From abstract: "This report describes work done on ARF Project C 216 from January 5, 1962 to September 15, 1962. The objectives of the program include evolution of an analytical research program to evaluate effects of environment contributed contamination on precise devices"

Abstract: "This is the first interim report of a literature survey investigating the uses and technology of radioscopes in the countries of the world, with particular emphasis necessarily placed on those more highly industrialized nations. Part I includes a general summary of the quantity and quality of radioisotope work being performed in these countries. Among the outstanding radioisotope applications with respect to quantity is the work of Japan in chemical research, that of USSR in metals research, and that in the USA in medical research. A detailed qualitative examination of the relatively narrow region of radioisotope applications in leak detection is also presented. Part II of this report gives a direct comparison between the progress and status of the US and the USSR in the varied uses of radio-isotopes."

This report summarizes investigations taken between October 1, 1959, to September 30, 1960 with the objectives of developing high-tungsten alloys which are readily fabricable into massive and complex shapes and which possess adequate strength for operation at temperatures up to 2000 F. Within this report, studies are divided into two main categories: alloy development and material fabrication techniques

Abstract: In one of the final stages of the process at the Mallinckrodt Uranium Refining Center, a 45 per cent nitric acid solution at about 170 F is used to pickle the calcined magnesium fluoride scale off the uranium derbies. The increase in the fluoride-ion content of the bath tends to promote corrosion of the Type 347 stainless tanks. This attack becomes excessive if 0.3 g/liter of fluoride ion or more is present. It was found that if aluminum ion is added to the solution the corrosiveness of the bath can be controlled. Two or three times as much aluminum ion as fluoride ion present is found satisfactory at 170 F. Indications are that the tying up of the fluoride-ion by the complexion [AlF6]8 is responsible for the corrosion control.

"Abstract: Data on analog magnetic tape characteristics are presented along with results from conventional and modulator playback system operational tests. Theoretical considerations imply that the modulator head should be loss sensitive to short term variations in record and playback tape speed. It is also pointed out that although a tape recorder operating at 7.5 in./sec has only 12 kcs bandwidth for sinusoidal wave forms. the record and play-back amplifiers for pulse recording can operate with other bandwidths. These amplifiers must be capable of passing a square wave with a frequency of 1.5 kcs. A square wave of such frequency represents the condition of 350 microsecond pulses with a 700 microsecond period. (J.R.D)."

From abstract: "The variation of the reactivity of a pile as a function of width of a transverse gap is obtained. The method involves first finding the boundary condition satisfied by the flux at the gap face. This, in principle, provides enough information for a complete solution of the pile equations. A method for calculating the reactivity change is presented. The calculated reactivity is compared with experiment and a brief discussion of the validity of the approximations is given."

From summary: "The influence of the structure of phosphate esters on the distribution coefficient of uranium between solutions of these esters in carbon tetrachloride and aqueous nitrate solutions has been studied. Esters of secondary alcohols showed higher distribution coefficients than primary alcohols. Phenyl esters extracted less uranium than alkyl esters, and the presence of other negative groups also resulted in less extraction. Compounds containing carbon to phosphorus bonds gave higher distribution coefficients than the corresponding esters, and the distribution coefficients increased with the number of such carbon to phosphorus bonds. Tributyl phosphine oxide (with three carbon to phosphorus bonds) showed high distribution coefficients with many salts, including uranyl nitrate, uranyl sulfate, uranyl chloride, thorium nitrate, plutonium (IV) nitrate and some of the fission products in nitrate solution. It is planned to study these and similar compounds further."

From abstract: "On the 86-inch cyclotron a 41-kw beam has been calorimetered at a net ion loading efficiency of 40%; the average proton current was 1.85 ma at 22.5 Mev. Practical specific yields have been determined for (p,2n) reactions on zinc and bismuth. The investigation of products of proton-induced fission of uranium has been continued and new techniques are being used in measuring angular distribution of reaction products. The 63-inch heavy particle cyclotron is now in operation; N+++ particles have been accelerated to ~25 Mev. In preliminary tests, induced activities have been detected in carbon, nitrogen, and oxygen targets. A hot-cathode ion source is ready for test operation. The 22-inch cyclotron is being used in an investigation of the problems associated with the use of rf and dc electrodes for the acceleration of protons from the ion source into the dees. Radiation-induced corrosion in Inconel tubing containing #21 eutectic (ANP) has been produced by proton irradiation in the 86-inch cylclotron; it is shown that the corrosion was not due to thermal effects. Approximately 150 grams of highly purified U 238 (< 5 ppm U 235) have been prepared, and two grams of thorium 230 (ionium) has been enriched to 90.6%."

Abstract: "The analysis of an immobilized plasma is here extended to the case where the geometry is cylindrical rather than Cartesian. (This report, UCRL-4439 (Rev, 4 constitutes Part II of the report series (UCRL-4466, Parts I, III, and IV) dealing with this general problem.)"

