The effect of stress on the microstructure of neutron irradiated type 316 stainless steel

Brager, H.R.; Garner, F.А.; Guthrie, G.L.

doi:10.1016/0022-3115(77)90119-2

Cited by 89 publications

(27 citation statements)

References 24 publications

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“…The nucleation, growth and character of c-component vacancy loops are governed to a large extent by a stress in the matrix, and the results would be accelerated or "breakaway" growth in neutron-irradiated zirconium [54]. Brager et al [12] have also shown that applied tensile stresses enhance swelling in neutron-irradiated 316 stainless steel, and that the number densities of both voids and Frankel loops are sensitive to the stress level. The results presented provide an atomic-level mechanism for the nucleation of a void embryo and its growth under applied stress (c-component) in zirconium, which explains the stress-enhanced void formation and swelling observed in neutron-irradiated materials.…”

Section: Discussionmentioning

confidence: 97%

“…Without insoluble gases, void growth has been also demonstrated by high-voltage TEM [9] because of the much higher displacement damage rate seen in heavy ion irradiation than observed in neutron irradiations. Furthermore, previous experimental work has also demonstrated that tensile stress can enhance cavity growth during irradiation [1,[10][11][12].…”

Section: Introductionmentioning

confidence: 92%

“…Due to the surface energy, vacancy clusters tend to agglomerate to vacancy loops unless insoluble gases or sufficiently large net vacancy flux are present to stabilize the formation of voids from vacancy clusters. Voids and bubbles (voids containing gas) have been observed in numerous neutron, heavy ion and high-voltage transmission electron microscopy (TEM) irradiation experiments in metals and alloys [1][2][3][4][5][6][7][8][9][10][11][12][13]. The significant contributions of insoluble gases (from pre-implantation or nuclear (n, a) transmutation reactions) to the cavity (voids and bubbles) nucleation and growth have been extensively discussed [1][2][3][4][5][6][7].…”

Section: Introductionmentioning

confidence: 99%

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Dislocation-accelerated void formation under irradiation in zirconium

Yao

Daymond

et al. 2015

Acta Materialia

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Molecular dynamics simulations have been performed to model defect creation in alpha zirconium with tensile strains comparable to the elastic strains near the interfaces between zirconium and hydrides. Irradiation-induced vacancy clusters under the strain field could be initiation sites for dislocation nucleation, and the gliding of these dislocations provides channels for transporting atoms from the cascade core, significantly accelerating the growth of vacancy clusters to form a void. The critical number of vacancies in a cluster that is enhanced to grow by the external stress is estimated. The present results provide an atomic-level mechanism to explain the stress-enhanced void growth under irradiation in zirconium, as observed in experiments. The acceleration of delayed hydride cracking under irradiation might be partially attributed to the formation of these voids.

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Section: Discussionmentioning

confidence: 97%

Section: Introductionmentioning

confidence: 92%

Section: Introductionmentioning

confidence: 99%

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Dislocation-accelerated void formation under irradiation in zirconium

Yao

Daymond

et al. 2015

Acta Materialia

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“…С другой стороны, растяжения повышают уровень рав-новесной концентрации вакансий, а это означает, что в материале возникает вакансионная недостаточность. Несмотря на то, что в ус-ловиях действия тензора гидростатических растягивающих на-пряжений вакансии, необходимые для образования пор, отсутст-вуют, скорость процесса с ростом растягивающих напряжений воз-растает [30].…”

Section: составляющие «температурно-силового» поляunclassified

Phase Transformations and Brittleness of ‘Iron–Vacancy’ System in Fields of Elastic Stresses

Laptev

Parkhomenko

2010

Usp. Fiz. Met.

