The alternating-gradient proton synchrotrons at CERN and Brookhaven are very similar in size, design and in their experimental use. For this reason, collaboration between the groups at CERN and Brookhaven has been close throughout the history of these two machines. For the most part this has taken the form of exchanges of visits of individual machine designers and of high-energy physicists. By 1962, however, it appeared that the reciprocal flow of information was not adequate and a more formal meeting was arranged. This meeting took place at Brookhaven during the week of September 10, 1962. CERN sent a representative group of machine physicists and high-energy physicists. The meeting was attended also by observers from several American high-energy installations. The discussion covered a wide range of topics, from operating characteristics of the machines themselves to future trends in design of experimental equipment. Plans for beam ejection were presented, techniques were described for better use of secondary beams from internal targets, progress was summarized on dc and rf particle separators. and future trends in neutrino experimentation were predicted.

Abstract: "Theoretical equations have been derived for calculating heat transfer coefficients for fluids flowing through concentric annuli for the following two cases: (A) constant and equal heat fluxes from both walls, and (B) constant, but unequal, heat fluxes from the walls, with equal wall temperatures at a given axial position along annular channel. In the derivations, the conditions of fully-established flow, and independence of physical properties with temperature variation across the flow channel, were assumed. The only geometrical parameter in this general case is the radius ratio r2/r1, and in the study it was varied from 1.0 to 10.0."

In a third run with the fluorine torch, the settling chamber wells were kept hotter than before (≥ 625°C); the flame was cooled by diluting the fluorine with helium. In the analysis of the products, 99% of the thorium fluoride fed in was accounted for, but only 64% of the protactinium activity. Part of this was carried in the exhaust gases past the cold trap and into the soda line disposal column, where it was detected by survey meters. The stripping of protactinium from the solid was somewhat more efficient than before; 77% of the feed which was recovered from the settling chamber had lost 72% of its original specific activity. About 15% of the input activity was trapped on the cold fingers with very little thorium fluoride.

The so-called Fluoride Volatility Processes refer to several proposed non-aqueous methods of processing irradiated fuel elements. In each of these methods, the uranium is fluorinated to UF6 and then decontaminated by distillation. One of those methods, involving the direct fluorination of the uranium by bromine trifluoride (BTF), has been under investigation at BNL since 1950. In 1952, it was demonstrated at BNL that uranium, as UF6, could be satisfactorily decontaminated by distillation in small-scale pilot plant equipment; end in 1953, BNL undertook the job of determining the technical feasibility of a continuous dissolver on a pilot-plant scale. The reason for the project was that the economic superiority of the process seemed to depend upon its amenability to continuous operation.