BAND-1 is an IBM-704 program to reduce the experimental data obtained from measurements of the neutron activation distribution within a critical facility. The data reduction consists of correcting the measured data, sorting and ordering it, and calculating the critical buckling parameters by means of a least squares analysis. (auth)

The Bevatron operated an average of 80% of the scheduled operating time with the exception of one 5-day shutdown period for emergency maintenance of the motor generator sets. The machine was shut off l9% of the scheduled operating time because of component failure and 1% at the request of the user. During and following the Christmas shutdown period an ultrasonic inspection was made of the flywheel keyway on each of the motor generator sets. No faults were apparent. Charpy samples were taken from the inspection bore in the flywheels. Subsequent"vee notch" Charpy impact tests indicated that the flywheels are operated in a brittle region rather than in the ductile range expected. The research program again was devoted mainly to study of pi - and K-meson interactions. (auth)

Separate abstracts were prepared for 43 sections of this report. (C.H.)

A colorimetric method was developed for the determination of uranium(IV) in the presence of uranium(VI), nitric acid, hydroxylamine sulfate, and hydrazine. A coefficient of variation of 2.4% (n = 25) was obtained. (auth)

The variation in concentration of settled beds of flocculated aqueous suspensions of thoria was studied experimentally as a function of the calcination temperature and particle size of the thoria, the temperature and initial concentration of the suspension, and the concentration of added chromic acid. Values of the ultimate settled-bed concentration were obtained by several methods. Dilatant-plastic behavior of one suspension was considered responsible for the formation, in long vertical tubes, of intractable plugs. (auth)

ABS>A statistical evaluation is presented of field data including measurements of alpha activity on work surfaces, in the environmental air; and the results of urinalyses obtained from employees assigned to a UF/sub 6/ manufacturing facility. Two years are studied wherein personnel were subject to relatively low concentrations of both soluble and insoluble normal uranium compounds. Approximately 700 urine specimens were collected and 500 spot-air samples, 4000 shift-length air samples, and 24 surface surveys were made. Statistical correlations of these data are presented, and a method is proposed for estimating the exposure potential of employee groups working in environments having varying uranium concentrations. (auth)

In an attempt to increase the efficiency, a proton recoil neutron spectrometer was built in which the proton detection crystal is in the shape of the surface formed by the rotation of the cos/sup 3/ THETA curve about the THETA = 0 axis where THETA is the angle between the direction of travel of the incident neutron and the direction of travel of the recoil proton. Such a construction makes the detector crystal conform to the range envelope of the protons recoiling from a neutron beam of sufficiently high energy into a gas in which the proton range is proportional to the 3/2 power of the proton energy. Sixteen pieces of thallium-activated cesium iodide were assembled as a mosaic arranged in the cos/sup 3/ THETA shape so that the maximum THETA was 30 deg . Calculations show that 25% of the protons recoil within 30 deg . The Po-Be snd Po-B spectra were measured with the instrument using xenon in the chamber. The resolution of the spectra obtained was low due to nonuniform pulse height response of the CsI crystal sections and excessive gamma-ray response even though sn anthracene proton radiator was used in a coincidence scheme designed to minimize …

A guide is presented for problems involved in counting methods and techniques used in avoiding or correcting . them. Beta, alpha, and gamma counting is treated. Among the items discussed are the geometry factor, absorption, scattering, and background. A bibliography of 164 references is included. (D.J.C.)

"This bibliography lists selected books, articles, and unclassified reports which have appeared in the following abstracts and indexes between August 1959 and December 1960."

Design data for BORAX V are presented along with results of hazards evaluation studies. Considcration of the hazards associated with the operation of BORAX V was based on the following conditions: For normal steady-state power and experimental operation, the reactor and plant are adequately shielded and ventilated to allow personnel to be safely stationed in the turbine building and on the main floor of the reactor building. The control building is located one- half mile distant from the reactor building. For special, hazardous experiments, personnel are withdrawn from the reactor area. (M.C.G.)

