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 …

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 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)

Preliminary studies were made of the relationship between the size of particles suspended in the lower atmosphere and the amount and nature of radionuclides they contain. Emphasis was placed on the distribution of strontium90. From a limited number of analyses, it was found that strontium-90 is associated primarily with particles below 0.1 micron in diameter. Preliminary studies were made of scavenging of particles by liquid water droplets. Studies are included of sticking probability and the effects of Brownian motion and water vapor diffusion. It was found that electrostatic effects are of primary importance for 1.9-micron (mean volume diameter) particles. Brownian motion and water vapor diffusion did not contribute to the scavenging. These results are based on known and new equations derived for various scavenging conditions. (auth)

This test will determine approximately the relationship between the power rate of rise indicated by the power rate meter and the actual pile power, rising period, and power rate. The actual pile power and power rate cannot be measured accurately during rapidly changing conditions; it is the intent of this test primarily to demonstrate that rate of rise protection offered by the power rate meter an be calculated to the same order of accuracy as the measurements of actual conditions.

Studies concerned with the deposition of salts from simulated fuel solution under boiling conditions were continued. Additional deposition tests were carried out in loop L-2-23 in which the core section was heated. Several reagents were tested to determine their ability to dissolve stainless steel corrosion products. A simulated HRT fuel solution was stable with regard to U concentration when diluted to 23 ppm at 250 C; however, some Cu was lost from solution. Preliminary tests in a uranyl sulfate solution indicate that an 18-8 stainless steel alloyed with either small amounts of Pt or Cu is more corrosion resistant at low flow rates than a conventional 18-8 stainless steel; however, the addition of either Cu or Pt did not reduce the corrosion rate of 18stainless steel at high flow rates. A study was made to determine the susceptibility of off-specification type 347 stainless steel to intergranular attack by uranyl sulfate solutions. Continued testing with a single heat of cast type 347 stainless steel has confirmed previously reported data to the effect that the cast alloy is more resistant a stress-corrosion cracking than is the wrought alloy. Six commercial grades of Al/sub 2/O/sub 3/ suitable for use as check balls in …

The purpose of this report is to present the results of laboratory experiments in which coolant water flowed backwards through a ``C`` reactor process tube with operational charge-discharge front fittings under conditions of typical reactor rear header pressures and post-scram rear header water temperature and tube powers. This information is of value in planning and interpreting transient experiments investigating the consequences of the rupture of reactor front face piping to a single tube.

The intermetallic compounds of the zirconium-irontin system (i.e., ZrFe/ sub 2/ and Zr/sub 4/Sn) were studied at 500 and 1100 C. The alloys were prepared from iodide zirconium and high-purity iron and tin by nonconsumableelectrode arc melting techniques under an inert atmospherc. Specimens were encapsulated in Vycor and annealed at the prescribed temperatures followed by a water quench. Data were gathered through the use of metallographic, x-ray diffraction, visible incipient melting, and magnetic susceptibility techniques. It was determined that Zr/sub 4/Sn (24.5 wt.% Sn) and (24.5 wt.% Sn and 7 to 8 wt.% Fe) are separate phases which are not in equilibrium with each other. ZrFe/sub 2/ was firmly established at its stoichiometric composition of 55 wt.% Fe, and it apparently has negligible solubility for tin. The specific magnetization of this ferromagnetic compound is of thc order of 55 cgs at room temperature. Its Curie temperature is about 355 C. (auth)

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The purpose of the Transuranics Program is to develop separation processes for the transuranic elements, primarily those produced by long-term neutron irradiation of Pu/sup 239/. The program includes laboratory process development, pilot-plant process testing, processing of 10 kg of Pu/sup 239/ irradiated to greater than 99% burn-up for plutonium and americium-curium recovery, and processing the reirradiated plutonium and americium-curium fractions. The proposed method for processing highly irradiated plutonium is: (1) plutonium-aluminum alloy dissolution in HNO/sub 3/; (2) plutonium recovery by TBP extraction; (3) americium, curium, and rare-earth extraction by TBP from neutral nitrate solution; (4) partial rare-earth removal (primarily lanthanum) by americium-curium extraction into 100% TBP from 15M HNO/sub 3/; (5) additional rare-earth removal by extraction in 0.48M mono-2-ethylhexylphosphoric acid from 12M HCl; and (6) americium-curium purification by chloride anion exchange. Processing through the 100% TBP, 15M HNO/sub 3/ cycle can be carried out in the Power Reactor Fuel Reprocessing Pilot Plant. New facilities are proposed 15M HNO/ sub 3/ cycle can be carried out in the Power Reactor Fuel Reprocessing Pilot Plant. New facilities are proposed for laboratory process development studies and the final processing of the transplutonic elements. (auth)

