Summary: "Criticality was considered impossible in any contingency encountered in practice under either of the following conditions which include no safety factor: (a) In any isolated cylinder not more than 5 in. in disruptor, if the total amount of U235 present does not exceed 7.5 Eg. (b) In an isolated vessel of any shape and size, if the total amount of U235 present does not exceed 880 g. An "isolated" vessel is one which does not "see" more than 0.1 [...] other vessels containing fissionable material."

The radiolytic decomposition of tributyl phosphate has been show by burr to product gases, acids, and polymers. the acids that are formed can limit the usefulness of tributyl phosphate for the processing of radioactive materials. The study of acid formation on radiolysis therefor becomes important to us for the understanding of the mechanism of acid formation, the influence of added materials and the effect of the structure of organo- phosphorous compounds. Samples of purified esters have been irradiated in the ORNL cobalt source. Conclusions: (1) The formation of acid from tributyl phosphate during irradiation with cobalt gamma rays involves a mechanism that is not a primary step. Evidence has been obtained for a secondary reaction that is minimized by the presence of certain compounds. (2) Toluene acting as an inhibitor for radiolytic formation of acid may indicate the usefulness of an aromatic hydrocarbon diluent in processing. (3) The aromatic hydrocarbon, when phenyl, was not effective when it was part of the molecule. (4) First tests revealed that dibutyl butyl-phosphonate produced less acid the TBP and may warrant further consideration for process application.

In the memorandum entitled "Stored Energy in BNL Reactor Graphite", dated February 25, 1953, there is described an experiment conducted by Gurinsky's group to determine the energy per gram of irradiated graphite released in a 200°C anneal. Similar experiments were subsequently conducted by W. Kosiba, differing from the original in two particulars: a) Instead of two graphite samples, one normal, and one irradiated, Kosiba used only an irradiated sample which he heated first to release the stored energy, and then again after the energy was released. In this way, he obtained time against temperature curves for both normal and irradiated graphite from the same sample. (These curves are graphed for each run in Figs. 1 thru 5.) b) The vycor tubing used in the original experiment was not used by Kosiba. Five runs of this experiment were selected, Runs 4P, 13, 36, and 40 at furnace temperatures of 200°C, and Run 45 at a furnace temperature of 400°C.

Thesis describing a research conducted to extend observations on nuclear energy levels and how they effect the nucleus itself, and an investigation on the gamma rays associated for the even-even isotopes and to obtain additional data for the oddmass neclei in the hope that more regularities will become apparent for that class of nuclides.

"The resonant frequencies of the magnet power supply are investigated. It is found that there are eleven resonant modes in addition to the desired mode of operation with six additional resonant frequencies. From measurements of the choke model, it appears that the frequencies of some of the spurious modes may lie in the same range as the desired mode of operation."

Five continuous coatings were produced on zirconium coupons using an anodizing technique. These layers appear to be quite adherent and not subject to visible or audible failure caused by flaxion of the basis metal, Their abrasion resistance, though not investigated thoroughly, appears to be moderately good.

In order that fairly accurate thermal stress calculations can be made on the ART, it is necessary to have a reasonable picture of the temperature distribution in the reactor. To get the temperature distributions, and to determine cooling requirements in various parts of the reactor, one must know the heat deposition rates due to alpha particles, beta rays, gamma rays, and neutrons in all parts of the reactor. The present report contains only the basic physical data necessary to determine the heat deposition rates due to gamma rays. Neutron fluxes in the core and reflector regions of the ART are to be obtained from two-dimensional multigroup calculations (performed by the Curtiss-Wright Corporation). These fluxes, in conjunction with the neutron absorption cross sections, determine the neutron capture and inelastic scattering rates in the core and in the reflector. The data in this report permit the calculation of the number of gamma rays originating at various energies at every point in the core and reflector.

The purpose of the test was to determine if the 1A Canal Water System Demineralizers can be satisfactorily charged with resin. The 1A Canal Water System Demineralizer was satisfactorily charged with resin and conductivity of the demineralizer effluent was less than 0.1 microbes as specified in the Test Procedure.

Quarterly progress report on various research projects conducted at the University of California Radiation Laboratory

The following report describes a study that was made to adapt a redox method that oxidizes uranium(IV) to uranium(VI) by ferric ion into a microcoulometric method.

The following report describes x-ray diffraction patterns of various compounds of americium and its crystal structures.

