Effect of neutron irradiation on tensile properties of materials for pressure vessel internals of WWER type reactors

Sorokin, A. A.; Марголин, Б. З.; Kursevich, I. P.; Minkin, A. J.; Neustroev, V. S.

doi:10.1016/j.jnucmat.2013.10.016

Cited by 32 publications

(26 citation statements)

References 11 publications

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“…The plasticity of austenitic steels decreases with the increase of the swelling which is consistent with [2,5,7]. The biggest impact of radiation swelling is the fracture toughness decrease with its dramatically reduction up to 1.3 Â 10 3 J/m 2 .…”

Section: Mechanical Testssupporting

confidence: 78%

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Investigation of high temperature annealing effectiveness for recovery of radiation-induced structural changes and properties of 18Cr–10Ni–Ti austenitic stainless steels

Гурович

Кулешова

Фролов

et al. 2015

Journal of Nuclear Materials

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Section: Mechanical Testssupporting

confidence: 78%

“…High neutron doses lead to the hardening and embrittlement of the baffle material [2]. Operation conditions lead to the radiation swelling of the baffle material as well [3,4] that causes the decrease of its ductility and dramatic reduction of fracture toughness compared to irradiation state without swelling [5e8].…”

Section: Introductionmentioning

confidence: 99%

Investigation of high temperature annealing effectiveness for recovery of radiation-induced structural changes and properties of 18Cr–10Ni–Ti austenitic stainless steels

Гурович

Кулешова

Фролов

et al. 2015

Journal of Nuclear Materials

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“…This is because many of the ceramic alloys are typically used in fuel cladding and must be able to withstand critical core scenarios. Other studies [22][23][24][25][26][27][28][29][30][31] showed that with an increase in neutron flux, the materials showed a temporary increase in hardness as dislocations helped in cases of work-hardening induced by shockwaves and other phenomena. However, the increase in embrittlement resulted in a gradual reduction in yield strength (see Fig.…”

Section: B Ceramic Materialsmentioning

confidence: 98%

A Cohesive Model to Predict Mechanical Responses in Novel Nuclear Fusion Materials and Designs Using a Combined Computational and Empirical Approach

Rodriguez¹,

Cassibry²,

Marlar³

et al. 2014

50th AIAA/ASME/SAE/ASEE Joint Propulsion Conference

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The intent of this paper is to establish the groundwork for additional research into applying nuclear-based materials for space exploration, and attempt to link computational simulations of material exposure to fusion environments with analytical and empirical-based testing of structural and shielding components in a comprehensive, multiphysics scheme. While a special emphasis is placed on the effects of neutron activation and developing a cohesive model that links computational approaches to analytical and empirical tests (especially those used in linear-elastic fracture mechanics and nonlinear approaches), this report will also examine the effects of other sources of damage such as erosion and ablation of electrode structures, which also contribute to reducing component lifetime. Nomenclature A= atomic number α = incident angle B, B 0 = creep compliance b = fatigue strength exponent C 0 = swelling-enhanced creep coefficient c S = solid phase heat capacity D = creep rate ε = material constant derived from the energy needed to remove a unit volume of material ε A = material strain ε' f = fatigue ductility coefficient I = fusion yield scaling coefficient I s = material constant for stress-to-rupture calculations K = particle's vertical velocity component normal to the surface k, k s = thermal conductivity k l , k v = thermal ablation material parameters M = mass of particle N f = number of cycles to failure q = heat flux q * = melting threshold factor φ = material constant relating to the average depth of impact R = Helium to dpa ratio ρ s = density of solid phase S R = Parameter relating rupture stress to time σ = electrical conductivity σ' f = fatigue strength coefficient T mp = melting temperature V = particle velocity V e = volumetric loss W = volume of material lost

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“…Приведенные в последнее время в научной литературе эксперимен-тальные результаты свидетельствуют о том, что реакторные аустенит-ные стали после высоких доз облучения (до 150 dpa), некоторых видов термообработки и при определенных параметрах испытаний действи-тельно способны проявлять высокую пластичность [8,9]. Эти данные значительно выделяются на фоне широко распространенных результа-тов, свидетельствующих о резком снижении пластичности (до 2−12%) с повышением дозы облучения и обнаружении так называемого явления низкотемпературного (20−300…”

Section: поступило в редакцию 22 января 2018 гunclassified

Волна Фазового Превращения В Деформируемых Аустенитных Сталях, Облученных В Реакторе Бн-350, И Условия Ее Реализации

Максимкин¹

2018

Письма В Журнал Технической Физики

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Experimental data on the influence of neutron irradiation on the plasticity characteristics of chromium–nickel austenite steels have been analyzed. Special attention is devoted to detection of anomalously high plasticity levels attained at some parameters of irradiation and deformation, which is explained by the formation and propagation of a “phase transformation wave” in the metastable steel. Necessary and sufficient conditions for the realization of this wave are formulated.

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Effect of neutron irradiation on tensile properties of materials for pressure vessel internals of WWER type reactors

Cited by 32 publications

References 11 publications

Investigation of high temperature annealing effectiveness for recovery of radiation-induced structural changes and properties of 18Cr–10Ni–Ti austenitic stainless steels

Investigation of high temperature annealing effectiveness for recovery of radiation-induced structural changes and properties of 18Cr–10Ni–Ti austenitic stainless steels

A Cohesive Model to Predict Mechanical Responses in Novel Nuclear Fusion Materials and Designs Using a Combined Computational and Empirical Approach

Волна Фазового Превращения В Деформируемых Аустенитных Сталях, Облученных В Реакторе Бн-350, И Условия Ее Реализации

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