The physical and mechanical properties of GCRE-type fuel elements were determined from room temperature to 1650 deg F. The fuel elements were prepared by cladding Type 318 stainless steel sheet to a core containing 15 to 35 wt.% UO/ sub 2/ in either prealloyed Type 318 stainless steel or elemental iron-18 wt.% chromium-14 wt. % nickel-2.5 wt. % molybdenum. The tensile strength in the direction perpendicular to the rolling plane decreased from 24,600 psi at room temperature to 9,200 psi at 1650 deg F for the reference fuel plate, whose core contained 25 wt.% UO/sub 2/ in the elemental alloy. The tensile strength in the longitudinal direction for this fuel element ranged from 54,800 psi at room temperature to 14,200 psi at 1650 deg F, with elongation in 2 in. ranging from 8 to 13 per cent. The extrapolated stress for 1000hr rupture life at 1650 deg F was 1800 psi, and a 1.4T bend was withstood without cracking. The mean linear thermal coefficient of expansion was 11.0 x 10/sup -6/ per deg F for the range 68 to 1700 deg F. (auth)

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.% …

The flooding characteristics of fluorothene Raschig rings at low liquid rates with the existing literature data on carbon rings are compared. Visual observations of flooding in the air-water system were correlated with pressure drop using a 3-in. i.d. glass column having an 18-in. long fluorothene Raschig ring packed section. A comparison of extrapolated literature data with these experimental data indicates thc gas flow rates required to flood fluorothene packing are slightly higher than for carbon packing. At a liquid flow rate of 537 lbs/hr-ft/sup 2/, fluorothene rings flooded at a gas velocity of 842 lbs/hr- ft/sup 2/ whereas carbon rings are reported to fiood at a gas velocity of approximately 755

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.

An accidental release of gaseous fission products from an ORR fused salt capsule, containing 26 mg. of U/sup 235/, was postulated and the resuiting hazard estimated by calculating the maximum external and internal dose an individual could receive from exposure to the gaseous fission products and their decay products. Assuming all the contained gaseous fission produets are released, the resulting external and internal dosc, to organs other than the thyroid, arc insignificant. The dose to the thyroid by radioiodine is considered to be significant. By retaining at least 90% of the iodine isotopes in the experiment system through use of an iodine trap, a large reduction in both the external whole body and internal thyroid doses may be achieved. Therefore, assuming an iodine trap is utilized, it appears that the consequences of am accidental gaseous fission product release from an ORR fused salt capsule experiment would not be serious. (auth)

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)

This document details activities of the Fuels Preparation Department during the month of March 1959. (FI)

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)

This annual report (1958) from the Hanford Atomic Products Operation. Various programs are briefly described including irradiation processing, fuels preparation, chemical processing, research and development, and supporting operations.

A series of critical experiments with blocks of 2% U/sup 235/--enriched UF/sub 4/-C/sub 25/sub 5/H/sub 52/ was initiated at the ORN L Critical Experiments Facility. Thus far assemblies with H:U/sup 235/ atomic ratios of 195 and 294 were built in parallelepipedal and simulated cylindrical geometries, both reflected and unreflected. From the results the minimum critical masses for reflected spheres were determined to be 16.3 and 8.5 kg of U/sup 235/ for fuel mixtures with H:U atomic ratios of 195 and 294, respectively. The minimum critical masses for unreflected spheres of these two fuel mixtures are 24.3 and 12.7 kg of U/sup 235/ respsctively. (auth)