Radiation embrittlement of low-alloy steels

Nikolaev, Yu. A.; Nikolaeva, A. V.; Shtrombakh, Ya. I.

doi:10.1016/s0308-0161(02)00065-0

Cited by 39 publications

(13 citation statements)

References 14 publications

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“…This has led to consider these chemical elements in the empirical embrittlement correlation models for the prediction of the shift of the reference index temperatures [15,16]. On the physical point of view, irradiation produces fine scale microstructures [17]. Their effects on the macroscopic behavior can be separated into two groups [17,18]: (i) change of the plastic hardening, (ii) embrittlement, one of the most wellknown and well-described being phosphorous segregation at grain boundaries [17].…”

Section: Effect Of Neutron Irradiation On the Charpy Transition Curvementioning

confidence: 99%

“…On the physical point of view, irradiation produces fine scale microstructures [17]. Their effects on the macroscopic behavior can be separated into two groups [17,18]: (i) change of the plastic hardening, (ii) embrittlement, one of the most wellknown and well-described being phosphorous segregation at grain boundaries [17]. Hardening mechanisms include matrix and age hardening.…”

Section: Effect Of Neutron Irradiation On the Charpy Transition Curvementioning

confidence: 99%

“…This will lead to higher computed stresses. Considering both the impact and fracture toughness properties, it is well known that irradiation embrittlement induces an increase of the DBT temperature and therefore of the index ) 2 1 2 3 [ 2,17,19,23,28,31]. As far as the upper shelf energy (USE) is concerned, most of the studies report a decrease with increasing irradiation level.…”

Section: ¡ E ¥mentioning

confidence: 99%

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Local approach to fracture based prediction of the ΔT56J and shifts due to irradiation for an A508 pressure vessel steel

Tanguy¹,

Bouchet²,

Bugat³

et al. 2006

Engineering Fracture Mechanics

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Section: Effect Of Neutron Irradiation On the Charpy Transition Curvementioning

confidence: 99%

Section: Effect Of Neutron Irradiation On the Charpy Transition Curvementioning

confidence: 99%

Section: ¡ E ¥mentioning

confidence: 99%

See 1 more Smart Citation

Local approach to fracture based prediction of the ΔT56J and shifts due to irradiation for an A508 pressure vessel steel

Tanguy¹,

Bouchet²,

Bugat³

et al. 2006

Engineering Fracture Mechanics

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show abstract

“…Numerous studies [32][33][34][35][36][37][38][39][40][41][42][43][44][45][46][47][48][49][50] showed that the increase in hardness, due to dislocation effects, could be mitigated by using high atomic weighted materials; however, the increase in atomic size increased the chances of neutron activation and subsequent mass embrittlement. By using lower atomic-weighted materials, the studies showed that embrittlement could be mitigated; issues still remained with high thermalization for low-weight materials, as some of the master curves in the studies indicated 39,40 .…”

Section: General Findingsmentioning

confidence: 99%

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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“…Reactor Pressure Vessel (RPV) steels subjected to neutron irradiation accumulate dosedependent defect cluster populations [1] [2]. This effect significantly influences the lifetime and serviceability of nuclear power plants (NPP), through its impact on dislocationmediated plastic deformation mechanisms.…”

Section: Introductionmentioning

confidence: 99%

Investigation of Radiation Temperature and Straining Temperature Effects on the Screw Dislocation Mobility Evolution in Irradiated Ferritic Grains Using 3D Dislocation Dynamics

Robertson

et al. 2019

The Minerals, Metals &Amp; Materials Series

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Nuclear structural materials subjected to neutron irradiation accumulate dose-dependent, disperse defect clusters populations. Subsequent dislocation/defect interactions induce material mechanical property degradations, including hardening and embrittlement. Our goal in this work is to evaluate the effect of disperse defect clusters population on the effective dislocation mobility in ferritic Fe-Cr grains, using 3D dislocation dynamics simulations. The defect induced changes of the grain-scale mechanical response are evaluated using the recently proposed Defect-Induced Apparent Temperature (DIAT) shift concept. It is found that the DIAT shift associated with a given defect dispersion scales with the ductile to brittle transition temperature (DBTT) shift associated with exactly the same, observed defect population. The dose-dependent evolutions associated with broad irradiation temperature and straining temperature changes are investigated herein, for further exploration and validation of the DIAT shift concept.

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Radiation embrittlement of low-alloy steels

Cited by 39 publications

References 14 publications

Local approach to fracture based prediction of the ΔT56J and shifts due to irradiation for an A508 pressure vessel steel

Local approach to fracture based prediction of the ΔT56J and shifts due to irradiation for an A508 pressure vessel steel

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

Investigation of Radiation Temperature and Straining Temperature Effects on the Screw Dislocation Mobility Evolution in Irradiated Ferritic Grains Using 3D Dislocation Dynamics

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