Radiation-Induced Effects on Microstructure

Zinkle, Steven J.

doi:10.1016/b978-0-12-803581-8.12075-2

Cited by 54 publications

(60 citation statements)

References 327 publications

Supporting

Mentioning

Contrasting

Unclassified

Order By: Relevance

“…In this paper, several important extensions to the modelling framework [3] for irradiation-induced recrystallization are made. The mechanism of loop incorporation into the dislocation network has been reported in [10,11,12] to occur in both bcc and fcc metals and was observed for tungsten in the form of coalescence of loops and dislocation network formation under certain conditions [5]. This mechanism is included in the present model and its effect on the microstructural evolution is investigated.…”

Section: Introductionmentioning

confidence: 77%

Long-term microstructural evolution of tungsten under heat and neutron loads

Mannheim

Dommelen

Geers

2019

Computational Materials Science

View full text Add to dashboard Cite

In nuclear fusion reactors, tungsten will be exposed to high neutron loads at high temperatures (>900°C). The evolution and degradation of the mechanical properties under these conditions is uncertain and therefore constitutes a major risk. Here, the microstructural evolution of tungsten under combined heat and neutron loads is studied, using a multiscale approach incorporating clusters dynamics and a mean-field recrystallization model. The mean-field recrystallization model contains both nucleation in the bulk and at the grain boundaries. The cluster dynamics model includes the incorporation of loops in the dynamics of the dislocation network as a mechanism. The effects of bulk nucleation on the microstructural evolution are explored. The simulations predict a cyclically occuring neutron-induced recrystallization at all studied temperatures. Furthermore, the evolution of the irradiation hardening during neutron-induced recrystallization is assessed from the simulated microstructures. * Correspondence to J. A. W. van Dommelen. Electronic mail: j.a.w.v.dommelen@tue.nl

show abstract

Section: Introductionmentioning

confidence: 77%

Long-term microstructural evolution of tungsten under heat and neutron loads

Mannheim

Dommelen

Geers

2019

Computational Materials Science

View full text Add to dashboard Cite

show abstract

“…During high temperature irradiation, the migration of helium is induced to the grain boundaries by the application of tensile stress, and large cavities may be formed. It has been observed that when the applying stresses are absence, the helium bubbles are divided throughout the metal [24].…”

Section: Helium Embrittlementmentioning

confidence: 99%

Mechanical Properties of Ferritic Martenstic Steels: A Review

Qadr

Hamad

2019

Scientific Bulletin of Valahia University - Materials and Mechanics

View full text Add to dashboard Cite

The word-wide demand for energy is constantly increasing, and therefore ideas around future energy-generation are also on the increase with the aim of meeting this demand. This includes designs for the next generation of nuclear power reactors, such as gas-cooled, liquid-metal-cooled and water-cooled reactors; the goal being to create smarter ways to produce more economical, environmentally-friendly energy. The conditions such reactors would need to meet, present significant design challenges for scientist and engineers, not least around the structural materials and components to use. Depending on the operational conditions, use of elevated- temperature ferritic/martensitic materials such as P91 and P92 steel are favoured by several of the designs for use with out-of-core and in-core applications. The main goal behind this review article is to explain mechanical properties of P91 and P92 steel; these are two types of ferritic/martensitic steels. This reviewer, highlight and discuss the development of ferritic/martenisitc steels for nuclear programmes and to explain the effect of irradiation on mechanical properties of P91 and P92.

show abstract

“…Understanding the mechanisms of these changes is a necessary requirement for the construction of predictive models for estimation of lifetime of power plant components. In particularly the formation and growth of voids and bubbles are of intense interest for material performance in radiation environments [1][2][3][4][5]. Fundamental understanding of the void growth mechanism and kinetics is important in predicting the swelling kinetics in irradiated materials and changes in the strength properties of materials [1][2][3][4][5][6].…”

Section: Introductionmentioning

confidence: 99%

Simulation of the atomic structure near voids and estimation of their growth rate anisotropy

Nazarov

Mikheev²,

Melnikov

2020

Journal of Nuclear Materials

View full text Add to dashboard Cite

We use a new variant of Molecular Static method for simulation of the atomic structure near nanovoids. In our model an iterative procedure is employed, in which the atomic structure in the void vicinity and the parameter determining the displacement of atoms embedded into an elastic continuum are obtained in a self-consistent manner. Results show that the atom displacements near nanovoids are significantly different for varies crystallographic directions in bcc metals. Not long ago we have obtained an equation of vacancy diffusion under strain. Now we use this equation and the atom displacements near nanovoids to evaluate shift of the void surface for varies crystallographic directions. We find the equation for the normal component of the vacancy flux to the surface of the sphere for some crystallographic directions and then calculate shifting rate of the void surface element in mentioned directions for the different supersaturations of the vacancies as a function of temperature.

show abstract

Radiation-Induced Effects on Microstructure

Cited by 54 publications

References 327 publications

Long-term microstructural evolution of tungsten under heat and neutron loads

Long-term microstructural evolution of tungsten under heat and neutron loads

Mechanical Properties of Ferritic Martenstic Steels: A Review

Simulation of the atomic structure near voids and estimation of their growth rate anisotropy

Contact Info

Product

Resources

About