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ANP QUARTERLY PROGRESS REPORT tank would be shielded fairly well, and it would be possible for a man to enter the inner tank through a manhole at the top for inspection or repair work, even after the tank had been closed and the reactor had been run at high power. The water capacity of the space between the tanks, together with the water in the reservoir above the inner tank (approximately 10 ft deep), would be of the order of 110,000 gal. Boiling of this water would suffice to carry off all the heat generated by the fission products for about two days without any fresh water being supplied to the outer tank. All the various wires, pipes, tubes, etc. connected to the reactor and its auxiliaries would pass through carefully laid-out junction panels such as the one shown in Fig, 2.7. Such a panel might be installed II of the tank shown in Fig. 2.6 with a ight gasketed flanged junction. The various thermocouples, power wiring, etc. could be installed on the reactor assembly in the shopand fitted with Cannon plugs so that they could be plugged into the panel in a short period of time after the reactor assembly had been lowered into position in the test facility. This should minimize the amount of assembly work required in the field. The layout investigated as the fourth proposed installation would involve placing the reactor inside a sort of swimming pool with water-tight thermal insulation surrounding the pressure shell, lines, and pumps. The lines could then be brought out the top of the water tank to the instruments and the heat dumps. In the event of a severe accident that resulted in a meltdown, there would be sufficient heat capacity in the water to absorb the heat from the fission products for some days before a seriously large amount of water would have been boiled out of the pool, Such an arrangement could be enclosed, of course, in an air-tight building. This might not be necessary, but it seems likely that, in the event of an abrupt meltdown type of failure, the high heat capacity of the region inside the thermal insulation might put so much heat into the water in a very short period of e that bubbles would boil violently to the surface and disperse entrained fission products. After, perhaps, 10 or 15 min, it seems unlikely that such entrainment would prove to be a problem. The unshielded reactor assembly will weigh approximately 10,000 Ib, the lead gamma shield approximately 30,000 Ib, and the water in the shield approximately 34,000 Ib. The first two of 34 these items could be handled conveniently with a 20-ton crane, while the borated water could be pumped in after the rubber tanks had been installed for the water shield. An arrangement such as the double-walled tank shown in Fig. 2.6 should prove to be adequate to take care of any accident not involving sabotage or bombing. The same should be true for either the hemispherical or circular Quonset type of building. Only the NRTS installation would, be- cause of the remote location, present a not-too- serious hazards problem if effectively sabotaged. To evaluate the merits of each of the installa- tions considered, an attempt was made to envision as many accidents as possible that might prove to be serious during the course of operation of the ART. The worst natural accident that could be envisioned would result in a meltdown. The only source of an explosion that has been envisioned would be either sabotage or bombing. If the volatile fission products are removed during the course of operation, the major hazard to the surrounding area would be from the fission products that might be dispersed in the course of violent boiling or from an explosion. Although in the preliminary hazards analysis consideration was given to operational hazards, operational sabotage, fire, earthquake, flood, windstorm, and bombing, the controlling considera- tions appeared.to be those associated with a total reactor tragedy. The total reactor tragedy is considered here as being an accident in which all the heat that could possibly be released from the chemical combination of various materials in the reactor and associated system would be released, together with the heat from the fission products accumulated after extended operation at full power and the energy released in an extreme nuclear runaway. The principal hazard associated with an ultimate reactor catastrophe is the dispersion of the fission products that would have accumulated from extended operation at high power. The key data on these parameters are presented in Table 2.2. In examining the data on the heat that could be released from the combustion of various materials in the reactor installation, it is immediately evi- dent that if kerosene or another hydrocarbon were used in place of water in the shield a very large amount of heat could be released, an amount almost one hundred times greater than that from any other
A" d OIL IN-l OIL IN-2 NUCLEAR I N STRU M E N TAT I ON 0 0 NaK PUMP DRIVE-2 THERMOCOUPLES CONTROL PUMP ROD PERlOD ENDlNG DECEMBER 10, 7954 Na PUMP DRIVE-I DRIVE-2 SHIELD COOLING IN IN SPARE SPARE SPARE SPARE SHIELD COOLING OUT OUT XENON VENTS He SUPPLY EXPANSION TANK , PRESSURE LIQUID LEVEL SPARES 9 OIL OUT- 1 OIL OUT-2 Fig. 2.7. Junction Panel. UNCLASSIFIED ORNL-LR-DWG 4502 35
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