Currently the B, C, KE and KW reactors are in operation. The B and C reactors are operating to produce 12% Pu-240 in both the E metal (0.95) and natural loadings. Some columns will be taken to 15% Pu 240 on a test basis. Production of 12% Pu-240 will result in exposures of 1400 MWD/ton on natural metal and 2,000 MWD/Ton on E metal. Currently exposures are such that 10 1/2% Pu-240 has been achieved. Some control problems and temperature cycling have been encountered with this mode of operation. Both K reactors are on enriched-depleted loads. The depleted metal is scheduled for irradiation to produce 27-30% Pu-240 (about 3,000 MWD/Ton; 15 months residence) and is currently at 30% of goal. The E metal drivers (0.95) will be discharged at weapons grade Pu exposures. The relatively small quantity of natural uranium in the K reactors will be exposed to produce 12% Pu-240.

A brief discussion is given of the long-term stability of particle motions through periodic focusing structures containing lumped nonlinear elements. A method is presented whereby one can specify the nonlinear elements in such a way as to generate a variety of structures in which the motion has long-term stability.

A brief discussion is given of the long-term stability of particle motions through periodic focusing structures containing lumped nonlinear elements. A method is presented whereby one can specify the nonlinear elements in such a way as to generate a variety of structures in which the motion has long-term stability.

This statistical analysis examines volume increase data from PTA-040. The purpose of this analysis is to compare four 1.25 enriched uranium core alloys (Standard, British, High Silicon, and Modified British), two heat treatments (Induction and Salt Bath), and the alloy-treatment interaction. The four core alloys were each processed using the two treatments and then canned as 5.540-in. AlSi fuel elements. Test pieces were charged in 16 tubes with 40 pieces per tube. The eight fuel types (4 alloys {times} 2 treatments) were arranged in a series of Latin squares in the test tubes to eliminate the effect of position and tube. A comparison of volume increase was deemed worthwhile after analyzing PTA-040 with regard to fuel element distortion. Volume increases in the present analysis were calculated by H.D. Huber using OD and ID measurements taken at C-Basin with consideration for can wall corrosion and geometric distortion. these volume increase calculations were not completely substantiated, since a thorough check with water displacement measurements at the Radiometallurgical Laboratory was not possible. Despite this fact, the present analysis was continued since a good correlation between the volume increase calculations and element exposure was observed.