The disassembly of the `Adams` primary was scheduled for April 28, 29, and 30, 1959. The method of disassembly is provided as a procedure to be accomplished in order and the time and initials of the person accomplishing each step recorded.

This report addresses air-core strong focusing synchrotron.

This production test was designed to evaluate the suitability of low hydrogen dingot uranium as routine process material. Nine tubes of I and E fuel elements (6 dingot, 3 ingot) with 32 fuel elements in each tube, have recently been discharged at the C Reactor and this document contains the results of analyses made on the dimensional stability properties of this material.

Angular distributions in SIGMA /sup +/ decay are analyzed for informatlon on SIGMA spin and parity conservation in SIGMA production. No evidence for a SIGMA spin > 1/2 or parity nonconservation in SIGMA prodiction is found. (auth)

A device was developed for detecting the failure of a fuel element in a reactor by monitoring for the presence of gaseous fission products. Small amounts of gaseous fission products were detected in the presence of radioactive argon by separating the fission product gases from the argon by chromatography. An automatic sequencing device was provided for taking samples at short intervals to ensure rapid detection of failures. (auth)

A brief survey of decarboxylation reactions and carboxylation reactions that are known or presumed in biological systems will be presented. While a considerable number of amino acid decarboxylations are known, their mechanisms will not be included in the present discussion but will be reserved for a later paper in the symposium. The remaining decarboxylation reactions may be subdivided into oxidative and nonoxidative decarboxylations. In most cases, these reactions are practically irreversible except when coupled with suitable energy-yielding systems. The carboxylation reactions which are useful in the formation of carbon-carbon bonds in biological systems seem to fall into two or three groups: those which exhibit an apparent ATP requirement, and those which exhibit a reduced pyridine nucleotide requirement, and those which exhibit no apparent ATP requirement. Of the first group at least four cases, and possibly six or seven, are known, and one interpretation of them involves the preliminary formation of 'active' carbon dioxide, generally in the form of a carbonic acid-phosphoric acid anhydride. Those exhibiting no apparent ATP requirement seem to be susceptible to classifications as enol carboxylations in which the energy level of the substrate compound is high, rather than that of the carbon dioxide. There appear to be …

Production of Pu, UO{sub 3}, and Pu metal exceeded forecasts. The 2nd attempt at Purex to recover Zr-Nb resulted in about 1/3 recovery, contaminated with about 1% of the Ce. Palm losses to Purex U product were eliminated, and the Pu content was reduced 5 to 10{times}. Routing the dissolver rinses into 3WB concentrator resulted into improved rinsing efficiency. Unclarified feed was processed through Purex HA column. In a test for using B in Redox, the B was routed completely to the waste; it was not detectable in product streams beyond the first cycle. Almost 1000 g Palm was purified and converted to oxide. Ferrous ion catalyzed the reduction of Palm VI by hydrazine or semicarbazide. Coordination of E-metal and NPR reprocessing at Redox in multipurpose dissolver was studied. An interim fission product recovery program at Purex will be directed toward low-efficiency collection of Pm {sup 147}. Locations for critical incident alarms were selected. (DLC)

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Two alternate systems, acetic acid-nickel and acetic acid-cobalt, were examined for possible replacement of the corrosion system: ferric chloride-nickel which is being used in the current transpiration corrosion protection studies. Two Fluorox fluidized bed runs were made, of 9 and 58 hr duration, in which dry air and oxygen were used as oxidizing and fluidizing gases. Tests of the hydroclone classification of thoria indicated that more than 95% of the +0.5 micron particles can be removed from a sample if 50% recovery of the -0.5 micron particles is acceptable. Fluidized bed denitration of ThNT did not produce large dense ThO/sub 2/ particles, but flame denitration of mixed thorium-uranium- aluminum nitrates produced spherical particles. Three alternate batch Darex flowsheets gave chloride removal to less than 350 ppm with 61% nitric acid feed, while dissolution studies of APPR fuel elements showed that complete dissolution of braze metal in aqua regia may be difficult. Leaching studies of unirradiated UO/sub 2/ pellets showed that the most important variable effecting dissolution rate was the total nitrate content of the dissolvent. Delivery of tae SRE decanning equipment was scheduled for April 1, 1959. Temperatare increases in cylinders of solid radioactive waste were calculated for APPR fuel …

