This manual represents the recommendations of the Instrumentation and Controls Division committee on Electrical and Electronic Symbols and Drawing that have been issued to date. Section I consists of copies of the American Standards Association Graphical Symbols for Electrical Diagrams, with certain variations or additions that have been recommended by the Committee to clarify or more positively identify the device or element symbolized. Since publication of the present ASA standards, certain elements, such as the transistor, have come into common use. Committee and represent the symbols have been selected after considerable study by the Committee and represent the symbols that seem to be standard Reference Information series, Interim E--1.

A uniform intensity flat top spill-out cannot be obtained by manual control for two reasons: 1. The horizontal density of the internal beam of the Cosmotron is far from uniform. As a result, a manually controlled linear motion of the internal beam into a target will result in a non-uniform spill-out intensity. 2. Stability requirements of the Cosmotron magnet voltage are not easily met without feedback because of inherent component stability. The proposed servo system will sense the external beam intensity, and correct the magnet voltage to keep this intensity constant. This servo must operate through the transfer function of the main ignitron system and the flat top filter. Both of those transfer functions impose special problems.

The power of nuclear track research emulsion as a fast neutron dosimeter is examined in the exposure of a human phantom to PuBe neutrons. Semiautomatic track scanning and high-speed data analysis obviate the major disadvantages of this dosimeter, and allow the following basic information to be obtained without a serious cost in time: the rulative proton recoil energy spectrum, the absolute differential proton track den sity spectrum, and the average proton recoil energy at various locations in the phantom. From this are calculated the total absorbed local tissue doze due is proton recoils, the local thermal neutron intensity, and that portion of the tissue doze due to thermal [formula] tracks.

"Equations for the heat-transfer coefficient existing at the interface of two metals in contact are discussed. The results of applying the equations (with a graphical determination of the geometric parameters) to an iron--aluminum contact are presented. A method is given for performing the graphical analysis by means of a general purpose analog computer. Data are included that were obtained by applying this method to Blanchard ground stainless steel surfaces in contact. Statistical analysis was applied to surfaces to determine the geometric properties of the contact as a function of root-mean-square roughness and method of surface preparation."

A method is presented for the analysis of transient temperatures in a homogeneous circular cylindrical fuel element in a coolant channel with no axial conduction and no heat loss to the channel wall. In addition, some results were obtained for mean fuel element temperatures in power transients for a simpler model, but accounting for details of the axial coolant temperature distribution in the unsteady state. (auth).

An investigation of the solvent extraction behavior of salicylato- beryllium complexes is reported. A simplified method for calculating the stability constants has been developed. The values obtained are beta /sub 1/ = 4.0 x 10/sup 12/ and beta /sub 2/ = 4 3 x 10/sup 22/ in 0.15 M sodium perchlorate. (auth)

Pechiney and Brush UOX BeO differ markedly in fabrication behaviour, only Brush UOX being readily sinterable. A comparative study of the two powders has shown few outstanding differences in powder properties. Both are of high purity but contain free and combined moisture to the extent of about 1.5 per cent. Pechiney BeO has a larger mean crystallite size (0.2 — 0.3μ) than Brush UOX (0.1 — 0.15μ) and a larger range of crystallite size, and both contain a small proportion of crystallites of size 1μ. and larger. The tap density of UOX is much lower than that of Pechiney, and its surface area is higher by a factor of two, UOX BeO can be hot—pressed or cold—pressed and sintered to high densities at temperatures of 1400º and 1500ºC respectively, which are approximately 300ºC lower than those required for Pechiney. Grain size of fabricated material increases with fabrication temperature in both grades, and at the same temperatures is larger for UOX than Pechiney. However, at comparable densities grain sizes are also comparable for the two materials, The bend strength at room temperature of hot—pressed Pechiney BeO reaches a maximum of approximately 30,000 p.s.i. when pressed at 1750ºC. Above this temperature the …

From abstract: "Recently a general chemical method for the analysis of mixtures of alcohols appeared, using pyridine catalyzed acetylation and second order kinetics to determine the amount of the faster reacting component. The use of 0.25M isobutyric anhydride in pyridine containing 0.0025M perchloric acid as catalyst promotes the rate of the reaction and diminishes the time necessary to perform an analysis. A mathematical treatment of the data and kinetic plot reduces the number of kinetic points to only four or five. The mixtures are primarily composed of isomers."

Technical report. From Abstract : "Irradiation of 'Dowex' 1, 'Permutit' S-1, and 'Permutit' SK anion exchange resins with alpha particles results in losses in ion exchange capacity and in 'apparent per cent crosslinkage'. The order of decreasing radiolytic stability for these properties in 'Permutit" SX > 'Permutit' S-1 > 'Dowex' 1."

None

This document details activities of the Fuels Preparation Department during the month of October 1961. (FI)

This document details activities of the irradiation processing department during the month of October, 1961. A general summary is included at the start of the report, after which the report is divided into the following sections: Research and Engineering Operations; Production and Reactor Operations; Facilities Engineering Operation; Employee Relations Operation; and Financial Operation.

