This manual discusses basic radiological safety and APPR-1 radiation monitoring. It then provides radiation protection instructions.

Lubrication of die surfaces with mineral oil or Dag 217 during final compacting of UF/sub 4/--Mg blends prevented seizing. Mineral oil application after every third press allowed 18 compacts before seizing became severe. Similar application of Dag 217 allowed 78 compacts. Mixing 0.33 wt.% Ceremul "C" with the powder allowed 40 compacts. Punch clearance had little effect on seizing. (T.R.H.)

Aluminum capsules with Al inserts and He atmospheres and containing 4 strips of Eu/sub 2/O/sub 3/-stainless steel were measured in the Reactivity Measurement Facility at MTR, both before and after irradiation. (T.R.H.)

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The developing fetal skeleton of the rat was used to study the microscopic localization of the rare earth Ce/sup 144/ in bone. Nineteen-day-old rat fetuses were injected with Ce/sup 144/ in isotonic sodium citrate via the umbilical vein. They were sacrificed one-haif hour after the injection by immersion in 80% alcohol fixative. The fetuses were embedded in paraffin and sectioned at 10 to 12 mu . Semiserial sections were treated with periodic acid- Schiff stain for mucopolysaccharides, and by the von Kossa technique for calcium. Contract x-ray-film autoradiographs and NTB stripping-film autoradiographs were prepared. Photographs of representative sections and their respective autoradiographs are presented for various bones. This material strongly suggests that the initial binding site of Ce/sup 44/ in the skeleton is in the organic matrix of cartilage and bone, especially where this matrix is just entering the calcifiable state. This conclusion is highly dependent upon the specificity of the von Kossa stain for calcium. (auth)

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An experimental study was made of the mass transport of chromium in poly- thermal Inconel-fluoride fuel systems. The transport of chromium was followed by toe technique of adding radioactive Cr/sup 51/ to the system as either CrF/sub 2/ , in the salt or as elemental chromium in the solid phase. The rates of diffusion of chromium in Inconel at 600, 700, 800, and 900 deg C were determined by an electropolishing technique. Polythermal studies were carried out by three methods, tilting capsules, thermal-convection loops, and pumping loops. Tilting- capsule experiments indicated that the preferred location for chromium deposition on the wall was in the region of maximum temperature but the conclusions were not clear cut. Thermal convection loops operated for 125 and 288 hr showed radioactivity profile which could be attributed to simple exchange, with some distortion in the 288 hr case. The duration of these experiments was evidently insufficient io allow equilibrium to be reached in the salt. A thermal- convection loop operated for 400 hr showed distortion in the exchange radioactivity profile which indicated a favorable position for chromium deposition at a point about 100 deg F below the maximum wall temperature, and on the upstream side of …

The purpose of this memorandum is to summarize the present state of development of iron-- aluminum-base alloys. The binary iron--aluminum alloys offer favorable tensile strength but possess very poor ductility. The iron-- aluminum -- molybdenum alloy, thermenol (Fe -16A1--3 Mo), is corrosion resistant, offers excellent tensile strength, and is ductile. (A.C.)

This report presents the results of initial experiments concerning the protection afforded by the Panellit system against hazards associated with the inadvertent plugging of a process tube.

A continuous process for the dissolution of irradiated fuel elements is a potential means of solving criticality limitations in the dissolution of enriched uranium slugs and of achieving higher dissolver capacity in the Redox and Purex Plants. This report summarizes development studies aimed at determination of dissolution rates, effluent compositions, and effects of changes in operating conditions on mercury-catalyzed dissolution in a tower-type unit.

The results show that the effective charge-exchange cross section per proton of the target nucleus decreases rapidly with increasing Z.

A study was conducted to demonstrate the stripping and evaporation steps in a Purex-type uranium recovery prccess and to ascertain the operating behavior of the equipment under a range of conditions. The factors considered were control, effectiveness, and reliability of equipment and optimum feed pcint. Experimental procedures are described, and recominendations for equipment mcdifications are included. (J.R.D.)

An investigation was conducted to determine radiation dosags rates associated with operation of the Sodium Reactor Experiment at 8.3 Mw. These values were extrapolated to full-power operation. Hadiation survey results are tabulated. (J.R.D.)

BS> Hydrogen pickup by U was studied in different salt mixtures at 1350 deg F under dry and wet atmospheres. Of the salts investigdted, 50 wt.% KCl-50 wt.% NaCl and 50 wt.% KCl-50 wt.% Na/sub 2/CO/sub 3/ gave the best results for low H pickup, corrosion of U, and salt stability at 1350 deg F. These salt mixtures resulted in H pickup of less than 3 ppm under dry atmospheres and less than 5 ppm under wet atmospheres. By comparison, the two salt mixtures, 44 wt.% Li/sub 2/CO/sub 3/-56 wt.% K/sub 2/CO/sub 3/ and 25 wt.% Li/sub 2/CO/sub 3/--75 wt.% K/sub 2/CO/sub 3/, resulted in H pickup greater than 5 ppm under dry atmospheres and as high as 13 ppm under wet atmospheres. Pilot-plantscale studies showed that the average final H content of the U specimens treated in the 50 wt.% KCl-50 wt.% NaCl baths was 0.47 ppm. The corresponding average for the 50 wt.% KCl-50 wt.% Na/sub 2/CO/sub 3/ baths was 0.77 ppm. Preliminary studies of corrosion of materials of construction in the pilot-plant-scale baths indicated that Type 330 stainless steel was more resistant to attack than mild steel and Types 304, 416, and 446 stainless steels. (auth)

To prevent corrosion of equipment by nitric acid hydrofluoric acid mixture, aluminum nitrate nonohydrate is added to tie up the fluoride, either as aluthinum fluoride or a tight complex. It was found that a solution of nitric acid, hydrofluoric acid, and aluthinum nitrate nonohydraie in which the hydrofluonic acid - aluminum nitrate nonohydrate molar ratio is 3, did not show serious corrosive attack on the 300-series stainless steel. (J.E.D.)

In a suady of the preparation and properties of deltaphase zirconium hydride it was found that large, sound bodies of the hydride can be prepared by direct combination of the elements if the rate of the reaction is retarded by limiting the supply of available hydrogen. Specimens up to 1-in. diameter were prepared using this technique. Because delta-phase zirconium hydride does not readily form eutectics with iron- and nickel-base alloys below 1800 deg F these materials may be utilized for cladding the hydride. Delta-phase zirconium hydride is unaffected by exposure to liquid NaK or to nitrogen gas at temperatures below 1000 deg F. The hot hardness of deltaphase zirconium hydride is about 130 kg per mm/sup 2/ at room temperature and 40 kg per mm/sup 2/ at 1500 deg F. The mean coefficient of thermal expansion (68 to 1337F) is 6.5 x 10/sup -6/ per deg F. The thermal conductivity varies from 5.7 Btu/(ft)(hr)(F) at 300 deg F to 5.1 Btu/(ft)(hr)(F) at 1300 deg F. (auth)

The use of a circulating-fuel type of nuclear reactor as an energy source in aircraft propulsion systems imposes upon the structural material metallurgical restrictions which limit the applicability of certain types of alloys. The general factors which must be considered in the selection of an alloy for this application are corrosion resistance, fabricability, nuclear properties, radiation damage, and elevated-temperature strength, The importance of each of these topics is pointed out, and it is shown that the selection of Iconel ss a structural material was based on these criteria (auth)