This study was undertaken to determine the most feasible and economical process or path for closing the uranium fuel cycle at HAPO, and to establish what benefits, other than improvement in FPD`s competitive position, would result from the selected closed fuel cycle. The study was separated into four phases; Phase I includes the selection and organization of plausible processes and the establishment of a realistic and effective evaluation procedure, Phase II will include evaluation and selection of an optimum path based on a medium range and a short range approach (5 to 10 years), Phase III will include evaluation and selection of an optimum path based on a long range approach (> 10 yrs.), and Phase IV will include refinement of previous work and issuance of a final report summarizing the study and the conclusions or recommendations which develop from the study. Phase I of the study has been completed. The purpose of this paper is to document the assembled data and the completed work.

General relationships are developed for the performance of continuous flooded dissolvers based on complete mixing, such as tank flow, uniform packing characteristics of metal, and a first-order rate law. The form of the final equation is the same as that derived for the nonmixing or tube-flow case discussed in earlier reports of this series, with differences appearing only in the term that expresses the concentrations of metal and dissolvent in the liquid phase. The relationships are applied to available pilot plant data on the mercury-catalyzed dissolution of four shapes of 2S aluminum elements. The data cover a range of catalyst concentrations from 1.5 x 10/sup -6/ to 3.75 x 10/sup - 4/ molar Hg/sup 2+/ and metal bed heights from 1 to 10 feet in a 2-inch pyrex column. The average initial dissolvent concentration was 5.6M nitric acid. Round rods, flat plates, tubes, and flattened tubes are compared. The data for the round rods are utilized to determine the effective reaction velocity constants at the various catalyst concentrations. The general dissolver equation is used to predict the effect on dissolution rate of the shape of metal elements, liquid phase flow rate, and height of the bed of elements. Calculated rates …

OR XLS 1-5 is a program for structure factor calculation and for the least squares refinement of crystal structures using x-ray or neutron diffraction data. The code is divided into five segments, and the purpose of each is briefly described. (W.D.M.)

The CUREBO code for the IBM 704 is described. The code is divided into three parts including the calculation of nuclear cross section of the various physical components of a reactor (WOX7), the solution of the multigroup diffusion equations in two-space dimensions in order to find neutron fluxes and sources for an operating reactor containing these components ( CURE), and the calculation of fuel and poison depletion as a result of operating this reactor under steady- state conditions (BO2). (auth)

A controlled-temperature irradiation capsule was operated containing small fueled specimens at 160O to 1650 F. The design involved calculating the specimen heat-generation rate and designing an insulating gas gap around the specimens to achieve the desired temperature. Electric heaters were inserted to help control temperature. The thickness and composition of the gas gap were modified prior to operation on the basis of information on probable neutron flux obtained from a nuclear mock-ups and on the basis of information on the thermal resistance of various gas annuli obtained from a thermal mock-up. The desired irradiation temperature of 1625 F was achieved with a variation of sintering time 25 F. (auth)

A brief summary, with reference literature for details, of pertinent and important process flowsheet conditions which are in use in the Purex Process is presented. (auth)

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For the determination of milligram quantities of uranium(N) in thorium oxide-uranium oxide mixtures which may also contain uranium(VI), it was necessary to devise a means of dissolving the sample so as to prevent any air oxidation of the uranium(IV) to uranium(VI). For this determination, the conventional potassium dichromate volumetric method was used except that the sample was dissolved under reflux in 7 M H/sub 3/PO/sub 4/ which contained an excess of standard dichromate solution. Following the dissolution of the sample, this excess was determined by back titration with a standard solution of iron(II). Barium diphenylaminesulfonate was used as the indicator. Initial tests on the dissolution of samples of thorium oxide-uranium oxide in hot HC1O/sub 4/ and hot HCI are described. (auth)

Results of a study concerned with the problem of retarding the diffusion of fission products through unclad graphite fuel elements are presented. The pertinent parameters are pointed out, and their relations with the properties of graphite and gas coolants are considered. The effects of parameter variation on the concentration in the reactor primary system and the fission-product diffusion rate into the primary system are also examined. (J.R.D.)