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Фазовые превращения и хрупкость системы «железо-вакансии» в полях упругих напряжений И. Н. Лаптев, А. А. Пархоменко ННЦ «Харьковский физико-технический институт», ул. Академическая, 1, 61108 Харьков, Украина Роль упругих напряжений в формировании структурно-фазовых состоя-ний в неравновесных системах «железо-вакансии» и «железо-вакансии-углерод» исследована теоретически. Построена петля гистерезиса, опи-сывающая процесс γ α-превращений в поле упругих напряжений. Поле нормировано как «температурно-силовое», каждая точка которого отве-чает определенному упруго напряженному состоянию и конкретному фа-зовому составу сплава. Силовые условия неравновесных мартенситных γ α-превращений в этом пространстве определяются вектором, соеди-няющим любые две точки, лежащие на противоположных ветвях петли гистерезиса. Предложен новый подход к определению температуры хруп-ко-вязкого перехода ОЦК-металлов и условий проявления сверхпластич-ности. Модель может быть использована для описания фазовых превра-щений и прогнозирования работоспособности материалов в сложных «температурно-силовых» полях, включая реакторное облучение.Роль пружніх напружень у формуванні структурно-фазових станів у сис-темах «залізо-вакансії» та «залізо-вакансії-вуглець» досліджено теоре-тично. Побудовано петлю гістерези, яка описує процес γ α-перетворень у полі пружніх напружень. Поле нормовано як «температурно-силове», кожна точка якого відповідає певному пружньо-напруженому стану й конкретному фазовому складу стопу. Силові умови нерівноважних мар-тенситних γ α-перетворень визначаються вектором, який з'єднує будь-які точки, що лежать на протилежних гілках петлі гістерези. Запропоно-вано новий підхід до визначення температури крихко-в'язкого переходу ОЦК-металів і умов прояву надпластичности. Модель може бути викорис-таний для прогнозування працездатности матеріялів у складних «темпе-ратурно-силових» полях, включаючи реакторне опромінення.The role of elastic stresses in the structure-phase states formation in the 'iron-vacancy' and 'iron-vacancy-carbon' systems is investigated theoretically. The hysteresis loop describing γ α-transformations in a field of elastic Успехи физ. мет. / Usp. Fiz. Met. 2010, т. 11, сс. 19-59 Оттиски доступны непосредственно от издателя Фотокопирование разрешено только в соответствии с лицензией © 2010 ИМФ (Институт металлофизики им. Г. В. Курдюмова НАН Украины) Напечатано в Украине.

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“…In these studies, it is implicitly assumed that the driving force for void nucleation is derived from the condensation of supersaturated vacancies (cf. Brager et al, 1977;Hirth and Nix, 1985), while not explicitly tracking the vacancy concentration in the material. The energy barrier and critical radius for void nucleation was calculated given the applied normal stress and interfacial energy at GBs and second phase particles (Raj and Ashby, 1975;Raj, 1978), and also considering local internal stresses due to the presence of voids (Hirth and Nix, 1985).…”

Section: Introductionmentioning

confidence: 98%

A void nucleation and growth based damage framework to model failure initiation ahead of a sharp notch in irradiated bcc materials

Patra

2015

Journal of the Mechanics and Physics of Solids

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a b s t r a c tA continuum damage framework is developed and coupled with an existing crystal plasticity framework, to model failure initiation in irradiated bcc polycrystalline materials at intermediate temperatures. Constitutive equations for vacancy generation due to inelastic deformation, void nucleation due to vacancy condensation, and diffusion-assisted void growth are developed. The framework is used to simulate failure initiation at dislocation channel interfaces and grain boundaries ahead of a sharp notch. Evolution of the microstructure is considered in terms of the evolution of inelastic deformation, vacancy concentration, and void number density and radius. Evolution of the damage, i.e., volume fraction of the voids, is studied as a function of applied deformation. Effects of strain rate and temperature on failure initiation are also studied. The framework is used to compute the fracture toughness of irradiated specimens for various loading histories and notch geometries. Crack growth resistance of the irradiated specimens are computed and compared to that of virgin specimens. Results are compared to available experimental data.

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The effect of stress on the microstructure of neutron irradiated type 316 stainless steel

Cited by 89 publications

References 24 publications

Dislocation-accelerated void formation under irradiation in zirconium

Dislocation-accelerated void formation under irradiation in zirconium

Phase Transformations and Brittleness of ‘Iron–Vacancy’ System in Fields of Elastic Stresses

A void nucleation and growth based damage framework to model failure initiation ahead of a sharp notch in irradiated bcc materials

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