Effect of elastic collisions on acoustic wave propagation in simplified nuclear glass: Molecular dynamics simulation

Deladerrière, N.; Delaye, Jean‐Marc; Peuget, S.; Bureau, G.

doi:10.1016/j.nimb.2008.03.100

Cited by 6 publications

(8 citation statements)

References 9 publications

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“…BS3 glass specimens were also irradiated with 135 MeV 18 O ions up to a fluence of 4×10 13 ions cm -2 (~2.5×10 20 keV.cm -3 ~ 16 MGy ~ 3.6 eV/atom). No visible structural modifications and no changes in the mechanical properties were observed [44].…”

Section: Resultsmentioning

confidence: 99%

“…Similarly, studies have shown that the hardness and elastic modulus decrease and finally saturate with alpha decay accumulation. Usually, the irradiation-induced changes saturate after an accumulation of about 2×10 18 to 5×10 18 alpha decays per gram (nuclear dose of about 3×10 20 to 7×10 20 keV.cm -3 ) [3,14,17]. By varying the actinide doping concentration in the range of 0.04 to 3.25 wt.…”

Section: 4mentioning

confidence: 99%

“…The role of alpha particles in damage accumulation is believed to be negligible. Furthermore, Molecular dynamics (MD) simulations of simple borosilicate glasses subjected to displacement cascades [18][19][20][21][22][23] have shown that NCs result in swelling, modulus decrease, boron coordination change (transformation of BO4 to BO3) and network depolymerization -all of which tend to saturation after about 4×10 20 keV.cm -3 (~ 26 MGy ~ 6 eV/atom) in good agreement with actinide doping studies [15,16]. This further lends support to the inference that NCs will control the long-term evolution of waste packages.…”

Section: 4mentioning

confidence: 99%

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Using external ion irradiations for simulating self-irradiation damage in nuclear waste glasses: State of the art, recommendations and, prospects

Mir

Peuget

2020

Journal of Nuclear Materials

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Due to the complexities associated with handling and characterizing the radiation damage in radioactive materials such as nuclear waste forms, ion irradiation has been widely used to simulate the effects of the selfirradiation damage. This often involves ion irradiation of nuclear waste surrogate glasses using ion accelerators. Such facilities allow using a wide range of ion types ranging from H to U and energies from tens of keV to hundreds of MeV. For various reasons, the researchers often have to use ions and energies that do not necessarily match with what is expected in actual nuclear waste forms. Due to a lack of detailed and dedicated studies, there are currently no guidelines or consensus regarding the use of the ion irradiation as a means of simulating the self-irradiation damage. The purpose of this article is to delve into this subject by presenting systematic studies of a number of glasses carried out in the last decade or so. By doing so, guidelines and easy to follow ion-mass Vs ion energy contour maps are provided to best simulate the long-term radiation damage in nuclear waste forms. We also discuss how the ions of different masses and energies can be exploited for defect healing and provide a roadmap to undertake systematic studies on this subject. For the sake of brevity, a quick summary of important results and the guidelines is presented towards the end of this article and not here. Besides the nuclear waste community, the study is also of interest to a wide research community dealing with defect formation and defect healing in glasses for use in radiation environments experienced in nuclear reactors, decommissioning and space applications to name a few.

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Section: Resultsmentioning

confidence: 99%

Section: 4mentioning

confidence: 99%

Section: 4mentioning

confidence: 99%

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Using external ion irradiations for simulating self-irradiation damage in nuclear waste glasses: State of the art, recommendations and, prospects

Mir

Peuget

2020

Journal of Nuclear Materials

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“…The Si O bond is chosen as this is normally considered to be the limiting factor in the rupture of bonds in silica based glasses [3]. Rearranging equation (13) gives: Figure 26 presents the bond elongation of the Si O bond using this equation. Assuming an ideal bond length of 0.161 nm, the strain on the Si O bond equates to 90 to 200% strain in the SBN glasses.…”

Section: Change In the V Versus K I In Region I As A Functionmentioning

confidence: 99%

“…Moreover, these components are used to model the behavior of their more complex counterparts (e.g. [13]). The last section provides a wrap up and an outlook to possible future avenues of research.…”

mentioning

confidence: 99%

Recent progress to understand stress corrosion cracking in sodium borosilicate glasses: linking the chemical composition to structural, physical and fracture properties

Rountree¹

2017

J. Phys. D: Appl. Phys.

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HAL is a multi-disciplinary open access archive for the deposit and dissemination of scientific research documents, whether they are published or not. The documents may come from teaching and research institutions in France or abroad, or from public or private research centers. L'archive ouverte pluridisciplinaire HAL, est destinée au dépôt et à la diffusion de documents scientifiques de niveau recherche, publiés ou non, émanant des établissements d'enseignement et de recherche français ou étrangers, des laboratoires publics ou privés. Recent IntroductionOxide glasses are among the oldest industrial materials known to man, and they are widely used due to their advantageous properties: transparency, low thermal expansion, high melting point temperature, relative inertness, etc. Yet, oxide glasses are not without significant shortcomings. In par ticular, they remain inherently brittle, despite significant scientific ingenuity to overcome this drawback. Moreover, they undergo abrupt catastrophic failure. Frequently, post-mortem failure studies reveal material flaws which were propagating via stress corrosion cracking. Understanding and predicting the growth of such flaws under sub-critical crack propagation remains a hurdle for scientists. Furthermore, how the basic glass network (i.e. the interconnect of the glass structure) dictates the physical, mechanical and stress corrosion cracking AbstractThis topical review is dedicated to understanding stress corrosion cracking in oxide glasses and specifically the SiO 2 B 2 O 3 Na 2 O (SBN) ternary glass systems. Many review papers already exist on the topic of stress corrosion cracking in complex oxide glasses or overly simplified glasses (pure silica). These papers look at how systematically controlling environmental factors (pH, temperature...) alter stress corrosion cracking, while maintaining the same type of glass sample. Many questions still exist, including: What sets the environmental limit? What sets the velocity versus stress intensity factor in the slow stress corrosion regime (Region I)? Can researchers optimize these two effects to enhance a glass' resistance to failure? To help answer these questions, this review takes a different approach. It looks at how systemically controlling the glass' chemical composition alters the structure and physical properties. These changes are then compared and contrasted to the fracture toughness and the stress corrosion cracking properties. By taking this holistic approach, researchers can begin to understand the controlling factors in stress corrosion cracking and how to optimize glasses via the initial chemical composition.

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Composition-dependent mechanical property changes in Au-ion-irradiated borosilicate glasses

Chen

Zhang

et al. 2019

Journal of Nuclear Materials

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Effect of elastic collisions on acoustic wave propagation in simplified nuclear glass: Molecular dynamics simulation

Cited by 6 publications

References 9 publications

Using external ion irradiations for simulating self-irradiation damage in nuclear waste glasses: State of the art, recommendations and, prospects

Using external ion irradiations for simulating self-irradiation damage in nuclear waste glasses: State of the art, recommendations and, prospects

Recent progress to understand stress corrosion cracking in sodium borosilicate glasses: linking the chemical composition to structural, physical and fracture properties

Composition-dependent mechanical property changes in Au-ion-irradiated borosilicate glasses

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