The Transuranium Processing Plant (TRU), designed to produce the world's first gram of californium-252 is near completion. The objective of the program is to produce, isolate and recover gram quantities of the transuranium elements for basic research, which include the isotopes of americium, curium, berkelium, californium, einsteinium and fermium. Californium, however, is believed to be the heaviest element that can be produced in quantities as large as one gram. This small, lightweight element could become a power source for satellites and space vehicles, and a portable neutron source for industry and other research laboratories.
ORNL's Operations Division in collaboration with Health Physics, laid plans to begin operation of a new intermediate level waste disposal method, called the shale fracturing system. This system blends cement, fly ash and other additives which are then pumped into a bedded shale formation several hundred feet underground. Fly ash being a major portion of the waste injection was considered to be a substantial savings and increasing its use in a number of injections over succeeding years would be an important economy factor. Further savings in the shale fracturing system would be realized by injecting more radioactive waste within a given layer of the bedded shale. This would save the cost of drilling a new injection well or opening new monitoring wells.
ORNL received approval for funding ($ 4.8 million in 1965 dollars or $ 39.5 million today) the construction of an electron linear accelerator (LINAC). This new accelerator will be a the first of its type constructed at any of the AEC laboratories. This high-intensity, short-burst LINAC can provide something that has been lacking, namely precise neutron cross-section information useful for development of the fast breeder-type reactors. The major part of the facility, to include a unique vacuum target room, will be underground to provide the needed earth shielding.
ORNL's Isotopes Division scored another world first by electromagnetic enrichment of americium-242 to provide milligram quantities for nuclear research. This achievement was made possible by the existence of electromagnetic separators located in a contained area, and by the design of special equipment which permitted the recovery of radioactive feed material without removing the separator components.