This report, from the Chemical Processing Department at HAPO for September 1963, discusses the following: Production operation; Purex and Redox operation; Finished products operation; maintenance; Financial operations, facilities engineering; research; employee relations; weapons manufacturing operation; and power and crafts operation.

This report, from the Chemical Processing Department at HAPO for May 1963, discusses the following: Production operation; Purex and Redox operation; Finished products operation; maintenance; Financial operations, facilities engineering; research; employee relations; weapons manufacturing operation; and power and crafts operation.

Production efficiency studies of the E-N loading require that conversion ratio values for both plutonium and tritium be defined. Changing of the core-loading charge makeup with each core load to obtain a more efficient loading has theoretically resulted in increasing the tritium conversion ratio. Tritium recovery data from the third H Reactor E-N loading has recently become available for analysis. The buildup of product is much slower in fringe blanket material then in core target pieces. The second group of fringe conversion ratio data has only recently been obtained for analysis, the material analyzed was from the DR Reactor, irradiated under conditions closely paralleling those in the H Reactor blanket load. This document reports the conversion efficiencies for tritium production in Hanford E-N core and blanket loadings `indicated by these most recent data.

The production of plutonium containing 17 to 18 per cent Pu-240 has been proposed for Hanford as part of the over-all process for production of transuranium isotopes. Purpose of this report is to summarize measures that would be taken to ensure good performance of the depleted uranium fuel elements and to predict the performance of the depleted fuel.

This report, for February 1963 from the Chemical Processing Department at HAPO, discusses the following: Production operation; Purex and Redox operation; Finished products operation; maintenance; Financial operations; facilities engineering; research; employee relations; weapons manufacturing operation; and safety and security.

The metastability of alpha plutonium above the {alpha} {r_equilibrium} {beta} equilibrim transformation temperature (112 C) was studied by metallographic techniques. The purpose of this study was to extend the previous work on the {alpha} {yields} {beta} transformation which was accomplished using fluid displacement techniques{sup 1} and to obtain a basis for determining the length of time the alpha phase is stable at high temperatures. Approximate isothermal reaction curves were determined experimentally and an {alpha} {yields} {beta} time- temperature-transformation (T-T-T) curve was derived.

This report will describe the important features of the development of magnetic tapes for the numerical control of a pulse-increment system consisting of a modified Gorton lathe and its associated control unit developed by L. E. Foley of Equipment Development Service, Engineering Services, General Electric Co., Schenectady, N.Y. Included is a description of CUPID (Control and Utilization of Pulse Increment Devices), a FORTRAN program for the design of these tapes on the IBM 7090 computer, and instructions for its operation.

In the summer of 1962, a brief scoping study of the N-Reactor`s capability as a producer of tritium concurrently with plutonium and steam was completed and documented. This study indicated that there might be considerable incentive in pursuing the development of a multi-product mode of operation of the N-Reactor. Early in 1963 reports presented the preliminary production and cost data, and brief discussions of the potential technical problems which mav arise in a multi-product mode of operation. On September 9, 1963, a report presented a program for the conversion of the N-Reactor to the concurrent production of weapon grade (6%) plutonium and substantial quantities of tritium. The production and cost data showed that the amount of tritium can be varied over a wide range and that weapon grade plutonium can be economically generated. The purpose of this report is to evaluate the feasibility and incentive for operation of the N-Reactor with fully enriched fuel producing only two major products tritium and steam. Neptumium 237 is an important by-product.

The transformation of retained phases of plutonium of different quality has been determined over a period of 10--12 months, by observing the density variation with time. A large density increase of each specimen was observed. The density increase of the low quality metal was the greatest and that of the highest quality metal was the least. The magnitudes of these increases are apparent from the graphs. One of the specimens fractured into two pieces after ten months. Also, surface cracks appeared in two of the other specimens. The fractured surfaces probably originated from the stresses associated with the transformation of retained phases or possibly from stress corrosion. The density increase with time was the same for the as-cast and cold treated specimens.

During the early part of CY-1961, water leak frequency on plant began to pose a mounting problem. At this time, DR reactor exhibited a leak mechanism which, although observed to some extent at other reactors, appeared to be primarily a DR problem. This mechanism can best be described as a trench running longitudinally along the top portion of the process tube. The dimensions vary considerably; however, the lengths attained were generally about two to there feet and the width was roughly one inch. The beginning of the trench appeared to be mainly in the position of 11 to 14 feet fro the rear Van Stone flange. The radial position of the trench in the tube runs from about the 10: 30 to the 2:30 o`clock position. For lack of a more definitive expression for this corrosion, it will be referred to as a form of ``accelerated local corrosion.`` This report deals entirely with one possible means of affecting accelerated local corrosion. A layer of gaseous air coming from the dissolved air in the process water could form a heat transfer resistant area. This area would probably exhibit an accelerated corrosion rate due to the higher tube wall temperatures resulting.

