Harrison and Paskin (HP) have calculated the ordering energy of β-CuZn using recent theoretical techniques of treating electron screening and Mott's polar model of an alloy. Good agreement is obtained between the calculated total energy of the order-disorder transformation and specific heat measurements. A consequence of the HP calculation is that the ordering energy is long-range and oscillates in sign. Walker and Keating recently measured the neutron diffuse scattering of β-CuZn above the critical temperature Tc and find their data is in agreement with order calculated by only considering a nearest neighbor interaction. Using the Cowley statistical theory of order, we compare the order generated by a nearest-neighbor interaction and the long-range interaction of HP at a temperature 1.1Tc. we find the average behavior of the order generated by the nearest-neighbor and long range interaction to be similar, The major difference is the nearest-neighbor interaction generates order that asymptotically, varies smoothly with neighbor distance whereas the order resulting from the long-range interaction fluctuates markedly about the nearest-neighbor generated order. This result may explain the success of statistical theories, based on nearest-neighbor interactions, in both order-disorder of alloys as well as in some magnetic systems which are also believed to have …

The solution time of analogue multipliers using field-effect transistors is investigated. This time is ultimately limited by the charging time of the field-effect transistor junction. In typical devices suitable for analogue multiplication the charging time is found to be about 10-20 nsec less than one percent. A four quadrant pulse amplitude multiplier circuit is described, whose solution time is equal to the field-effect transistor charging time.

The basic similarity in cytochrome physiology between Anacystis nidulans ad Euglena gracilis, strains Z, is impressive in view of their gross dissimilarities in size, structure, and pigment content. We have investigated the cytochrome reactions by sensitive spectrophotometric methods in order to gain some insight into the patterns of energy transfer from the various light receptors to the reaction centers involved in the two photochemical reactions of green plant photosynthesis and also to elucidate the pathways of photosynthetic electron transfer. The major thrust of this presentation will be the implications of experiments on whole cells in which both wavelength and intensity of monochromatic actinic light have been systematically varied. Some preliminary observations of the effect of carbonyl cyanide-m chlorophenylhydrazone (CCCP) are presented, and the light-driven reduction of cytochrome b6 in Euglena chloroplast fragments is described.

A model has been developed for the analysis of current reversal chronopotentiograms in systems where the electrode process is followed by a homogeneous second order reaction. The model is analyzed using the IBM 7094 digital computer programed in FORTRAN language. Working curved, derived with the aid of dimensional analysis, can be used to evaluate rate constants from experimental data. The electroreducation of uranium (VI) to uranium (V) with subsequent second order disproportionation of uranium (V) has been studied as an experimental test of the model. Disproportionation rate constants thus obtained are in satisfactory agreement with previously reported values. Other possible applications of the model are discussed.

The importance of the examination of paper and textile supported art objects by means of low energy X-rays has been ably discussed in the preceding papers of this session. The apparatus used for such radiography, however, has tended to be both expensive and confined to laboratory use. A lack of mobility arises from the weight and size of X-ray apparatus and the fact that its installation frequently requires shielding and special electric power lines. An inexpensive radiographic apparatus that required no special installation or external power and is small and light enough to be easily portable should be quite useful.

The heavy metal intoxications involving the brain may be divided into two groups: One, in which the offending metal is clearly a poison, such as mercury or lead; and a second, in which the offending agent is normally an essential constituent of the body. The latter category would include manganese poisoning, copper poisoning (or Wilson's disease) and, if some recent data are valid, Huntington's chorea, in which iron seems to have been implicated. Our interest in the second category of diseases is due to the fact that these conditions represent special aberrations of normal homeostasis. Homeostasis is the sum of the processes which maintain constant structure, function and constitution in the body and its organs. In manganese poisoning, the homeostatic control is disturbed by virtue of oversupply of this element via an abnormal route (the respiratory tract), while in Wilson's disease homeostasis is disturbed by virtue of genetically transmitted abnormal avidity of the body for dietary copper. In the present paper, we will discuss first some of the clinical features of chronic manganese poisoning in order to raise some questions about extrapyramidal syndrome in general. Thereafter, we will allude to some investigations conducted at this center during the last ten …

Brookhaven has sponsored a summer program to study possible experimentation with super-high-energy accelerators of ~ 1000 BeV and to examine the feasibility of colliding beam experiments. A group of about fifty physicists took part in this study program. These investigations are a continuation and supplementary to our previous studies at Brookhaven about two years ago.

A strong motivation for metabolic investigations of essential metals lies with the simple fact that these elements are primordial metabolites and building blocks of living matter, a truism largely forgotten today. Among them, the metals of the first transition group display high physical and chemical flexibility: They can concomitantly coordinate natural or artificial ligands; they can regulate electron and proton transport; they can act as catalysts or as cofactors to catalysis.

