Abstract: A potentiometric study of the complex formation between citric acid (H3L) and the uranyl ion at 25° and ionic strengths of 0.1 and 1.0 (KNO3) is reported From the concentration dependence of the formation constant, it is concluded that polynuclear complexes are formed in which bridging between metal ions occurs through carboxylate and hyroxyl groups of the ligand. The values of the logarithms of the formation constant of the metal checlate [UO2L-]/[UO2+][L3-] and of the dimerization constant [(UO2)xL22-]/[UO2+][L3-] are found to be 7.40 and 4.07 respectively. Infrared absorption measurements of protonated and dissociated carboxyl groups in aqueous uranyl citrte system indicated the presence of both carobxy-late and hydroxide bridging in the polynuclear complex. On the basis of the "core plus links" treatment of polynuclear complexes, the polymeric species in solution in the buffer region between 3 and 4 2/3 moles of base per mole of metal complex appears to be predominantly (U)2)2L2((OH)5(UO2)2L2)216-.

Report issued by the University of California Lawrence Radiation Laboratory discussing a method of updating library circulation records on an IBM 1401 computer. The report describes the methods of generating and updating the records using transaction cards to create computer tapes that are sorted and updated to prepare current reports of circulation information.

Report that summarizes multiple laboratories' reports on global fallout deposition. Reports include data on Strontium-90 deposition recorded by the Health and Safety Laboratory, data from other laboratories, related interpretive reports, and recent publications related to fallout.

A research program is being conducted to obtain experimental data in the irradiation of plutonium-enriched fuel to confirm a theoretical model for predicting isotopic composition and reactivity changes in plutonium-enriched, light-water-moderated reactors. Quarterly progress: Forty-six fuel pellet faces have been auto-radiographed. These faces have been prepared from twenty-three pellets by making an exposure before and after the removal of an additional ten mils of fuel. A substantial number of large "hot spots" continue to appear. The largest spot so far observed was 44 mils long, 20 mils wide, and of the order of 20 mils thick. This spot has a PuO2 concentration which varied from 70% on the periphery to 100% at then center. There is some evidence that the segregated regions are elongated with their long axes perpendicular to the direction of the pressing of the green pellet. Determination of the size and concentration distribution is continuing. The EPITHERMOS code now seems to be operating correctly. A test problem for a typical water lattice converged in eleven iterations. The computation of the spectrum for a pure water medium gave results which agreed very well with the expected 1/E spectrum. At the end of the quarter, the program fuel element …

Summary: All experimental work under the Corrosion Mechanism task has been completed. The remaining topical reports are being prepared by D. L. Douglass, now on assignment at Mol. Experimental work on the first round of 31 alloys and on the second round of 10 alloys has been completed. Steam exposures of at least 3000 hours were finished for all the alloys at all test temperatures, with exposures of some coupons to 6700 hours. Mathematical expression have been derived to describe all first round data for corrosion rates and hydriding rates at 300, 400, and 500 degrees C as a function of Nb, Cr, Fe, and Cu content. Solution of the equations for particular service temperatures yield Zr-Cr alloys at optimum at lower temperatures and Zr-Cu-Fe alloys as optimum at the higher temperatures. The second round test results show that neither Ni nor Be additions to Zr-Cr or Zr-Cu improve the performance over that of the optimum Zr-Cr or Zr-Cu-Fe alloys. For the first round heat treatment used, post-corrosion ductility depends on two factors in addition to alloy composition and hydrogen content: crystallographic texture and intermetallic aging reactions. Alloys with a high original ductility are embrittled less by a given amount …

Report regarding ongoing research and development undertaken at Hanfdord Laboratories' physics and instruments laboratory and chemical laboratory.

From Introduction: "This test manual is intended to be used as an aid to persons purchasing or evaluating permselective membranes. This manual covers specified methods for testing, sampling, storing, and shipping permselective membrane materials of both cationic and anionic types."

From Introduction: "The purpose of this study was to investigate analytically the performance of various combination heat and work-input MPE desalination systems ranging from pure heat-input to pure work-input types. MPE desalination systems are described in the following section, while, the analytical methods and discussions of the results obtained are presented in the appendices."