This report, for October 1963 from the Chemical Processing Department at HAPO, discusses the following: Production operation; Purex and Redox operation; Finished products operation; maintenance; Financial operations; facilities engineering; research; employee relations; weapons manufacturing operation; and safety and security.

This report, for January, 1963 from the Chemical Processing Department at HAPO, discusses the following: Production operation; Purex and Redox operation; finished products operation; financial operations; facilities engineering; research employee relations; weapons manufacturing operation; and power and several maintenance operation.

This production test authorized the irradiation of 1.6% enriched single tube elements in KER-1 and 2. This document provides the process tube loading, operating limits, and water shutoff times for the charge.

A thin plate-type element containing a dispersion of 20% enriched U/sub 3/O/sub 8/ was developed and successfully used in the 5-Mw pool-type research reactor at the Puerto Rico Nuclear Center. The underlying criteria that guided the design are presented. The technological factors, such as compatibility, corrosion resistance, and irradiation behavior, which led to the selection of U/ sub 3/O/sub 8/ as the fissile compound and aluminum as the cladding and matrix material, are reviewed. The fabrication procedures developed and adopted for manufacturing the component are presented. The scheme involves incorporation of 55 wt% U/sub 3/O/sub 8/ into aluminum compacts by powder metallurgy techniques, preparation of composite fuel plates by roll cladding, assembly of fuel plates into an integral unit by either the roll-swaging or pinning techniques, and corrosion protection of the element by an anodizing treatment to increase service life. Quality control measures adopted to ensure dimensional tolerances are described. Mechanical joining proved to be an economical method for assembling the pool-type fuel elements within dimensional specifications. (auth)

The costs of interim storage of solidified Purex and Thorex wastes in water-filled canals were estimated as the third part of a study to evaluate, from the standpoint of econoNonemics and hazards, the various steps leading to and including the permanent disposal of highly radioactive liquid and solid wastes. The wastes were assumed to have been solidified following their production in a plant proccessed 1500 metric tons per year of uranium converter fuel it a burnup of 10,000 Mwd/ton and 270 tons/yr of thorium converter fuel at 20,000 Mwd/ton. Separate facilities where designed for the storage of the calcined wastes in the acid and reacified forms, and for the Thorex waste made into a glass. Consideration was given also to storage (in the same facilities) of the combinations acid Purex-acid Thorex and reacified Purex-reacidified Thorex wastes. Costs for interim storage times from 1 to 30 yr were computed for wastes decayed 120 days and 1, 3, and 10 yr at time of initial storage. Costs ranged from 1.5 x 10/sup -3/ mill/kwh, for 1-yr storage of calcined 10-yr-old acid Purex waste to 18 x 10/sup -3/ mill/kwh/sub e/ for 30-yr storage of calcined, reacified 120-day- old Thorex wastes. Costs of …

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A syntax checker was designed based on the syntax of Algol as previously described. It was desirable to design the syntax checker as a set of mutually recursive processors tied together by building blocks which perform certain bookkeeping functions. Because of the recursive nature of the language and of the syntax checker, the problem of recovery after an error required much attention. A method was devised which permits most programs to be checked completely despite errors. The syntax checker was implemented for the IBM 7090 as a part of the SHARE ALGOL processor, and has operated very satisfactorily. (auth)

Tests of subsize tensile and impact specimens of Type 547 stainless steel irradiated in three capsules to fastneutron exposures of up to 1.1 x 10/sup 22/ nvt were conducted. Ductile fractures at impact energies of 65 ft-lb, representing a 35% decrease in impact strength, were noted at room temperature. Impact energies of approximates 20 ft-lb and a fracture with both brittle and ductile characteristics were observed at -300 deg F. Irradiation-induced property changes included increases in yield strength from 35,000 to 105,000 psi and in ultimate strength from 90,000 to 112,000 psi and a decrease in total elongation from 63 to 31% at room temperature. A 600 deg F anneal produced no measurable recovery of preirradiation properties for periods up to 144 hr, but a large degree of recovery was obtained by annealing 1 hr at 1800 deg F. In material irradiated at 750 deg F, increases in yield strength from 55,000 to 149,000 psi and in ultimate strength from 92,000 to 149,000 psi, decreases in elongation from 55 to 10%, and reductions in area from 70 to 60% were observed. (H.G.G.)