The following report describes a thermonuclear reactor based on the use of a long layer of rotating relativistic electrons to confine and heat the plasma.

Report analyzing the "preferential removal of neutral gas from an incompletely ionized plasma in which the ionized particles are allowed to drift along magnetic field lines through a differentially pumped channel" and its relation to the P⁴ experiment. The report also analyzes the regenerative and non-regenerative losses of plasma by radial diffusion, as well as "considerations relating to the ultimate disposal of overflow plasma."

Abstract: The reactor kinetics equations are combined into a single integral equation whose kernel describes the time-dependent characteristics of the reactor including six delayed groups of neutrons. Numerical solutions of the integral equation are given for constant, linear, and ∫sin²kx dx reactivities. An approximate solution of the integral equation is obtained which provides a basis for the formulation and solution of the reactor system control problem using the methods of servomechanisms theory. The reactor frequency response function, a product of the approximate solution, is calculated and plot given.

Abstract: "This report describes six electronics areas at the Radiation Laboratory (Berkeley and Livermore) that are being successfully used with various particle acceleration for nuclear research. The electronics equipment, consisting of pulse amplifiers, scalers, coincidence circuits, pulse-height analyzers, automatic recording equipment, high-voltage supplies, etc., is arranged in such a manner that most experiments can be quickly set up, and a number of people can run experiments simultaneously. Advantage and limitations of these areas are discussed."

From abstract: "The relative differential neutron-proton scattering cross section has been measured in the range of center-of-mass angles from 5.1° to 36.0° for approximately 90-Mev neutrons and from 10.7° to 37.8° for approximately 290-Mev neutrons."

Report discussing the equations of the Debye-Huckel theory modified to include quantum statistics.

The following report proposes a concept of a transient version of Astron thermonuclear reactor while describing the basic concepts of the reactor and the design criteria.

Report discussing the application of some previously established methods to yield a calculation of the pressure and internal energy functions of a system of point charges interacting only with Coulomb forces.

Abstract The phase diagram of the uranium-rhenium alloy system is presented along with a discussion on transformation kinetics of the uranium solid solutions. The phase diagram is of the double eutectic type with the intermediate phase having the composition URe2. This phase exhibits allotropy at 180°C and melts congruently at 2200°C. URe2 reacts sluggishly with the uranium solid solutions below 750°C to form the peritectoid compound U2Re. Eutectic reactions occur at 1105° and 2105°C at respective compositions of 10.5 and 65.5 wt. % Re. Eutectoid reactions occur at 643° and 681°C at compositions of 1.4 and 6 wt. % Re, respectively. The maximum solubility of rhenium in α uranium is about 0.4 wt. % at 643°C and in β uranium is 1.9 wt. % at 681°C. The solubility of rhenium in γ uranium is 6 wt. % at 681°C and increases to about 7 wt. % at 975°C. The solubility of uranium in rhenium is 0.6 wt. % at room temperature with little variation up to 2000°C. Alloys of β and γ uranium containing more than about 1.2 and 7 wt. % Re respectively, can be readily supercooled to room temperature. Rapid cooling of γ alloys containing less than about …

This technical report provides a design criteria for a technical support facility for the Lithium Cooled Reactor Experiment (LCRE) and SNAP-50-DR-1 Test Facilities. The support facility is adjacent to the LCRE Test Facility and is located completely within the existing Building 629 structure at the former ANP area of the National Reactor Testing Station (NRTS) near Idaho Falls, Idaho. The information and specifications presented establish the basis for the design of laboratories, shops and engineering areas required to support the installation, operation, maintenance and disassembly of the LCRE and SNAP-50 tests. The construction and modification required to adapt the building to reactor test support operations are described in detail in the following report.

The present report is concerned with the electronic relay which, upon the reaching of a pre-determined value of ionization current in the associated chamber, actuates the safety rod release mechanism. The are here proposed two independent suggestions: (1) An improved trip circuit of such sensitivity and stability as to allow it to be actuated by a signal directly from the chamber without the necessity of interposing intermediate amplifier stages. The value of chamber current at which tripping occurs is stable to +- 0.4%. (2) A triple-wound relay to prevent shut-downs of the pile which would otherwise be caused by development of defects in the safety circuits.

Technical report with short reports from the (1) Experimental Nuclear Physics Group; (2) Theoretical Physics Group ; (3) Lattice Design Group; (4) Pile Design Group; (5) Exponential Experimental Group; (6) Radiation Group; and (7) Shielding Group.

The following report on the nuclear synthesis of technetium is based on work performed under contract No. W-7405-eng-26 for the Atomic Energy Project at Oak Ridge National Laboratory.

The following report discusses the renewed element 43, or eka-manganese, whose discovery was heralded in 1925, but whose chemical properties remained unreported until the radiochemical investigations of Perrier and Segre."

Abstract: "A method of recovering the tuballoy from the trap washes of the high temperature salvage chlorinator is described."