Introduction: Recently a new type of charged particle detector, the so-called spark chamber, has been developed. The detector has certain advantages in high energy physics over bubble chambers aside from its much lower cost.

A description is given of the design of a prototype "packaged" nuclear power plant. The purpose of the plant is to alleviate fuel oil logistics and storage problems posed by remote auxiliary DEW Line radar statibns north of the Arctic Circle. The ALPR (redesignated SL-1) is a 3 Mwt, heterogeneous, highly enriched uranium- fueled, naturalcirculation boiling water reactor, ccoled and moderated with light water. Steam at 300 psig, dry and saturated (421 deg F) is passed directly from the reactor to a conventional turbine-generator to produce electric power (300 kw nominal) and space-heating (400 kw) requirements consistent with rigid mechanical and structural specifications prescribed by the military, and dictated by the extreme geophysics prevailing at the ultimate site. The over all design criteria emphasize: simplicity and reliability of operation and maintenance, with minimum supervision; minimum on-site construction; maximum use of standard components; limited water supply; utilization of local gravel for biological shielding; transportability by air lift; and nominal 3-year fuel operating lifetime per core loading. The "packaged" concept is incorporated for the initial erection. The plant is not designed for relocation. The design criteria for the prototype necessitate special features. The fuel plates are clad with an alurninurn-nickel alloy (X8001). …

"The laboratory experiments and field testing which were carried out in the development of a homogeneous gas labeling device are described. Detailed drawings of the injector and its most critical components are included. Recommendations are made for a production model of the device along with estimated costs of construction."

Control of the exit temperature of the coolant from each fuel channel of the Hallam Nuclear Power Facility reactor is obtained by adjusting the coolant flow rate by a remotely operated variable orifice. Two variable orifices were designed and the hydraulic characteristics determined. Both orifice designs utilized a tapered plug moving in and out of a restricted flow passage at the upper end of the fuel channel. Data were obtained on pressure drop as a function of flow rate at different orifice plug positions; all measurements were made using water, and data were converted to equivalent values for sodium. Either type of orifice was capable of adjusting flow rate to match the power output of a fuel element at any location in the reactor core. The temperature sensitivity (change in exit temperature per unit change in orifice plug position) of the first type of orifice was low (lO deg F/in.) when used in combination with a central fuel element, and high (7OO deg F/in.) when used with a peripheral element. The temperature sensitivity of the second type was more uniform (varying from 90 to 250 deg F/ in.). Consequently, the second type of orifice was selected for the HNPF. (auth)

ABS>A review of laboratory diffusion studies on uranium and its compounds and alloys is presented. Included are results and analysis of studies on diffusion in single-phase and in multiphase U alloys, diffusion of gases in U, and diffusion in UO/sub 2/. (J.R.D.)

Oxide films were prcduced on Zr and Zr-Ti alloys by anodizing and by exposure to 02 and H20 at high temperatures. The electrical resistances of the films were measured in air at room temperature and in vacuum at temperatures up to 290 deg C. At room temperature, all films were insulators, although anodic films had the higher resistivities. Upon heating corrosion fiIms to 185 and 290 deg C, they became semiconducting. Corrosion films on Zr alloys containing 0.05 to 0.50 wt% Ti had relatively constant resistsnces, although the corrosion rates increased rapidly in this range and the films showed potential differences. For Zr alloys containing 10 to 95 wt% Ti, the film resistances decrease with Ti content amd potential differences were absent in most cases. The results indicate the measurements of the electrical properties of the corrosion films should be made during corrosion. (D.L.C.)

Liquid radioactive wastes are converted into solids, with volume reduction factors of 3 to 8, by flash drying on finely screened, porous, inert solid particles (e.g. alumina) in a fluidized bed at 320 to 550 deg C. The wastes may be either aluminum nitrate-containing wastes from the processing of MTR-type fuel elements, or Purex Process wastes. Ruthenium is found to be the only volatile fission product in this temperature range. Methods are described for its removal from the fluidizing gas. (T.F.H.)

