A new slug for U-233 production consisting of a solid thorium core externally jacketed by a thin Oralloy foil is described. Advantages of this system are pointed out. The bulk of this report concerns itself with the long-term changes of reactor parameters as the foil slug is irradiated at constant specific power (kilowatts per foot). Isotope yield curves are also presented.

The purpose of this report is to present the results of a brief series of transient heat transfer experiments directed toward determining the possibility of damage to a K reactor should a front hydraulic connector fail to a tube containing I&E fuel elements. Nuclear heating of a train of 32 I&E slugs was simulated by electrically heating a rod in a K geometry process tube. Failure of a front fitting to such a tube was simulated by simultaneously and rapidly closing a valve in the water supply to the tue and opening a valve in a line which permitted discharge from the inlet of the tube through a front nozzle to atmosphere. Two to three seconds after the valve operation, a power reduction was initiated. The power reduction was in accord with an 800 inhour scram, except for two runs at 1,500 inhours. The reverse flow, rear header pressure and eight rod thermocouples, as well as other less important variables, were monitored. A test was continued until rod temperatures of 450 to 500 C were reached or until conditions of adequate cooling were established. With the exception of one run at 750 KW, all runs were with an initial tube …

The author tells about some of the most interesting aspects of recent research on the synthetic transplutonium elements. The amount of recent information on these elements is obviously too much to cover completely in the time that has been placed at my disposal. Therefore, in planning my talk, I have attempted to choose those topics which have the broadest implications for the whole transuranium field of research. Although much important and interesting research is, of course, being done in many laboratories, I have chosen examples mainly from the work in our own laboratory, the Radiation Laboratory at the University of California in Berkeley. I shall cover this information about the known transplutonium elements, listed in Slide No. 1, by discussing them in order of increasing atomic number, and I shall conclude with some thoughts concerning the prospects for elements with higher atomic numbers than any that have been produced and identified up to the present time. For purposes of orientation, Slide No. 2 shows the position in the periodic table of the presently known and the future transuranium elements. The transplutonium elements through element 103, together with the five preceding elements, are members of the 'heavy rare earth', or actinide …

None

It has been the custom to report the operating experience at the ORR along with other activities in the reports of the ORNL Operations Division. It was decided to combine the sections of the Operations Division reports appropriate to ORR operation covering the year from April 1958 through March 1959. (W.D.M)

None

A radiofrequency system consisting of 16 cavities, strongly coupled together by transmission line, is analyzed. This system can be regarded as a single cavity operating in a particular mode, and is found to be a practical system for the accelerator. Also methods ef coupling r-f power into the system are considered. The r-f system with beam loading is analyzed for stability, and a relationship determined for the range ef the cavity tuning over which the system is stable. (auth)

None

Critical-assembly studies were made to provide engineering and physics data to aid in developing the Gas Cooled Reactor Experiment-1 (GCRE-l). Measurements of critical mass, flux and power distributions, and shutdown worth of the GCRE-1 mock-up safety and control blades were obtained. The critical assembly consists of aluminum tubes containing four concentric stainless steel cylinders wrapped wtth highly enriched uranium foil. These tubes are supported at each end by grid plates aiid arranged to approximate a right circular cylinder. The entire core structure is supported within a tank which can be filled remotely with moderator water. A void beneath the core structure and the air above it represent the gas plenums of the GCRE-1 reactor. Critical mass and flux power distributions were determined for several cases of four basic cores. The thermal utilization, measured in two core configurations, was 0.780 for the reactor wtthout burnable poison or a lead reflector. The temperature coefficient of reactivity, measured in two cores, was positive at room temperature but negative in the proposed operatingtemperature range. The total reactivity effect in going from 20 to 80 deg C was a positive 0.22% DELTA k/k. The worth of control and safety-shutdown blades of several compositions and sizes …

None

None

In the exposure to a 7 0 0-MeV/c negative particle beam, 35 antiproton stars have been found. Of these antiprotons, 21 annihilate in flight and three give large-angle scatters ( {Theta} > 15 , T{sub P-} > 50 Mev), while 14 annihilate at rest. From the interactions in flight we obtain the total c r o s s section for antiproton interaction

Progress in the Fluorox program is reported. The chemical reaction of primary interest in the Fluorox program is the oxidation of UF/sub 4/ with O/sub 2/, 2UF/sub 4/ + O/sub 2/ = UO/sub 2/F/sub 2/ + UF/sub 6/; however, to study this process at higher temperatures, the thermal decomposition of UO/sub 2/F/sub 2/, 3UO/sub 2/F/sub 2/ = 2/3 U/sub 3 /O/sub 8/ + UF/sub 6/ + 1/3 O/sub 2/, is being investigated by thermogravimetric methods in the temperature range 750 to 900 deg C. A fluidized bed reactor and a flame reactor have been used successfully to perform the continuous oxidation of UF/sub 4/ with O/sub 2/. The 3-in. fluidized bed reactor was operated up to 825 deg C on both a continuous and batch basis while the flame reactor was used to continuously react finely divided UF/sub 4/ with O/sub 2/ in a CO-O/sub 2/ flame at temperatures greater than 1200 deg C. (auth)

The effect made on the RM (Remote Mechanical) Line equipment by an increase in the plant batch size from ca. 300 grams to ca. 375 grams has been studied. Using the process as determined by Production Test 234-3, the volumes for a 300 gram batch and a 375 gram batch are as follows, respectively: volume of plutonium peroxide (alcohol washed, filtered)--1,275 cc., 1,593 cc.; volume of plutonium tetrafluoride (as produced)--617.7 cc., 772 cc.; and volume of reduction charge (tamped)--511 cc., 638 cc. The difficulties encountered with 375 gram batches are discussed.