By William. R Stratton
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Extra info for Review of Criticality Accidents
7 times the average power. 8 minutes, in which case the average power required to account for the observed yield is about 220 kl% After this, the system probably started to boil, causing a sharp decrease in density and reactivity and reducing the power to a low value for the final 18 minutes. Figure 10 is a photograph taken of the 55 gallon drum shortly after the accident. There was no damage or contamination. 8 rem). At least one person owes his life to the fact that prompt and orderly evacuation plans were followed.
5 x 10’7 fissions. little less than 50 ~ of solution in the early evening of 5 December. The plutonium in R2 was then precipitated with approximately 15 g of plutonium discharged with the supematant. The precipitate was again dissolved, and the carbonate solution was transferred to the holding vessel, leading to the criticality accident. Table 5. 0 Running Plutonium 9. total of in RO (g) 267–51 =216 216+ 176–21 =371 371 +328–39=660 660 +46 -24 = 682 8. Idaho Chemical Processing Plant, 25 January 196114115~1G~17 Uranyl nitrate solution, U(90), in a vapor disengagement This accident occurred in the main process building, CPP 601, in H-cel[, where fission products were chemically separated from dissolved spent fuel.
6% by weight at this point in the cascade). This stage was used to remove contaminants such as air and excess hydrogen fluoride (HF) from the UF~. This Process was accomplished by 1. con~nuousiy diverting a portion of the UF6 cascade stream to DSS-6, vessels, about 4,500 / in capacity each. The contents of these holding vessels were then transferred to the gas purification equipment by the action of a vacuum pump (Figure 15) that used oil as its working fluid. 92, with a concentration of-20 g U//) reducing the pump’s efficiency.