The flux pesking facter resulting from the use of a seamed fuel thimble in CP-5 was determined experimentally and by diffusion theory calculations. A comparison of the two methods indicates that an underestimation of the magnitude and sharpness of the flux peak is obtained from the diffusion calculations. Based on this comparison, a conservative calculation of the peaking effect which would result from the use of seamed fuel tubes in CP-5 indicates a maximum local power-peaking factor of 1.10 and a maximum fuel surface temperature 3 deg C above that obtained with extruded tubes for the same total reactor power and the same flow conditions. (auth)

The results of a critical-experiment program conducted to study the Hallam Nuclear Power Facility (HNPF) reactor concept and to verify design parameters are presented. Experimental procedures and results are given, and comparisons are made with calculational techniques currently in use for determining the nuclear characteristics of the HNPF reactor. (auth)

From introduction: "Once-Through boiling of water to 100 per cent steam quality was successfully accomplished. Results of Departure from Nucleate Boiling, transition, and film boiling tests are presented."

Two thin plates of high-density UO/sub 2/ were sandwiched together with thermocouples between them and pressed against the outer surfaces. The thermocouples were used as electrodes and the electrical resistivity of the UO/sub 2/ measured by the potential drop method using corresponding arms of the thermocouples as current lead-in wires and potential probes. The UO/sub 2/ was heated by its own fission heat and the electrical resistivity measured at temperatures from 50 to 972 deg C. Preirradiation measurements were made using an electric furnace to obtain temperatures to 750 deg C. Electrical resistivity did not change with irradiation up to about 10/sup 1//sup 8/ nvt, at which point the resistivity decreased by a factor of 3. The resistivity ranged from 8.75 x 10/sup 3/ ohm-cm at room temperature (before irradiation) to 0.4 ohm-cm at 773 deg C (after nvt > 10/sup 1//sup 8/). The activation energy was 0.5 ev during irradiation as compared with 0.65 ev before irradiation. The temperature between the plates was higher than the outside temperature during irradiation. This thermal gradient created a thermoelectric emf between the UO/sub 2/ and the platinum thermocouples. The thermoelectric emf for the Pt-UO/sub 2/-Pt system ranged from 130 mu v/ deg …

The methods of successive displacements or relaxation methods are investigated for a class of nonlinear problems. In particular it is shown that these methods are applicable to a large class of nonlinear problems arising from variational problems which yield elliptic equations. Constructive existence and uniqueness theorems are presented for the discrete problem and criteria are given for a practical method of obtaining solutions. The example of a discrete Plateau problem is used to illustrate the feasibility of the results. The processes are also shown to apply to uniformly elliptic problems.

Strontium recovery from Purex 1WW was investigated with simulated feeds and tracer activities. Initial experiments demonstrated recovery of over 70% of the strontium by sulfate precipitation from partially neutralized 1WW by either increasing the sulfate concentration to about 3 M or by adding carriers such as lead. Precipitation of iron was avoided by addition of one or more moles of tartrate per two moles of iron. Precipitation at elevated temperatures and addition of lead after pH adjustment were shown to be beneficial. Strontium recoveries of over 95% were achieved by precipitation at about 80 deg C at pH values of 0.4 to 4.0 with sulfate concentrations of 0.67 to 3 M and over 0.02 M lead carrier added. High sulfate concentrations were required at low pH, but the sulfate concentration is not critical above pH 1. Some separation of strontium from cerium was observed at pH 2 to 4, with the degree of separation being dependent on both tartrate concentration and pH. Recovery of strontium from the sulfate precipitate by leaching with nitric acid, sodium acetate, or oxalic acid was unsatisfactory because of the large volumes required. Metathesis with sodium hydroxide removed most of the lead as plumbite and converted …

Measurements of material bucklings for graphite uranium systems are summarized. A comprehensive listing and guide to the original data sources is provided. Complete information on physical and nuclear properties of the lattice and the geometry of the exponential assembly is included, along with some of the auxiliary data taken. The fuel sizes vary from 0.925 to 2.5 in. in diameter for five different fuel geometries. The lattice spacings vary from 4 3/16 to 15 in. Over 300 measurements of material buckling are included. (auth)