A high expense item in the operation of the button line has been the RS-6 crucible which can be used only once. The 234-5 Research and Development Laboratory has done some preliminary development on a reusable crucible. Before continuing their program, they have requested that an economic study be made to determine what potential savings could be realized if RS-6 were replaced with a reusable crucible. For the purpose of this study, the costs involved were broken down into three areas: Button line costs, Recuplex costs, and Conversion costs. Button line costs include initial crucible costs, operational handling and radiation factors, and other material savings. Recuplex costs cover the effect the elimination of crucible fragments would have on the recovery operation. Conversion cost is an estimate of the expense required to convert the present button line to use a reusable crucible. The results of the study are very favorable and the total possible savings appear to be high enough to write off the cost of conversion of the button line to use the reusable crucible in one year. To write the conversion off in one year, the purchase cost per firing of the crucible must be equal to or less …

The object of the production test described in this report is to evaluate the operational aspects of a proposed method for reducing minimum downtime. The excess xenon poisoning, which occurs during the first 32--38 hours after the shutdown of a reactor from present equilibrium levels, will be partially overridden by a central enriched zone whose added reactivity contribution would be compensated during normal operation by means of poison splines.

The objective of this production test is to compare the irradiation behavior of N Reactor inner fuel tubes (NIE1 elements) having negligible warp after beta heat treatment to the behavior of NIE1 elements with extensive warp after beta heat treatment which were straightened and beta heat treated a second time. The information from this test will be used in the development of a program to evaluate the irradiation behavior of NIE1 elements in various conditions of pre-irradiation warp and straightening.

Accumulation of data on rear face piping strain, piping vibration, water pressures; and water temperatures at KE Reactor was recently completed. A preliminary review of this data indicates that much of the pressure and temperature data could be significant to the study regarding the capability of the K Reactor rear face piping to accommodate the proposed increased water flow. In view of this, a copy of the pressure-temperature data is attached. The purpose of the test was two-fold: (1) to establish mechanical and hydraulic conditions in the rear face piping accompanying operation at current flows and maximum bulk outlet temperatures; (2) to use this information to assess the feasibility of continued operation at these conditions. A preliminary review of the data brings forth the following observations: (1) a downcomer flow transition begins to occur at about the 85 C bulk outlet temperature; (2) the current flow conditions at the top of the downcomer appear to be slightly different from the original design concept; (3) the pressure recorded on the near side of the downcomer just above the orifice (P-10) appears doubtful, and instrumentation will be checked; (4) flow characteristics of the multiple parallel orifices in a single channel does not …

Tests in which aluminum-jacketed, Al-Si bonded uranium fuel elements were baked at various temperatures have shown there is a time-temperature relationship for Al-Si layer decomposition. For heat transfer and secondary coolant barrier considerations, the extent of bonding layer deterioration during fuel element irradiation is important. Currently, Al-Si bonded fuel elements show evidence of spire bond separation, and to a lesser degree, can-bond separation following irradiation. Such evidence has aroused concern for the ability of the currently produced Al-Si bonded fuel elements to withstand future reactor operating conditions. Several potential uranium fabrication and canning process improvements are being developed to further advance fuel element stability and performance. Optimization of process conditions based on these improvements may provide the necessary margin of safety for good bond layer integrity, but before a decision can be made to continue improvement of the present process or convert to a new canning process, more information on the stability of the present fuel element bond is needed. This report presents the irradiation phase of a test which was designed to more fully evaluate Al-Si bond integrity under anticipated future reactor conditions.

The purpose of this Process Improvement Transition Authorization (PITA) is to authorize full pile loading bumper fuel elements in the fringe zone will be reviewed and, if desirable, recommendations to curtail fringe loading may be made based on economic considerations.

The combination of a large reactor core with a sufficiently high flux level results in complications of the dynamic behavior of the core due to asymmetric xenon and temperature instabilities. In both phenomena, a local increase in neutron flux causes an increase in neutron multiplication in a surrounding zone. We consider here the instability associated with the delayed production of Xe{sup l35}, an isotope with a very high thermal neutron cross section. In order for this instability to result in flux oscillations., the neutron production in one part of the core must be independent of conditions in another part. Said in another way this means that the neutron migration area must be considerably less than the square of any core dimensions. Thus, even though the total reactor power is held constant, it may be possible that neutron leakage from one part of the reactor to another is insufficient to counteract the tendency of the local flux to continue increasing in the part of the reactor where it is already high. An asymmetry in the distribution of reactor power may thus tend to increase in After some initial confusion., it has been found that close monitoring of the local power trends …

The oxidation rate of the moderator in D-Reactor has been monitored from samples placed along the length of process tube channel 3478. During the interval from August 8, 1960, to August 10, 1961 were very high, up to 40%/KOD (1000 operating days). From the shape of the front-to-rear burnout profile, the oxidant appears to be oxygen and/or water.

This is the monthly report for the Hanford Laboratories Operation October 1961. Reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, biology operation, physics and instrumentation research, operations research and synthesis, programming, and radiation protection operation are discussed.

The following data represents processing conditions used in fabricating prototypic (except for supports) natural and enriched NPR element assemblies and K-type I&E{sup 2} for the following production tests: ETR, 6{times}6 Loop; GEH-10, Nos. 52, 53, 54 and 55; KER Loops; PT-377; MTR Loop; GEH-4, Nos. 68, 69 and 70. The purpose in documenting the data is to provide a permanent record of processing conditions and dimensions which may be referred to for post irradiation analysis and possible future process work. Post irradiation results will be issued by the Fuels Development Operation, Hanford Laboratories Operation, and the test loop operating conditions will be issued by Process and Reactor Development Operation, Irradiation Processing Department, as outlined in the Production Test Procedure.

The purpose of this report is to present experimental data concerning the heat transfer and fluid flow conditions within a C-overbore geometry process channel for the cases of steady state operation, flow plugging incidents, and inlet piping failure incidents.

This report describes the history of the Federal Income Tax from the first enacted Income Tax in 1861 to when the report was published in 1961.