This scaler was designed to replace an obsolescent tube design that was in general use at Lawrence Radiation Laboratory in Livermore. The new design, using solid state devices and printed circuit modules, allows two complete scalers in one frame to occupy the same rack space as the tube design. Switches in the input circuits of the new scaler change input impedance and sensitivity for operation with either tube or transistor circuits. The use of transistors has greatly increased reliability, and has also reduced power by a factor of fifteen. Modular construction of all circuits, including the power supply, minimizes down time since all modules are replaceable without removing the scaler from its rack. Reliability, then cost, were the criteria dictating choice of components and circuits in the scaler design.

Two principle reasons exist for the extension of high pressure research to temperatures near absolute zero. First, the comparison of certain data with theory (such as the pressure-volume relationship) is more meaningful if the effects of thermal vibrations can be ignored. Second, there are phenomena which can be studied only at low temperatures. These include superconductivity, the properties of solid helium and other inert gases, some electronic phenomena, etc.

Task A: Modification and Preparation of Experimental Facility. Facility engineering and layout is about seventy-five percent complete. Task B: Design and Construction of Test Sections. The major dimensions and characteristics of the metal and glass test sections have been calculated. One feasibility test of the electrically conducting coating on samples of glass tubing has been completed. Task C: Design and Construction of Test Stand, Task E: Pressure and Temperature Instrumentation for Test Section and Task F: Power Supply for Test Section. Preliminary engineering has been initiated on these tasks. The planned approach has been defined in each case. For Task E the transducer specifications have been defined and quotations on and/or sample units of the transducers have been requested. Tasks C and F can proceed with detailing as soon as drafting on Task B is about 50 percent complete. This point is scheduled to be reached during the first part of July. Task D: Void Fraction Instrumentation. The requirements for the x-ray instrumentation have been considered in the course of Task B and the x-ray power supply is presently on hand. The detailed engineering effort on this task is not scheduled to begin before July.

This document describes the detailed test procedures to be used during the initial phases of the physics test program--the approach to critical and minimum critical size tests. During these initial phases, several physics characteristics of the reactor will be evaluated in addition to determination of the critical loading. Overall flux distributions will be determined in the critical pile and used to evaluate the lattice buckling characteristics. Theoretical calculations normalized to experimental values from exponential and PCTR tests have been used for estimating the experimental results for each phase. The startup tests will be used to verify the preliminary calculations and to define the reactor characteristics within the precision required for safe and efficient operation of the reactor. Detailed and accepted test procedures are required for maximum test efficiency and reactor safety during the physics test program and for sufficient overall scheduling into the N-Reactor operational test program. Hazards` analyses have been performed and are presented for cases which are unique to the physics startup tests or significantly differ from the Design Hazards Review.

None

This document lists the physics factors for the K Reactors following the transition to the KV fuel element geometry and zirconium tubes. Each new parameter with the zirconium tube lattice has been calculated relative to the factors used with aluminum tubes and the KIV fuel elements. The purpose of this document is to provide working values for plant assistance use during the transition to the zirconium lattice. In some cases, where there are large uncertainties in the absolute values, the conservative end of the range has been provided for present operational use in safety and control administration. Refinement and publication of ``best`` values for the zirconium lattice based on the extensive experimental and calculational studies are included in future Reactor Physics Unit programs.

A testing program designed to provide the necessary data for evaluation of the emergency flow backup adequacy was conducted at the K reactors on February 16, 1963. Three transient or trip-out tests and 13 steady-state tests were performed under authorization of PT IP-573-I. This report contains the numerical results of the pressure and flow data that were obtained during these tests.

A study on low flow in tubes indicates that the below normal coolant flow is due to an abnormality in the rear hardware. It is suggested that reaming the rear Parker fittings on the tubes and subsequently inspecting the venturi gauges is an good solution.

The effective delayed neutron characteristics of a reactor are dependent on the relative fission rates in the various fissionable isotopes present. The delayed characteristics of the production reactors are presented as a function of exposure.

Heavy-ion reactions in the low-Z region were investigated with 27-Mev nitrogen ions from the 73-inch Cyclotron and with 30-Mev oxygen ions from the Tandem Van de Graaff. Experiments included studies of angular distributions and excitation functions for transfer reactions, compound-nucleus reactions, effects of angular momentum on the density of nuclear states, and so-called Ericson fluctuations in the compound nucleus Si/sup 28/. Nuclear reactions induced with 22-Mev protons in the 86-Inch Cyclotron were used in studies of the pickup- reaction mechanism, shell-model studies from pickup reactions, scattering and the optical model, and level schemes in highly deformed nuclei. In theoretical investigations of the mechanisms of nuclear reactions and related nuclear- structure information, the elastic scattering of complex particles was analyzed via the optical model; the applicability of the distorted-wave method to stripping reactions was investigated, and the inelastic scattering of carbon ions from carbon was examined. Experimental studies with the eightsector electron model, Analogue II, led to very successful deflection of the beam in November 1962, a significant advance in accelerator technology, This investigation, still incomplete, eases one of the major uncertainties associated with the proposed Mc/ sup 2/ cyclotron. The radioactivity resulting from the residual undeflected beam being dumped onto …

