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Extra resources for Cracking in Pressure-Boundary Materials of LWRs (csni87-141)
The power levels of AMI, bracketing the fission gas release, have been converted to fuel temperatures using the power/temperature correlation determined for test AN3 (Fig. 1), which had similar test parameters. TABLE 1. Power levels at thermocouple hot junctions and corresponding temperature readings after 4h hold time. Determined by linear interpolation between actual levels to enable intercomparison. CO Power at TC W/cm Fill gas 15b He Test AN4 Fill gas 1bXe Test AN10 Fill gas 5b He 200 880'C 1050'C 870'C Test AN3 250 1040'C 1170'C 1020'C 300 1200'C 1300*C 1170'C 350 1380'C 1450'C 1330'C' ' Linear extrapolation from max level at TC position 336 W/cm 3 o 800 600 400 200 0 T—l—i—i—i—i—i—i—\—|—l—l—l—l—l—l—i—i—i—|—:—i—i—i—i—l—i—i—i—l—l—l—r~ XX) 200 400 300 Power at TC, W/cm Fig 1.
The ANF fuel was base irradiated in the Biblis-A reactor in Germany and subsequently transient tested in the DR3 reactor at Ris0. The base irradiation spanned four reactor cycles beginning on July 10th 1982 and ending on October 3rd 1985. 4% FIMA. 7 kWm"1. Powers of this magnitude were recorded at the beginning of the second and fourth reactor cycle. Power changes within each cycle were made at a rate slower than 24 kWnY'h"1. Fission gas release in the base iradiation was very low. 3% release was measured when 4 pins were punctured.
The results obtained on the standard fuel rods in this study appear to support the discussion in it. The FGR data obtained in this study are represented in figures 2 and 3 with the previous ones. Figure 2 shows that the FGR rates at the burnup range lower than l5GWd/t are very low. On the contrary, some fuels show high FGR rates and the scattering of the data increases suddenly at a higher burnup side. However, there are many fuel rods which keep their FGR rates very low as a few« at high burnup over 40GWd/t.