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 condenser-discharge method of conducting molten metal- water reactions at high temperatures was refined. Two methods to measure energy input to specimen wires and, therefore, to compute initial metal temperatures were developed. Calculated metal temperatures were estimated to be accurate to within 100 deg C. Two reaction cells were designed, one for operation at atmospheric pressure with water at room temperature, and the other for operation at high pressure and with water at elevated temperature. Means were developed to determine the surface area of metal exposed to reaction and to determine the total extent of reaction. Pressure transducers were used to record the rate of reactions. The zirconium- water reaction was studied with initial metal temperatures from 1100 to 4000 deg C with 30 and 60-mil wires in room-temperature water. Initial pressures in these runs were the vapor pressures of water at room temperature (20-30 mm). Runs were made with 60-mil wires in water heated to 200 deg C (225 psi). Results in room-temperature water indicated that the reaction became explosive at an initial metal temperature of 2600 deg C. Below this temperature, 20% or less reaction occurred. At higher water temperatures, reaction ranged from 40 to 70%. Runs in …

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)

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 …

"The present work describes some computer-oriented techniques for the application of the laws of quantum mechanics to the problems of determining basic structure of diatomic molecules. At times, calculations of the type described here yield results which can be compared directly with experiment to check the validity of the hypotheses and technique used they may predict the results of unobserved experimental phenomena; and, in many instances, they provide quantities which are necessary for the interpretation of experimental data but which cannot be directly measured."

The solubilities of uranyl dlbutyl phosphate, uranyl monobutyl phosphate, ferric dibutyl phosphate, and ferric monobutyl phosphate were measured in aqueous nitric acid solutions ranging from 0 to 3 M and in 30% TBP in Amsco 125-82 solution containing 0--0.7 M HNO/sub 3/. For the respective compounds in the aqueous phases, as the acidity increased from 0 to 3 M, the solubilities increased from 0.004 to 0.7 g U/liter, O.O5to 50 g U/liter, <1 to 30 mg Fe(III)/ liter, and 0.003 to 3 g Fe(III)/liter; corresponding solubilities in the organic phases increased with acidity from 14 to 165 g U/liter, 11 to 110 g U/liter, <O.5to 4 mg Fe(III)/liter, and <0.002 to 1.5 g Fe(III)/liter. All these compounds foamed or formed very flocculent solids in the aqueous phases snd tended to settle slowly in the organic phases and rise to the surface in the aqueous phases, suggesting that they would be interface seekers in two-phase aqueousorganic systems. (auth)

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 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)

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)

A program is described which is devoted to heat transfer and pressure drop measurements on single tube sections with coolant flow only on the inside. The tests were conducted on simulated PM-1 fuel elements. Data are included and data reduction methods are discussed. (J.R.D.)

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The Livermore 90 deg inch variable-energy cyclotron was used to measure the 90 deg excitation function for the Al/sup 27/(p, gamma )Si/sup 28/ reaction. Proton energies between 5 and 13 Mev were used which gave excitation energies in Si/sup 28/ corresponding to the region of the photonuclear giant resonance. Two gamma rays were observed: gamma /sub O/, the groundstate gamma ray and gamma / sub 1/ resulting from deexcitation through the first excited state of Si/sup 28/ at 1.78 Mev. They were detected by a 5-in.-diam by 6-in.-long NaI(Tl) crystal. A Pb collimator was used to improve the resolution of the detector. The results indicated that both gamma /sub O/ and gamma /sub 1/ display the giant resonance behavior; the gamma /sub O/ carve reached a peak value of approximately -8 mu barns/sr at E/sub p/ = 8.75 Mev, while the gamma /sub 1/ peak was approximately -14 mu barns/sr at E/sub p/ = 10 Mev. Both curves displayed the fine structure previously reported by Gove et al. A detailed balance calculation was made, using the gamma /sub O/ data. A comparison with the measurements of Johansson on the total yield of protons from the Si/sup 28/( gamma ,p)Al reaction …

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 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)

The High Flux Beam Reactor, HFBR, is cooled, moderated, and reflected by heavy water and designed to produce 40 Mw with a total epithermal flux of ~1.6 X 10/sup 15/cm/sup -2/ sec/sup -1/ and a flector thermal maximum flux of 7 X 10/sup 14/ cm/sup -2/ sec/sup -1/, using a core formed by ETR plate-type fuel elements in a close-packed array. The hazards summary is given in terms of site description, reactor design, building design, plant operation, disposal of radioactive wastes and effluents, and safety analysis. (B.O.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.

The transmission coefficients T/sub l/ and total reaction cross sections sigma /sub R/ for alpha particles from 0 to 46 Mev interacting with twenty target nuclei with atomic numbers from 10 to 92 are calculated with optical model program in which a previously determined complex nuclear potential is utilized. The dependence of the T/sub l/ values, and hence of sigma /sub R/, on the Woods- Saxon parameters is investigated as a function of projectile energy. The optical model reaction cross sections are compared with those derived from a square-well potential and a model which approximates the real optical model potential barrier by a parabola and makes use of the Hill-Wheeler penetration formula for a parahelic potential. (auth)

ALPR fuel plates were converted into tubular fuel elements for use as additional fuel for the CP-5 reactor. fabrication was carried out by introducing a cross-roll step in the ALPR rolling schedule and roll-forming tubes from these plates. (D.L.C.)

Results are reported from a radiological survey of the diagnostic x-ray facility to determine the levels of exposures encountered in scattering under normal operating conditions. A survey was made of the air dosages received by operating personnel and those undergoing diagnostic study. The results indicate that, the exposures received by operating and subject personnel do not approach permissible levels recommended as maximum by the National Committee on Radiation Protection. (C.H.)

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 …

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

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.)

As a part of the RAIL feasibility study, Operation Dorothe (March 1961) was conducted to determine if a liquid explosive could survive the acceleration of launch from a 155 mm howitzer. This operation was successful, although some structural difficulty was experienced with the test round (C-90). Upon completion of that exercise, it was decided to design a test round that could be used with the more viscous slurry-type explosives, and to fire several of these new rounds with inert filler prior to their use with slurry High Explosives (H.E.), precluding the difficulty previously experienced. The C-91 projectile, is a modified M107 H.E. round. It has been reduced in weight, equipped with an obturator, and provided with a large fill orifice. The rotating band has been altered to eliminate rotation. Internally, a plastic plug is used to control column height. A piston-type `O` ring seal prevents gun gas from reaching the interior to the projectile. Four of these projectiles were fired from a 155 mm howitzer at 15,500 g`s, plus. They survived not only the launch, but also impact and repeated ricochet in sand, gravel, and small rock. No leakage of the inert filler (glycerin) occurred. All rounds were destroyed with …