Mechanisms of helium interaction with radiation effects in metals and alloys: A review

Mansur, L.K.; Coghlan, W.A.

doi:10.1016/0022-3115(83)90047-8

Cited by 290 publications

(111 citation statements)

References 33 publications

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“…It is now clear that the model must presuppose a ready supply of gas impurity atoms (e.g., oxygen and helium [13]) to promote the formation of small voids from the radiation-induced, supersaturated vacancy population. In practice, reasonable corrections to void energies may reproduce the approximate void number density observed in irradiated steel [8].…”

Section: Introductionmentioning

confidence: 99%

Void nucleation, growth, and coalescence in irradiated metals

Surh

Sturgeon

Wolfer

2008

Journal of Nuclear Materials

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A novel computational treatment of dense, stiff, coupled reaction rate equations is introduced to study the nucleation, growth, and possible coalescence of cavities during neutron irradiation of metals. Radiation damage is modeled by the creation of Frenkel pair defects and helium impurity atoms. A multi-dimensional cluster size distribution function allows independent evolution of the vacancy and helium content of cavities, distinguishing voids and bubbles. A model with sessile cavities and no cluster-cluster coalescence can result in a bimodal final cavity size distribution with coexistence of small, high-pressure bubbles and large, low-pressure voids. A model that includes unhindered cavity diffusion and coalescence ultimately removes the small helium bubbles from the system, leaving only large voids. The terminal void density is also reduced and the incubation period and terminal swelling rate can be greatly altered by cavity coalescence. Temperature-dependent trapping of voids/bubbles by precipitates and alterations in void surface diffusion from adsorbed impurities and internal gas pressure may give rise to intermediate swelling behavior through their effects on cavity mobility and coalescence. IntroductionIrradiation of metals has long been known to culminate in macroscopic property changes including void swelling [1]. Characteristic stable voids and steady volumetric swelling develop for a range of temperatures and fluxes, independent of whether radiation bombardment damage occurs as disseminated Frenkel pairs or as small defect clusters. This can occur whether or not helium is generated along with atomic displacements. In either case, small, unstable voids, loops, and other defect clusters will develop almost immediately within the irradiated material. Their subsequent evolution determines the fluence required to create stable voids and achieve 1 arXiv:0803.3829v1 [cond-mat.mtrl-sci]

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Section: Introductionmentioning

confidence: 99%

Void nucleation, growth, and coalescence in irradiated metals

Surh

Sturgeon

Wolfer

2008

Journal of Nuclear Materials

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“…maintain a constant dislocation bias, and (b) maintain constant sink strength during irradiation. This may be achieved by introducing additional spherical absorbers with fixed density and size as follows 2 …”

Section: Sink Strengths In the Okmcmentioning

confidence: 99%

“…That report provided a general description of two alternate methods, reaction rate theory [2] and object kinetic Monte Carlo, that can be used to describe cluster evolution and some preliminary comparisons of the results obtained from specific implementations of the two methods. A substantial fraction of the background material from that preliminary report is repeated here in order to provide a self-contained description of both the computational methods and an extensive comparison of the predictions the models provide.…”

Section: Introductionmentioning

confidence: 99%

Evaluation of Reaction Rate Theory and Monte Carlo Methods for Application to Radiation-Induced Microstructural Characterization

Stoller¹,

Golubov²,

Becquart³

et al. 2007

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The multiscale modeling scheme encompasses models from the atomistic to the continuum scale. Phenomena at the mesoscale are typically simulated using reaction rate theory, Monte Carlo, or phase field models. These mesoscale models are appropriate for application to problems that involve intermediate length scales, and timescales from those characteristic of diffusion to longterm microstructural evolution (~µs to years). Although the rate theory and Monte Carlo models can be used simulate the same phenomena, some of the details are handled quite differently in the two approaches. Models employing the rate theory have been extensively used to describe radiation-induced phenomena such as void swelling and irradiation creep. The primary approximations in such models are time-and spatial averaging of the radiation damage source term, and spatial averaging of the microstructure into an effective medium. Kinetic Monte Carlo models can account for these spatial and temporal correlations; their primary limitation is the computational burden which is related to the size of the simulation cell. A direct comparison of RT and object kinetic MC simulations has been made in the domain of point defect cluster dynamics modeling, which is relevant to the evolution (both nucleation and growth) of radiationinduced defect structures. The primary limitations of the OKMC model are related to computational issues. Even with modern computers, the maximum simulation cell size and the maximum dose (typically much less than 1 dpa) that can be simulated are limited. In contrast, even very detailed RT models can simulate microstructural evolution for doses up 100 dpa or greater in clock times that are relatively short. Within the context of the effective medium, essentially any defect density can be simulated. Overall, the agreement between the two methods is best for irradiation conditions which produce a high density of defects (lower temperature and higher displacement rate), and for materials that have a relatively high density of fixed sinks such as dislocations.2

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“…It can be noted that the cavity structures was categorized into two types; large cavities with a small number density and fine cavities with a quite high number density, as shown typically in figure 7d. Such cavity structures are named "bi-modal distribution" [11], which means two typed cavities has different nature; voids which have relatively large size and low gas-pressure, and bubbles which have small size and high gas-pressure.…”

Section: Behavior Of Dislocation Loops In Stainless Steel -mentioning

confidence: 99%

In-situ observation of microstructural development in Fe-Cr-Ni alloys under dual-beam irradiation

Ohnuki

Takahashi

Hidaka

et al. 1993

Microsc. Microanal. Microstruct.

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Abstract. 2014 To investigate the effect of gaseous elements on point defect cluster formation, such as dislocation loops and cavities, in-situ observation of dual-beam irradiation has been carried out for Ni and commercial stainless steels by using 1300 kV HVEM and 300 kV ion-accelerator facility. During dual-beam irradiation to Ni, small cavities nucleated at only compression side of faulted interstitial loops. From the loop growth experiment in both of Ni and stainless steels, it was confirmed that injected He can increase the migration energy of vacancies, which means He has a strong binding energy to vacancies. Therefore, He atoms and vacancies can move to the compression side of dislocations. In commercial 316 steels the cavity nucleation was strongly enhanced by the dual-beam irradiation, and the bi-modal distribution in cavity size was developed at higher He concentration. From the dualbeam irradiation with different He injection rate, it was clarified that the cavity formation with small size is needed to accumulate some amount of He in the matrix. These suggest that injected He atoms can be stored in the internal sinks.

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Mechanisms of helium interaction with radiation effects in metals and alloys: A review

Cited by 290 publications

References 33 publications

Void nucleation, growth, and coalescence in irradiated metals

Void nucleation, growth, and coalescence in irradiated metals

Evaluation of Reaction Rate Theory and Monte Carlo Methods for Application to Radiation-Induced Microstructural Characterization

In-situ observation of microstructural development in Fe-Cr-Ni alloys under dual-beam irradiation

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