Role of Irradiation Temperature

Irradiation temperature typically invokes a very large influence on the microstructural evolution of irra­diated materials. There are several major tempera­ture regimes delineated by the onset of migration of point defects. Early experimental studies used iso­chronal annealing electrical resistivity measurements on metals irradiated near absolute zero temperature to identify five major defect recovery stages.61-64 Figure 6 shows the five major defect recovery stages for copper irradiated with electrons at 4 K.65 The quantitative magnitude of the defect recovery in each of the stages generally depends on material, purity, PKA spectrum, and dose. Based on the cur­rently accepted one-interstitial model, Stage I corre­sponds to the onset of long-range SIA migration. Stage I often consists of several visible substages that have been associated with close-pair (correlated) recombi­nation of Frenkel defects from the same displacement event and long range uncorrelated recombination of defects from different primary displacement events. Stage II involves migration of small SIA clusters and SIA-impurity complexes. Stage III corresponds to the onset of vacancy motion. Stage IV involves migration of vacancy-impurity clusters, and Stage V corresponds to thermal dissociation of sessile vacancy clusters. It should be noted that the specific recovery stage tem­perature depends on the annealing time (typically 10 or 15 min in the resistivity studies), and therefore needs to be adjusted to lower values when considering the onset temperatures for defect migration in typical

image031

Подпись: 50keV
Подпись: Z

Подпись: Figure 6 Electrical resistivity defect recovery stages for copper following electron irradiation at 4 K. Reproduced from Agullo-Lopez, F.; Catlow, C. R. A.; Townsend, P. D., Point Defects in Materials. Academic Press: San Diego, CA, 1988; p 445. image278

Figure 5 Comparison of the molecular dynamics simulations of 1-50 keV PKA displacement cascades in iron. PKA energies of 1 (red), 10 (green), and 50 (blue) keV for times corresponding to the transient peak number of displaced atoms are shown. The length of the Z (horizontal) dimension of the simulation box is 170 lattice parameters (49 nm). Adapted from Stoller, R. E., Oak Ridge National Lab, Private communication, 2010.

Table 1

Summary of defect recovery stage temperatures for materials8,18,63,66 69

Material

Melting temperature (K)

Crystal structure

Stage I (K)

Stage III (K)

Stage V (K)

Pb

601

fcc

5

150

300

Al

933

fcc

35

220

Ag

1233

fcc

35

240

540

Au

1337

fcc

<4

290

530

Cu

1357

fcc

50

270

550

Ni

1726

fcc

60

350

Pd

1825

fcc

50

~350

Pt

2045

fcc

30

~350

Rh

2236

fcc

32

~500

SiC

3103

cubic

220 (C) 450 (Si)

~ 1400(C) 1050 (Si)

a-Fe

1809

bcc

110

230

Cr

2130

bcc

40

380

V

2175

bcc

<6

220

Nb

2740

bcc

5

230

Mo

2890

bcc

40

470

Ta

3287

bcc

10

270

W

3680

bcc

30

650

Cd

594

HCP

<4

120

Zn

693

HCP

18

125

Mg

922

HCP

13

130

Ti

1043

HCP

120

250

Be

1560

HCP

45

280

Co

1768

HCP

55

310

Zr

2125

HCP

150

270

Re

3453

HCP

100

630

1180

Al2O3

2324

HCP

~150

~850

Source: Eyre, B. L. J. Phys. F1973, 3(2), 422-470.

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Schilling, W.; Ehrhart, P.; Sonnenberg, K. In Fundamental Aspects of Radiation Damage in Metals, CONF-751006-P1; Robinson, M. T.; Young, F. W., Jr., Eds. National Tech. Inform. Service: Springfield, VA, 1975; Vol. I, pp 470-492.

Hautojarvi, P.; Pollanen, L.; Vehanen, A.; Yli-Kauppila, J. J. Nucl. Mater. 1983, 114(2-3), 250-259.

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Schultz, H. Mater. Sci. Eng. A 1991, 141, 149-167.

Xu, Q.; Yoshiie, T.; Mori, H. J. Nucl. Mater. 2002, 307-311(2), 886-890.

Young, F. W., Jr. J. Nucl. Mater. 1978, 69/70, 310.

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neutron irradiation experiments that may occur over time scales of months or years. Table 1 provides a summary of defect recovery stage temperatures for several fcc, bcc, and HCP materials.8,18,63,66-69 Although there is a general correlation of the recovery temperatures with melting temperature, Table 1 shows there are several significant exceptions. For example, Pt has one of the lowest Stage I temperatures among fcc metals despite having a very high melting temperature. Similarly, Cr has a much higher Stage III temperature than V or Nb that have higher melting points. As illustrated later in this chapter, the micro­structures of different materials with the same crystal structure and irradiated within the same recovery stage temperature regime are generally qualitatively similar.

Several analytic kinetic rate theory models have been developed to express the dose dependence of defect cluster accumulation in materials at different temper­ature regimes.6,70-72 In the following, summaries are provided on the experimental microstructural obser­vations for five key irradiation temperature regimes.