Как выбрать гостиницу для кошек
14 декабря, 2021
As discussed in the previous section, the PBM changed the concept of RDT by recognizing that qualitatively different mechanisms operate in materials when the initial damage is in the form of only FPs and under neutron irradiation, when thermally stable glissile SIA clusters are continuously produced in cascades. The successful applications of the PBM have been limited to low irradiation doses (<1dpa) and pure metals (e. g., Cu). Furthermore, it predicts the saturation of void size with increasing irradiation dose. Thus, it fails to account for the most important observation under neutron or heavy-ion irradiation: continuous increase in void swelling.
The observed continuous void growth may be explained by the development of spatial correlations between voids and other lattice defects. Such as, precipitates and dislocations, that shadow voids from the SIA clusters (see Figures 8-10). It has been argued that this must be the case and the very absence of a void lattice (i. e., a particular case of spatial correlation, which is between voids) must be an indication that spatial correlations with other defects prevail.35
Figure 8 Schematic diagram illustrating screening of a void from self-interstitial atom clusters by a precipitate. The close-packed directions of the cluster Burgers vectors are indicated by arrows. From Barashev, A. V.; Golubov, S. I. Philos. Mag. 2009, 89, 2833-2860. |
Figure 9 Same as in Figure 8 but for a void in the compression side of edge dislocation. From Barashev, A. V.; Golubov, S. I. Philos. Mag. 2009, 89, 2833-2860. |
To account for this effect, a new parameter, ^c, has been introduced, called the 1 correlation-screening factor, which is equal to unity in the absence of shadowing effects and zero when voids are screened completely from the SIA clusters. The swelling rate is then given by
dS
df
where F is a proportionality coefficient, which is a function of all parameters involved.35 Experimental evidence on the association of large voids with various precipitates (G, ^, Laves, etc.)120,160-162 and the compression side of edge dislocations163,164 has been available for a long time. More recent evidence can be attributed to Portnykh et al.165 who studied the microstructure of 20% cold-worked 16Cr-15Ni- 2Mo-2Mn austenitic steel irradiated up to ^100 dpa in a BN-600 fast reactor in the temperature range from 410 to 600 °C. TEM studies revealed voids of three types: a-type associated with dislocations, b-type associated with G-phase precipitates and c-type distributed homogeneously. The c-type voids were the smallest and made practically no contribution to swelling, while the a-type voids were the largest. Such spatial correlations must be a common feature under cascade irradiation.
As discussed in Barashev and Golubov,35 the experimental data on void swelling can be fit by eqn
[143] with an appropriate choice of the dependence of on the irradiation dose (see Figure 10). At high doses, the voids must be completely shielded from the SIA clusters: = 0, and the steady-state swelling
rate of ~1% per dpa observed in austenitic steels33 can be interpreted as being equal to about half of the production bias, that is, the fraction of SIAs produced as 1D mobile clusters:
dS 1 g dfNRT ~ 2 Wi
where esurv = (1 — er) « 0.1 is the survival fraction of defects in displacement cascade. The weak dependence on steel composition observed is probably because the final defect structure is defined by early stages of cascades, when the energies involved are much higher than the binding energies of defects with solute atoms. The observed correlation of the incubation period prior to swelling with the formation of a dislocation network may be connected with an increase of the volume for the nucleation and growth of voids in which voids are screened from the SIA clusters. Higher dislocation density also corresponds to a smaller dislocation climb rate, which might be essential for preserving void-dislocation correlations.
Another distinguishing feature of neutron irradiation is transmutation of atoms, which transform even pure metals into alloys with increasing irradiation dose. The atmospheres of solute (or transmuted) elements near voids may repel SIA clusters and, hence, assist or even solely explain the unlimited void growth. It was shown (see, e. g., Golubov,166 Golubov etal.,167 and references therein) that RIS can provide an additional mechanism of preferential absorption of mobile defects even in the framework of FP3DM, causing a ‘segregation’ bias, which must be different for immobile defects (e. g., voids) and mobile defects, such as dislocations. In the PBM, the interaction of the mobile SIA clusters with different defects may even be more important. Solute atoms may also decrease the mobility of SIA clusters, thereby increasing the recombination rate with migrating vacancies. In the case of very high binding energy of SIA clusters with impurity atoms, the ‘Singh—Foreman catastrophe’18 discussed in Section 1.13.6.2.1 may occur.
Thus, two additional features beyond those already in the PBM distinguish the microstructure evolution under neutron compared to electron irradiation at high enough doses: transmutation of atoms and development of spatial correlations. A fully predictive theory must account for these effects.
The development of a predictive theory requires revisiting all its essential elements: nucleation, growth, movement of voids, and other lattice defects in the presence of spatial correlations, etc. Carefully planned experiments spanning different temperatures, defect production rates, etc., must be a central part of these future studies. Development of the RIS theory for accounting for the SIA clusters is necessary for understanding the sensitivity of microstructure to material composition. Generally, the challenge is to create a theory, where the mean-field approach in its conventional form is abandoned, a task not attempted before.
The authors would like to acknowledge the fruitful collaboration and discussions on the physics of radiation damage for many years with Professor Yu. V. Konobeev (IPPE, Russia), Drs. B. N. Singh (Riso National Laboratory, Denmark), H. Trinkaus (Forschungscentrum Julich, Germany), SJ. Zinkle and Yu. N. Osetsky (Oak Ridge National Laboratory, USA), and Professor D. J. Bacon (The University of Liverpool, UK). Various aspects of the author’s research discussed in this chapter were supported by the Division of Material Science and Engineering and the Office of Fusion Energy Sciences, Department ofEnergy and the Office ofNuclear Regulatory Research, US (SIG and RES) and the UK Engineering and Physical Science Research Council (AVB).