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Nucleon-meson cascade calculations were carried out and the dose as a function of depth was obtained for an 800-Mev proton beam incident on a shield. The physical properties used for the shielding medium are only a rough approximation to the properties of any particular medium. Muon, neutron, pion, and proton dose rates and fluxes are listed. (auth)

From 19th International Union of Pure and Applied Chemistry Congress, London. A systematic introduction is presented to the subject of the variation with pH of the polarographic half-wave potential, which is probably the most readily measured electrochemical energetic parameter of organic compounds. Emphasis is placed on (a) the types of relationships observed for both reversible and irreversible electrode processes, (b) the mathematical formulation of these relationships, (c) the structural, mechanistic, kinetic, and environmental factors influencing such relationships, and (d) the presumptive physical causes for such relationships, e.g., the effect of pH on the electrochemical kinetics. Although the discussion is primarily concerned with behavior in aqueous solution, the conclusions drawn are equally valid for nonaqueous media in which hydrogen ion or some other Lewis acid can play a significant role. The half-wave potential for an organic electrode process may be independent of pH, or may vary lineanly or sigmoidally; other types of relationships observed are likely to be combinations of such effects. These variations may be due (a) to direct participation of hydrogen ion in the transition state involving the electroactive site in the organic molecule and the electron source, e.g., polarization of the bond to be broken, (b) to control …

Reactions with water of as-cast uranium-carbon alloys containing 2to 10 wt% carbon (UC/sub 0.4/ to UC/sub 2.2/) were investigated by using gas- chromatography for analysis of the gaseous products. Uranium metal-uranium monocarbide alloys yielded 2 moles of free hydrogen per mole of free metal, in addition to methane, small quantities of higher molecular weight gaseous hydrocarbons, and a solid, hydrous, tetravalent uranium oxide. The gaseous producte contained all the carbon originally present in the alloy. Uranium dicarbide (UC/sub 1.86/; this combined-C/U atom ratio was the maximum which could be obtained) yielded a mixture of 38 hydrocarbons (methane, 15 vol%; ethane, 28%: C/sub 3/- to C/sub 8/-alkanes, 7%; alkenes, 8%; alkynes, 0.6%; and widentified unsaturates, 1%), free hydrogen (40 vol%), a water-insoluble wax, and a solid, hydrous, tetravalent uranium oxide. Forty% of the combined carbon was found in the gas and 25% in the wax. The gaseous products from the hydrolysis of both UC and UC/sub 1.86/ were not affected by changes in the reaction temperature between 25 and 99 deg . The composition of the gases evolved at 80 deg from as-cast alioys with compositions between UC and UC/sub 1.86/ varied linearly with the combined-C/U atom ratio of the alloy; …

The nuclear star density produced by a 24-Bev proton beam in a material having approximately the properties of heavy concrete is calculated. A comparison is made with experimental measurements made at CERN; but, since the quantity that can be calculated is not the same as that measured, no firm conclusions can be drawn. Proton, neutron, pion, and muon intensities are plotted vs. distance as are star densities. (auth)

Tributyl phosphate can be used for extraction in processing all current power reactor fuels. Nitric acid is the only salting agent required. Typical flowsheets are presented. In aluminum nitrate systems which are more than 0.1 M acid deficient, the uranium distribution coefficient is a function of pH and independent of aluminum concentration; the coefficient remains constant at one in fluoride systems when the nitrate to fluoride ratio is approximates 3.5. Many objectionable properties of degraded diluents are ascribed to nitroparaffins. Aliphatic diluents with the least branching are the most stable to nitration. The nitration stability of aromatic diluents varies with structure, e.g., stabilities of diethylbenzenes decrease as meta >> ortho > para. Solvent purification by flash distillation appears superior to other methods. The stability of Amsco 125-82 was permanently improved by treatment with sulfuric acid. The radiation stability of TBP was approximates 2 times higher in an aromatic diluent than in Amsco 125-82. The G decomposition value for 1 M TBP in Amsco alone was approximates 0.9; whereas in 1 to 3 M HNO/sub 3/ it was 1 to 5 and G (--HNO/sub 3/ org phase) was 3 to 20. Variation of uranium--thorium separation factors with structure of some neutral …