By J. H. W. Simmons and J. V. Dunworth (Auth.)
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For this value of T are given in Table 6 c w t n D c c D Ni c TABLE 6. NICKEL-DAMAGE INDEX «D/<£Ni** (Calculated (Experimental) T = 25000 KeV) /3^D/^Ni Moderator Position BEPO Experimental Hole* BEPO Hollow Fuel Element* BEPO Empty Fuel Channel* PLUTO Replacement Fuel Position* PLUTO Hollow Fuel Element* C 100 0-43 100 0-59 0-49 0-51 0-49 0-39 Graphite Graphite Graphite D 0 D 0 D 0 DR3 Replacement Fuel Positionf D 0 DR3 Hollow Fuel Elementf HERALD Replacement Fuel Position} H 0 2 2 2 2 2 0-43 100 0-52 0-49 0-52 0-49 * Bell et al (1962) t Bridge et al (1963) % Simmons (unpublished) ** Wright (1962) for comparison with the measured values.
Some information can be obtained from diffraction experiments but at present the properties of the intermediate size defects have to be inferred from changes in properties produced by them. Irradiation is not the only method of producing lattice defects. They may be produced by heat treatment and some defects are always present in unirradiated graphite. Point Defects The simplest defects that can be considered are vacant lattice sites and interstitial atoms. The equilibrium position for an interstitial atom is one which gives the maximum spacing between the interstitial and the surrounding atoms and therefore the minimum energy.
By the position of the control rods or other absorbers. The ratio ^ D / ^ N I ^ therefore substantially independent of the power level in n a n D D D m t n e 34 RADIATION DAMAGE IN GRAPHITE this particular position, thus justifying the assumption made in determining Q. /0Ni * values calculated from the reactor spectra for various values of T . Values of the ratio calculated by Wright (1962) are given in Fig. 9. A comparison with the experimental results gives T = 25,000 eV. <£ /<£ for this value of T are given in Table 6 c w t n D c c D Ni c TABLE 6.