Interstitial Removal in Stage-III Recovery of Neutron-Irradiated W

Deuterium retention in self-damaged tungsten

“…The temperature of 1200 K is too low to anneal out voids [15]. Our assumption of deuterium being trapped by vacancy clusters is supported by field ion microscopy studies (FIM) where no voids but interstitials, vacancies, and vacancy clusters were observed in W irradiated by neutrons [19], [20] and [21]. Additionally, FIM and isochronal resistivity measurements [22] and [23] The TDS spectra from all samples implanted with D at 320-350 K have two peaks: a low-temperature peak with a maximum at about 420-450 K and a middle-temperature peak with a maximum at about 640-670 K. These peaks were already observed, e.g., by…”

Blister formation on tungsten damaged by high energy particle irradiation

“…These studies showed that there are three principal recovery stages above 343 K. The Stage III recovery, the intermediate one, and the Stage IV recovery occurred at $0.15T m , $0.22T m , and $0.31T m , respectively, where T m is the melting temperature of tungsten in K. For the Stage III recovery region Attardo et al concluded that the selfinterstitials produced by neutron irradiation migrate and recombine with vacancies [11]. The intermediate recovery region occurring at $0.22T m is considered to be due to divacancies, impurities, impurity defect complexes, or interstitials which escaped from shallow impurity traps [12].…”

“…The recovery of tungsten defects induced by neutron irradiation (E n > 1 MeV) at reactor ambient temperature (about 373 K) have been studied via isochronal annealing resistivity recovery and field ion microscopy (FIM) [9][10][11][12][13][14]. These studies showed that there are three principal recovery stages above 343 K. The Stage III recovery, the intermediate one, and the Stage IV recovery occurred at $0.15T m , $0.22T m , and $0.31T m , respectively, where T m is the melting temperature of tungsten in K. For the Stage III recovery region Attardo et al concluded that the selfinterstitials produced by neutron irradiation migrate and recombine with vacancies [11].…”

Microstructural evolution of irradiated tungsten: Ab initio parameterisation of an OKMC model

“…The relative stability of the possible dumbbells (h1 0 0i, h1 1 0i or h1 1 1i dumbbells) has proven to be significant in predicting the SIA migration behaviour in Fe and as a result the prediction of the primary damage [27,28]. Most experimental results [29][30][31] as well as MD simulations using ''old" potentials (Guinan et al [32] using the potential derived by Johnson in 1972 [6]; and Carlberg et al [33] using the potential also derived by Johnson but in 1989 [14]) seem to indicate that in W the h1 1 0i dumbbell is the most stable SIA configuration. However, ab initio calculations using PLATO [34] and VASP [35] have showed that it is the h1 1 1idumbbell which is the most stable.…”