It is necessary to provide accountability tables and equations for use in routine product buildup predictions for the duration of the E-N and blanket loads charged under PT-IP-350-C. Recommended values are given.

Report regarding an airborne gamma-radioactivity survey that took place in the 2,800 square mile area around the Los Angeles region in California. Topics include the types of bedrock noted in the area as well as their levels of radioactivity.

Abstract: "The pressure drop and the time-temperature variation of the air test medium and heat storage material in a pebble-bed heater (designed for intermittent hypersonic wind-tunnel operation at test section Mach numbers of 4 to 11) are presented."

The purpose of this document is to characterize, as completely as possible, the stored energy distribution in D Reactor as of March 1958, the date of the last stored energy survey and to estimate the temperature rises which can be expected to occur during a stored energy release. D Reactor was chosen for this study only because it represents one of the oldest operating Hanford reactors and not because of any circumstances peculiar to this reactor. 14 refs., 13 figs.

A graphical compilation is presented of atomic and molecular cross sections of interest to controlled thermonuclear research. The cross sections are shown, as a function of energy, for collision processes involving molecular ion dissociation, charge exchange, excitation, ionization, photoionization, scattering, energy loss, and recombination. Pertinent nuclear cross sections are also included. A bibliography is given covering the literature since 1950. (auth)

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 calculation of tritium beta energy absorption in spherical bulbs filled with mixtures of tritium and other gases is ' carried out under the empirically substantiated assumption that the energy absorption per spherical shell surrounding a point tritium source is representable by a pure exponential function. Primary and successive backscattering at the wall of the vessel is taken into account by means of a very approximate calculation. The computed energy absorption function for hydrogen gas in a silvered bulb agrees within plus or minus 3% over a wide range of gas pressure with the one available set of spherical ionization chamber data. (auth)

A carrier-free separation of hafnium from several hundred milligrams of rare earth oxides by anion exchange from saturated HC1 solution is given. The procedure is completed in 4-8 hours and is suitable for remote control work.

Pu nitrate production was above revised forecast. 141 kCi Sr-90 was isolated in Purex and stored for decay; to date, 1190 kCi has been recovered from Purex wastes. Casks of Cs-137 and Sr-90 were turned over to AEC for ORNL. Production of UO{sub 3}, Pu metal buttons, and weapon component fabrication exceeded forecasts. Purex processing continued until April 14. The Purex neptunium campaign had low yield because of loss to waste system. The cartridge in the Purex co-decontamination column scrub section was replaced with a new design. After the Redox organic distillation pot was replaced, {gamma} activity in Redox recovered hexone increased 300 {times}; product quality returned to normal after the faulty steam traps were replaced. Fabricated parts underwent dimensional changes after machining and gaging; part dimensions have been altered to compensate. Design for the proposed caisson-lateral leak detection system was revised to contain 3 horizontal laterals beneath each tank and 7 vertical wells around each tank. A ratio exists between the Cs-137 in the coating waste solution and the total U in liquid and precipitate phases. (DLC)

ICPP Operations. Changes made in processing equipment are described, and the use of continuous steam stripping to free waste solvent of Pu is described. Agueous Processing Studies. Studies were made of methods for separating Zr from dissolver solutions of U-Zr alloys. Recovery of U from BeO/ sub 2/-UO/sub 2/ ceramic fuels by grinding-leaching technique using boiling HNO/ sub 3/ reached 75 to 80%. Waste Calcination. Test results of feed spray nozzles for use in the Demonstrational Waste Calcining Facility are given. Studies were made on the calcination of aluminum nitrate and zirconium fluoride waste solutions. Waste Treatment. Removal of Cs and Sr from wastes by adsorption was investigated. The conditions for optimum separation of Fe, Ni, and Cr by Hg cathode electrolysis from waste solutions resulting from processing of stainless steel reactor fuels were determined. Electrolytic Dissolution Systems. The electrolytic dissolution of type 304 stainless steel was studied in the transpassive region as a function of electrode potential and HNO/sub 3/ concentration. An analog simulation study of an electrolytic dissolver is described. A niobium cathode in an electrolytic dissolver dissolving stainless steel in boiling HNO/sub 3/ did not absorb H/sub 2/. The corrosion resistance of several container materials to 1 …

Abstract: The acid hydrolysis of [Pt(NH3)3Cl] has been shown to occur to a measurable extent. for this reaction: [APt(NH3)cCl]+ + H2O [chemical equilibrium symbol with rate constant k-1 above and k1 below] [Pt(NH3)c(H2O)]++ + Cl-, the equilibrium quotient was measured at 25 degree C and 35 degree C. At 25 degree C this quotient was 8.4 x 10-5 at [Mu] (ionic strength) = 0 and 25 x 10-5 at [mu] = .318 M. This variation is consistent with the expected changes in activity coefficients. [Delta]H for the reaction was found to be approximately 0. The rate constant, k1 was 2.3 x 10-5 sec.-1 at 25 degree C and it was nearly independent of ionic strength. The acid hydrolysis provides a mechanism for the exchange of the chloride ligand and Cl-. Exchange experiments with Cl36 showed that in addition to the acid hydrolysis, a process, first order in both, [Pt(NH3)3Cl] and Cl- with a rate constant of 6. 10-5 sec.-1M.-1 contributes to the exchange. The behavior of the entire series of chloro-ammines of platinum(II) toward acid hydrolysis and chloride exchange has been summarized, and a likely mechanism for the process has been discussed.

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)

"Graft polymers were made by Co60 mutual irradiation of mixtures of styrene and methyl acrylate in contact Teflon. These graft copolymers were analyzed by infra-red absorption and their composition determined. The composition of the graft copolymer formed from styrene and methyl acrylate was different from that which is predicted by the copolymer composition equation."

Graphical presentation of K-factors for eight isotherms, published data on the solid-vapor region, and a bibliography of approximately 450 references.

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 test was performed on June 19, 1959 to determine the capacity of the Core Removal Cooling System for removing reactor decay heat under split-flow'' conditions. The system operated satisfactorily during this test; the pumps developed a flow of approximates 73 gpm at a total head of 254 ft water, as compared with their rated capacity of 75 gpm at a total head of 250 ft water. (D.L.C.)

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.)

The ACIR Library is composed of publications that study the interactions between different levels of government. This document addresses county areas of declining population, 1950-60.

BS>Critical studies of a fast reactor core containing a simulated oxide fuel having an oxygen-uranium atomic ratio of 1: 1 are described. Calculated and experimental critical masses are compared. Experimental results are given for fission ratio, central reactivity coefficient, fuel bunching, and distributed worth measurements. (auth)

Critical studies were made with a simulated, large, dilute power reactor having uranium carbide as fuel. The uranium in the core was 30.7% enriched, and the atomic ratio of uranium to carbon was 0.946. The critical mass was 503.01 kg U/sup 235/ and the critical volume 574.47 liters. Central reactivity coefficients, effective fission crosssection ratios, heterogeneity effects, reactivity worth of distributed materials, foil irradiations, and the average prompt neutron lifetime were measured. Multigroup calculations using the Yiftah, Okrent, and Moldauer crosssection set overestimated k for the critical configuration by 4.7%. (auth)