Document zdV89Dd6RQ11aee8o3q6q3eV7

LEAK CALCULATION D-500 REACTOR 12:45 p.m. - April 1, 1980 An orifice calculational procedure based on the methods of Spink^ was used to determine the amount of the leak. The length and width of the crack were measured and from this a hydraulic radius of 0.0315 inches was calculated. Leak rates were then calculated for ten minute intervals using the average pressure and temperature of the reactor for each interval. These results are shown below: Time Period Reactor Pressure Temperature Psig F Discharge Rate (lb./hr.) Weight Fraction VCM VCM Leaked in Period lbs. 12:45 - 12:55 12:55 - 13:05 13:05 - 13:15 13:15 - 13:25 13:25 - 13:35 13:35 - 13:45 13:45 - 13:55 13:55 - 14:05 14:05 - 14:15 14:15 - 14:25 14:25 - 14:35 14:35 - 14:45 14:45 - 14:55 14:55 - 15:05 15:05 - 15:15 15:15 - 15:25 15:25 - 15:35 15:35 - 15:45 15:45 - 15:55 15:55 - 16:05 16:05 - 16:15 16:15 - 16.25 16:25 - 16:35 16:35 - 16:45 16:45 - 16:55 16:55 - 17:05 17:05 - 17:15 118.5 98.5 73.5 63.0 60.5 59.0 57.0 53.5 49.5 46.5 44.5 44.0 42.0 39.5 38.0 38.0 39.5 38.5 36.0 34.0 32.5 28.0 27.0 22.0 9.0 3.0 1.0 133 120 106 99 95 93 93 90 86 82 81 81 79 75 73 73 75 73 72 70 66 63 61 127 164 187 200 139 120 , 94 , 84 81 80 78 74 70 67 65 64 62 60 58 58 60 58 56 54 52 48 47 38 21 9 5 0.996 0.998 0.999 0.999 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 0.983 0.925 0.780 0.556 TOTAL 23 20 16 14 14 13 13 12 12 11 11 11 10 10 10 10 10 10 9 9 9 8 8 6 3 1 - 283 DTH 000114447 ^Spink, L. K., "Principles and Practices of Flow Meter Engineering 9 9th ed., The Foxboro Company, 1967.