Report discussing a method for the stepwise calculation of the number of transfer units utilized in a given solvent extraction operation. "Use of the method results in a very appreciable saving in time of calculation with an error of 1.5% for the runs tested. The error tends to become smaller with increasing total numbers of transfer units involved."

Abstract: "The mechanical properties of a large number of zirconium alloys have been investigated. These alloys include zirconium-tin and zirconium-tin-uranium. Tensile tests have been run on these alloys at room temperature, 500 F, and 600 F. Hot-hardness data have been obtained from room temperature to 1600 F, with particular emphasis on the hot-rolling range. Creep tests and fatigue tests have been run on a number of zirconium-tin alloys at 500 F."

Abstract: "The mechanical properties of a large number of zirconium alloys have been investigated. These alloys include zirconium-tin and zirconium-tin-uranium. Tensile tests have been run on these alloys at room temperature, 500 F, and 600 F. Hot-hardness data have been obtained from room temperature to 1600 F, with particular emphasis on the hot-rolling range. Creep tests and fatigue tests have been run on a number of zirconium-tin alloys at 500 F."

Report discussing the progress of research projects at Battelle Memorial Institute relating to civilian applications during August 1956.

This report follows a preliminary study on uranium migration in pressed and sintered UO2-bearing bodies based on MoSi2 or Al2O3.

From abstract: "A continuous countercurrent solid-liquid contactor has been developed which retains the desirable features of the conventional fixed bed and gains the advantages of countercurrent flow. It can be adapted to many solid-liquid mass-transfer processes such as ion exchange, silica gel adsorption, and ore leaching."

Technical report about the liquidus curve for the nuclear reactors bismuth-uranium system and the need for a suitable container for this fuel.

Technical report outlining a preliminary design for carrying out the process of producing U233 from Th232.

Technical report containing the general arrangement of the Low Intensity Training Reactor and outcomes of experiments that have been performed in the reactor to measure the rate of fission product heat dissipation from the fuel pieces after loss of water. [From Summary, Introduction]

This quarterly progress report discusses topics of research and experimentation at the Oak Ridge National Laboratory, including inorganic chemistry, nuclear chemistry, radio-organic chemistry, chemistry of separations processes, chemical physics, radiation chemistry, chemistry of the solid state, instrumentation, reactor chemistry.

The following report proposes various methods in injecting and heating in mirror machines, using high-energy ion beams.

Abstract: "A particularly conventional modified form of Maxwell distribution is chosen. The modified expressions for (a) the energy transfer from the ions to the electrons in a plasma and (b) the brehmestrahlung from the electrons are calculated. Using the expressions some possible steady-state conditions for the ion and electron gases are derived and compared with those for the usual Maxwell distributions."

From introduction comments: The present analysis is intended to examine the relations for "adiabatic" injection in general from a different point of view.

From introduction: "In this report we consider a few non-adiabatic processes. The types to be discussed will be limited because of two reasons: first, complete descriptions are available for some processes; second, as time goes on alternative injection methods undoubtedly will be discovered, so this list must necessarily be incomplete."

Introduction: This note describes briefly the current concept of the experimental program on source development for mirror machines. There are two major facilities involved: (1) A comparatively small machine whose code name is "Guppy", and, (2) A larger d.c. mirror geometry whose code name is "Waldo."

Report discussing the heating of a plasma which passes through a series of magnetic pumping cells by applying the second-order theory of transit-time heating developed by Berger and Newcomb. From abstract: "Transit-time magnetic pumping in single-transit systems seems to be a feasible method of increasing plasma energy by amounts of the order of a factor of 10."

Report discussing the survey work done at the Battelle Memorial Institute with the objective to successfully build a gas-cooled reactor.

"A design study is presented for a sodium cooked, graphite moderated power reactor utilizing low enrichment uranium fuel. The design is characterized by dependence on existing technology and the use of standard, or nearly standard, components. The reactor has a nominal rating of 167 thermal megawatts, and a plant comprising three such reactors for a total output of 500 thermal megawatts is described. Sodium in a secondary, non-radioactive, circulation system carries the heat to a steam generator at 910 degrees F and is returned at 420 degrees F. Steam conditions at the turbine throttle are 600 psig and 825 degrees F. Cost of the complete reactor power plant, consisting of the three reactors, and on 150-megawatt turbogenerator, is estimated to be approximately $43,165,000."

"The Atomic energy Commission has undertaken a development program to provide the technology needed for the evaluation and economic design of nuclear power plants. This program is to be carried out during the next five years at several national laboratories and industrial organizations. The Sodium Graphite Reactor (the SGR) is one of those to be investigated and experimentally tested as part of this 5-year effort. The program on the SGR is intended to expand our area of information covering sodium-graphite technology, experimentally demonstrate the feasibility of this reactor complex and extend its performance limits, and apply in information developed to designs suitable for the full-scale nuclear power plant. As a principal part of this program, a Sodium Reactor Experiment (the SRE) is to be constructed and operated; it will be the major experimental facility in which the performance of this reactor will be studied and new technological advances tested. This report continues an earlier series 2-7 in which previous work on the SGR and the SRE has been described. In this report, the progress on the program is described in two main sections. Section A is devoted to work relating to the general technology of Sodium Graphite Reactors, and to …

Abstract: Experiments on colloid milling and pumping show that uranium trioxide, when carefully dehydrated, can be dispersed in water to form a relatively stable slurry, suitable for a homogeneous slurry pile. At temperatures considerably below those of anticipated pile operation particle size growth occurs attended by increase in settling rate and decrease in viscosity. Theses properties of the slurries may be strongly affected by impurities present as well as by special operating conditions.

Introduction. the colorimetric determination of iron based on the formation of the colored ferrous-1,10-phenanthroline complex has been used successfully by a number of investigators. In this technical report, its adaptation to the routine determination of iron in cerium, thorium, and beryllium metals and their compounds is described.

Abstract: A pilot plant facility for recovering Pu238 and unconverted neptunium from irradiated neptunium target elements was operated for 17 months at the Savannah River Laboratory. The process required that the irradiated target elements be dissolved and the solution be processed through three anion exchange cycles for removal of undesirable fission products and cations, recovery of unconverted neptunium, and concentration of Pu238 solution. The process equipment was enclosed in three stainless steel boxes that were installed in two general-purpose cells of a ten-cell complex. The basic cells were not modified. The two cells were not separated from from the adjacent 8 cells. Containment of the high-specific-activity alpha emitters was accomplished by ventilation, development of handling techniques, use of procedures, and close Radiation Control coverage. The facility was dismantled, and the cells were decontaminated and returned to normal use. With the exception of an accidental overexposure, all personnel exposures were kept below the administrative level of 3 R/yr. None of the personnel assimilated detectable amounts of he material handled.

Technical report describing two experiments performed to compare the amounts of fission gases swept out of UNH solution with those amounts swept out of PU solution under idential condiditons. The charge wire technique was used. The essential date and the results are given in tables in the report.

Technical report that attempts to bring together the various chemical procedures which proved most useful in studying the results of cyclotron bombardment or small scale neutron bombardments of heavy element targets. The report is limited to the elements of the "actinide", or second rare earth series, starting with thorium and including the newly discovered elements of atomic number 95 and 96. Every attempt is made to include all details necessary so this report can serve as a practical laboratory guide. The report covers separation problems, time factors, and dealing with dangerously radioactive targets.