appl. Phys. 97, 113509 (2005) ) and at five temperatures: 80, 300, 573, 773, and 1073 K. Irradiated samples have been characterized by Rutherford backscattering spectroscopy in channeling mode, X-ray diffraction and transmission electron microscopy techniques in order to determine the disordering kinetics. All experimental results show that, whatever is the irradiation temperature, the damage build-up follows a multi-step process. In addition, the disorder level at high fluence is very similar for all temperatures. Thus, no enhanced dynamic annealing process is observed. On the other hand, transitions in the damage accumulation process occur earlier in fluence with increasing temperature. It is shown that temperature as low as 573 K is sufficient to accelerate the disordering process in ion-irradiated YSZ. V C 2014 AIP Publishing LLC. [http://dx

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Section: à2mentioning

confidence: 98%

Section: à2mentioning

confidence: 99%

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Comprehensive study of the effect of the irradiation temperature on the behavior of cubic zirconia

Debelle

Channagiri

Thomé

et al. 2014

Journal of Applied Physics

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“…Zirconia-based PuIMFs have achieved plutonium consumption rates of up to 142 kg/TWhe, although the thermal conductivity of zirconia-based fuel is less than half that of UO 2 [5]. [8][9][10][11][12][13][14]. Its excellent neutronic properties have lead to its use in the reflector segments of the Belgium MYRRHA accelerator driven system (ADS) for minor actinide transmutation [15].…”

Section: Introductionmentioning

confidence: 99%

Krypton and Helium Irradiation Damage in Yttria-stabilised Zirconia

et al. 2011

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A candidate matrix material for inert matrix fuel (IMF), yttria-stabilised zirconia (YSZ) has been doped with Nd 3+ as a surrogate for Pu 3+ . In order to simulate and asses the effects of fission gas accommodation and alpha decay on the microstructure, samples of (Y 0.1425 . Monte Carlo simulations using the TRIM code show that it is only at these fluences that the level of atomic displacements is sufficient to result in defect formation within the material.

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“…Out-of pile irradiation studies designed to understand the mechanism of radiation damage have been completed [6]. Neutronic feasibility of YSZ-based IMF has been also assessed [7] complemented by core burnup calculations and accident analyses [8].…”

Section: Introductionmentioning

confidence: 99%

Fabrication and characterization of dual phase magnesia–zirconia ceramics doped with plutonia

Medvedev

Jue

Frank

et al. 2006

Journal of Nuclear Materials

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Dual phase magnesia-zirconia ceramics doped with plutonia are being studied as an inert matrix fuel (IMF) for light water reactors. The motivation of this work is to develop an IMF with a thermal conductivity superior to that of the fuels based on yttria stabilized zirconia. The concept uses the MgO phase as an efficient heat conductor to increase thermal conductivity of the composite. In this paper ceramic fabrication and characterization by scanning electron microscopy, energy and wavelength dispersive xray spectroscopy is discussed. Characterization shows that the ceramics consist of the two-phase matrix and PuO 2 -rich inclusions. The matrix is comprised of pure MgO phase and MgO-ZrO 2 -PuO 2 solid solution. The PuO 2 -rich inclusion contained dissolved MgO and ZrO 2 .

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Radiation-induced defect clusters in fully stabilized zirconia irradiated with ions and/or electrons

Cited by 56 publications

References 25 publications

Comprehensive study of the effect of the irradiation temperature on the behavior of cubic zirconia

Comprehensive study of the effect of the irradiation temperature on the behavior of cubic zirconia

Krypton and Helium Irradiation Damage in Yttria-stabilised Zirconia

Fabrication and characterization of dual phase magnesia–zirconia ceramics doped with plutonia

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