From abstract: "A detailed description of a reference 1000-MWe fast breeder reactor plant is presented, together with design specifications and the experimental bases for the design."

From introduction: "Documentation of the various considerations and design techniques involved in the design of the reference 1000-MWe fast oxide breeder reactor."

"Designers, builders and operators of water cooled reactor systems have been queried regarding the range of parameters which should be investigated in a study of piping rupture."

Report documenting the design and testing progress of the Oak Ridge National Laboratory's Gas-Cooled Reactor Program.

From introduction: "Cytological examinations of the irradiated and some unirradiated populations in the radioactive sediments of White Oak Creek and the Clinch River were made."

Report containing the results of a preliminary study of a design concept for a graphite-moderated pressure tube reactor. Topics include reactor design, operating procedures, subsystems, hazards analysis, and economic potential. Appendices begin on page 174.

Report containing the estimated costs of the chemical and metallurgical steps in plutonium recycling for large desalination reactors.

Report presenting graphs of the change in input impedance of electrically short dipole antennas in the presence of an isotropic and homogeneous ground which considers four types of antennas: horizontal and vertical, electric and magnetic dipoles. Curves of the change in both the input resistance and reactance are shown for a wide range of values of the frequency, antenna height above the ground, and electromagnetic ground constants.

From abstract: "The time-dependent behavior of the Advanced Test Reactor was calculated by the Babcock & Wilcox Company on the Philco 2000 computer, using the Turbo depletion program."

From abstract: "Results of burnout test to determine the limiting heat flux in a simulated Advanced Test Reactor fuel element channel."

In the course of a general study of K- p interactions at 2.24 Bev/c incident K- momentum, we have investigated the following reactions, the experimentally detectable final states of Ξ Κ π system. In this report we shall discuss the possible existence of Ξ π resonances above 1530 Mev and the evidence for possible structure in the overlap regions. An evaluation of the isospin of the Ξ * will be made. In addition, production and decay angular distribution of the Ξ * will be presented.

The inelastic scattering of low energy neutrons from condensed matter offers a means of investigating the motions of atoms in liquids or solids down to times in the order of 10-12 to 10-13 seconds. The theoretical framework and techniques of such measurements are discussed and the results of cold neutron measurements with liquid H2O and Pb are presented. In H2O the neutron data show that for times in the order of 10-12 seconds the water molecule tends to maintain some average position with respect to its neighbors. In this sense the short time behavior of water is similar to that of a solid. Diffusion characteristic of a liquid occurs at later times. Measurements in liquid lead just above the melting point also show the same effect but not as markedly.

Programs are under way at Brookhaven National Laboratory to study the behavior of fission products released from reactor fuel materials. Major emphasis has been placed on fission product iodine because of the physiological hazard associated with the I131 isotope. A complete reactor safety analysis, considering either a slow or rapid release of fission products, requires a knowledge of the chemical and physical states of the fission products during release, the extent of their release, and an understanding of their chemical interactions with the reactor environment.

One of the major, as well as first, decisions which must be taken on a large chamber is to decide on the direction of the magnetic field, i.e., vertical or horizontal. Either alternative has advantages and disadvantages ad it is the intention of this note to discuss these features.

Prior to assembly into the 80" bubble chamber, the expansion system was subjected to a series of tests to check piston dynamics and gain information on the reliability of the various components. Furthermore, the rest provided operating personnel with the opportunity to become familiar with the operation and maintenance of the expansion system. Two separate tests were performed with the apparatus that was located at the north end of the AGS experimental area; one during the week of Oct. 15 and the other during the week of Nov. 12. The system was run with helium gas supplied from AGS compressor room and the piston was operated at room temperature.

When the design of the refrigerator was begun, one of the important parameters was refrigeration capacity required. In order to estimate the required hydrogen refrigeration load the following had to be considered: 1. Dynamic Load due to pulsing of the chamber. Although this has been determined some two years ago through test work, it has not been published as of this date and will be presented here. 2. Static losses due to conduction, radiation, and convection. This is covered by Eng. Note BC-03-0-B. 3. Cool-down requirements. This is covered by Eng. Note BC-03-0-C.