A method for the direct determination of uranium in a cyclohexane solution of tri-n-octylphosphine oxide (TOPO) is presented. The adduct, UO/sub 2/ Cl/sub 2/ x 2TOPO, that is formed when uranium(VI) is extracted from hydrochloric acid solutions by tri-n-octylphosphine oxide absorbs light in the ultraviolet region. This absorbance is measured at 230 m mu vs. a TOPO-cyclohexane solution that was contacted with hydrochloric acid of the same concentration as that in the test aliquot. The molar absorbance index is 5500. The method is not selective; of the elements that are extracted by TOPO from hydrochloric acid, iron(III), zirconium, molybdenum, tin and thorium, only thorium can be tolerated. (auth)

BS>The ten transuranium elements discovered since 1940 are discussed in chronological order. The discoverer, the history, and methods used are given for each element. Future developments in the discovery and preparation of transuranic elements are discussed. (A.C.)

Economic aspects of nuclear power development in the U. S. are tabulated and graphed. Included are figures on presently operating reactors as well as those contemplated or scheduled. Also a brief description of the objectives of short- and long-range programs is given as well as tables listing some of the characteristics of each reactor. (J.R.D.)

A study was made of the effect of carbon, manganese, oxygen, palladium, and sulfur on the structure and fabricability of iron-35 wt.% chronium-1 wt.% yttrium alloy. Using a vacuum-induction melting technique each of the additives except oxygen was introduced to 1-lb remelts of a single 15-lb master alloy. The master alloy and remelts were made under similar melting, pouring, and casting conditions. Oxygen was introduced as Fe/sub 2/0/sub 2/ by inertelectrode arc melting to avoid extraneous, uncontrolled contamination stemming from crucible contact. Photomicrographs were prepared of as-cast metal illustrating structural variations. Ingots obtained were fabricated to 0.050-in. sheet at 2000 deg F to compare fabrication characteristics with those of the control ingot containing no additives. As a qualitative measure of metal soundness and ductility, a portion of each of the 0.050-in. sheets was further reduced at room temperatare to 3-mil foil. During melting at 2900 to 3000 deg F under controlled conditions, the amount of yttrium present in the charge was reduced roughly 50% by reaction with the alumina crucible. Sulfide, added as FeS, and oxide additions also lowered the amount of yttrium retained in ingots. The maximum amount of sulfur retained in an alloy of nominal composition iron-35 wt.% …

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Uranium dioxide pellets sealed in Type 316 stainless steel containers with a helium gas were irradiated in helium and in C0/sub 2/ in thermal fluxes or the order of 1 x 10/sup 13/ n/(cm/sup 2/)(sec). Cladding-surface temperatures were reportedly between 1200 and about 1800 F. The hot-cell examination performed by BMI showed that there were no obvious effects of the irradiation on the specimen tested in helium. However, the specimen irradiated in the presence of C0/sub 2/ exhibited severe cladding-CO/sub 2/ reaction and possible central melting of the UO/sub 2/. Although comparisons between pre- and postirradiation data were difficult because of involved fabrication history of the specimens, the tests did further establish the fact that helium is a satisfactory coolant gas for stainless steel cladding material at a temperature of 1200 F. The data obtained from the specimen tested in the presence of C0/sub 2/ indicate that at temperatures in the range of 1600 to 1800 F Type 316 stainless steel is not compatible with C0/sub 2/. (auth)