Centrifugally cast stainless steel piping was selected for the primary piping of Spert III, a 2500-psi, 650 deg F water moderated and cooled nuclear reactor system, because of the significant cost advantage of using cast piping and because of favorable results from metallurgical examinations of the material. Essentially no operating experience was available at that time on the performance of cast piping in elevated pressure and temperature service. Presented are a brief history of operational experience with this piping in Spert III, the results of a recent plant inspection, and the results of the initial metallurgical examination of centrifugally cast material. On the basis of the Spert experience, it can be concluded that centrifugally cast stainless steel pipe has given adequate service under cyclic operation and probably is equal to high-pressure stainless steel piping fabricated by other methods. However, due to the limited general use of this material, no statement can be made as to the usual commercial quality of cast piping or to its performance under conditions other than those reported. (auth)

A summary of studies conducted on the pressurizedwater reactor loss-of- coolant accident is presented, and an experimental safety program is proposed. The various phenomena involved in the loss-of-coolant accident, related research and development programs, assumptions currently used to predict the various physical phenomena, and the general approach to be used in conducting the safety tests are discussed. In order to accomplish the loss-of-coolant experimental safety program, a dry containment test facility is proposed for construction at the Test Area North of the National Reactor Testing Station in Idaho. The site selection utilizes existing support facilities suited for performing nuclear safety tests requiring experiment assembly areas and post-test analytical examination of the irradiated nuclear components. (auth)

Pump loops designed to operate at temperatures and pressures to 320 deg C and 2000 psia are described. The loops were used to circulate uranyl sulfate solutions and aqueous thoria slurries in out-of-pile tests for the aqueous homogeneous reactor program. As this phase of the aqueous homogeneous reactor program was completed, the loops were converted for use in studies of materials of interest to other types of reactors. Solutions or slurries are circulated in the loops by means of a 100-gpm cannedmotor centrifugal pump. The loop piping is of 1- or 1 1/2-in. size and pressurizers of 4-in. pipe are used where required for steam pressurization. Two of the loops were constructed of commercially pure titanium while all others were of type 347 stainless steel. Some loops are hydraulically pressurized by means of a feed pump and letdown valve arrangement. The nominal volumes of the 15 loops, which were constructed varies between 10 and 30 liters, and each loop was designed to contain a large number of corrosion test specimens of various types for exposure under a wide range of conditions. Each loop test was usually of 200 to 500 hr duration, but some tests were operated continuously for more …

A CDC-1604 subroutine package was written to facilitate the plotting of curves and points on linear, logarithmic, and semilogarithmic graphs using the CALCOMP plotter. The subroutines accomplish the necessary computations and prepare a magnetic tape for use by the plotter. (auth)

The fabricability of dispersion fuels using UO/sub 2/ or UC as the dispersoid and uranium combined with 10 to 15 wt% Mo as the matrix was investigated. Cores containing l7.8 wt% UO/sub 2/ dispersed in U-- 15 wt.% Mo were successfully fabricated to about 80% of theoretical density by cold pressing at 50 tsi, sintering at 1100 deg C, and cold coining at 50 tsi. Comparable results were obtained with UC as the dispersoid. Core fabrication results varied greatly with the type of matrix powder used. Occluded gases, pour density, and surface cleanliness bore important relations to the fabrication behavior of powders. Suitable pressing and sintering results were obtained with prealloyed, calcium-reduced U--Mo powder and with molybdenum and calcium-reduced uranium as elemental powders. Shotted prealloyed powders were difficult to press and sinter, as were elemental and prealloyed powders prepared by hydriding. The cores containing UO/sub 2/ were picture-frame, hot-roll-clad as miniature plates. Molybdenum, Fansteel 82, and Zr--3 wt% Al were investigated as cladding materials. While each bonded well to itself, only the molybdenum-clad core, rolled at 1150 deg C to 10/1 reduction, resulted in dispersions free of ruptures and UO/sub 2/ fragmentation and in strong bonding to the core, evaluated …

The composition of the vapor phase over sulfuric acid has not been measured experimentally because of the low volatility of H{sub 2}SO{sub 4}. A method is described for calculating the partial pressures of H{sub 2}O, H{sub 2}SO{sub 4}, and SO{sub 3} based upon liquid-phase partial-molal thermodynamic quantities. Tables and graphs are provided which give the above partial pressures from -50 to 400 C at thirty-six compositions between 10 and 100 weight-percent acid.