Final Report of SL-1 Recovery Operation
U.S. Atomic Energy Commission, Division of Technical Information Extension, 1962 - Nuclear reactor accidents
In May, 1961, it waa determined no renewed nuclear reaction in the SL-1 pressure vessel was possible as long as water was excluded. It was therefore possible to proceed with the final phase of the SL-1 recovery. This work consisted of moving the pressure vessel and core to the Hot Shop at the north end of the National Reactor Testing Station, dissecting and analyzing the reactor and its components, cutting up and burying the reactor building, and decontaminating the rest of the SL-1 area. These things were accomplished by the General Electric Company between May 1961 and July 1962. It was determined that the central control rod was bound in its shroud at a position corresponding to 20- inch withdrawal. Analysis of the pertinent data showed that the amount of reactivity associated with this rod position, inserted at a rate compatihie with manual withdrawal of the rod, can explain the significant evidence which was coliected. No other means of withdrawing the rod was found to be in accordance with the evidence. It was found that the relatively low yield (130 Mw-sec) nuclear excursion produced a water hammer with pressures up to 10,000 psi, which, in turn, caused the pressure vessel to rise some 9 feet in the air. (auth).
What people are saying - Write a review
We haven't found any reviews in the usual places.
Steel Punchings Near Head of Reactor Vessel
Bottom View of Reactor
Upper End of Pressure Vessel
11 other sections not shown
activity amount approximately assembly attached beta blade blocks body boron bottom camera central cleaning collapsed completely condition connecting contamination control rod core cover crane damage decontamination deformation deposits dose effect energy entry equipment examination excursion exposure extension rod fan room feet Figure flange flux Fuel Element fuel plate gamma ground guide tube heat hole housing I I I I I I inches incident indicated initial inside lifted load lower marks material measured Model normal nozzles nuclear observed obtained occurred operating room period personnel photographs placed plate portion position pressure vessel produced R/hr rack radiation levels reactor building recovered recovery region remaining remote removed samples Shield Plug shown shows shroud side SL-l steam steel strips surface survey tank temperature thermal upper wall wires withdrawal