The behavior of light and heavy water solutions of boric acid toward pile radiations has been investigated as a function of boric acid concertation. A study has also been made of the effect of hydrogen, hydrogen peroxide, and potassium iodide on the radiation stability of boric acid solutions.

The purpose of the test was to obtain data on the decontamination factors for Cesium-136, Cesium-137, Strontium-92, one hour gross iodine and Iodine-131. This data will be used to determinate efficiency of lithium hydroxide resin for removing radioactive cations and anions. The denomination factors for a particular demineralizer using lithium hydroxide resign were found to vary for different radioisotopes. This variation was from 2.3 for Cesium136 to 77,000 for gross iodine.

The coefficient of linear expansion of alpha plutonium has been determined for the range -180 to +100 degree C by the silicon-tube and dial-indicator method. The value of the expansion coefficient is reported as [formula]. Included are a detailed description of the apparatus and a discussion of the method.

The following report describes methods developed for determination of uranium in the alloy.

At the request of 234-5 Development, studies of a system for controlling plutonium powder transfer were undertaken by Process Equipment Development. This report presents details of equipment designed to fulfill requirements and proposes equipment for installation on additional Hot Button Line prototypes.

From introduction: "The purpose of this report is to present some design and construction data for automatic titrators."

Abstract: "The results of this investigation that it is necessary to remove fluoride prior to precipitation zirconium with mandelic acid or phenyl arsonic acid. Fluoride, however, has little effect on the cupferron method of precipitation. The discovery that zirconium fluoride is soluble in a mixture of aqua regia and sulfuric acid made it possible to dissolve the material without the addition of fluoride from hydrofluoric acid."

Primary control of the PRTR is achieved by regulating the level of the heavy water moderator which is held in the reactor vessel by a helium gas balance system. Emergency shutdown is effected by a gas-balanced moderator dump system which drain the moderator from the calandria at a rapid rate. This report presents a quantitative appraisal of the reactivity effects due to moderator level changes in controlling or scramming the reactor. In conjunction with the reactivity calculations, solutions were obtained which yield an evaluation of vertical flux or power distributions for any positioning of the moderator level. Coupled with the radial distributions for a given fuel loading, this information is useful in obtaining the value of the maximum specific power associated with a given power of operation and moderator height. The calculations were made using VALPROD, a one dimensional, multigroup diffusion theory reactor code programmed for the IBM-650 computer.

"The effect of correcting quadrupole lenses on the betatron oscillation characteristics of an AG synchrotron was studied, and general formulas are given for the fractional changes of the amplitude and phase functions. Calculations performed for different setups of different numbers of lenses for the CEA synchrotron structure point out that one may correct for sizable errors in the n- value by means of 8 pairs of quadrupole lenses in two consecutive straight sections with the focusing lens between defocusing sectors and vice versa. An increase of BETA /sub max/ of about 5% is obtained for DELTA n/n approximately 0.04. It was found that the necessary corrections can probably be obtained satisfactorily with lenses of 6 in. length. "

Preliminary results of tests wit the Westinghouse 100A pump indicate that Al2)3 and tungsten carbide coated bearing-journal assemblies prepared by the Linde process are not promising as substitutes for the graphitar-stellite combination. The front Al2O3 assembly failed at start-up with water and both front and rear tungsten carbide assemblies failed after 121 hours with water at 245 C.

Purpose: "In order to determine the optimum procedure for sampling the coarse-feed tank (C-102) of the NP and MTR process, a systematic series of tests has been conducted to measure the extent of solution stratification and effect of air-sparging as a means of vessel homogenization."

Abstract: "Type 347 stainless steel was selected for SIR applications requiring resistance to corrosion in sodium on the basis of limited corrosion data and extrapolation of experience in aqueous media. Subsequent testing indicated that carbide stabilization was not necessary for good resistance to corrosion in sodium. Evaluation of the unstabilized grade of 18-8 stainless steel, Type 304, was intensified because it offered a number advantages over Type 347. Type 304 was more readily available, required fewer strategic materials, was less expensive, and was reported to be weldable with less difficulty. From the results of this investigation, it appears that Type 304 can be substituted for 347 for all SIR applications where the slightly higher elevated temperature strength of 347 is not required."

The following report examines primarily water and air factors that affect the quality of vacuum induction-melted uranium, yet follows experiments with other factors such as graphite and zirconium crucibles under dry and wet conditions, usage of hydrogen, oxygen, CO and other subject admitted to determine pressure-time relationships and residual gas compositions, as well as a study of water-gas reaction within the furnace.