This report provides a summary of the results of a process study, requested by the Atomic Energy Commission an the recovery of krypton and xenon from irradiated uranium at the Hanford Purex Plant. This request was prompted by original Commission forecasts of the expanded requirements for Krypton-85 for commercial phosphorescent signal lights and markers and for xenon isotopes of low neutron cross-section for use in liquid xenon scintillation counters, in connection with D.M.A., government and university-sponsored work. It was requested that both Hanford and Savannah River submit order of magnitude cost estimates for recovery facilities at the respective sites for three separate design cases. The cost information developed, along with market survey information obtained-through the A. D. Little Company and Department of Defense market surveys, would serve as the basis for scheduling of the Hanford and Savannah River participation in the Commission`s overall fission rare gas recovery program.

This report provides raw data reactor calculations for the time period of September 12, 1958 through July 21, 1960.

None

The solution-type research reactors placed in operation by Atomics International fall into three power range categories. The 50-kw type has the advantages of a large graphite refiector, both horizontal and vertical thermal columns, and gamma ray exposure facilities in its sub-pile area. The 1.5-kw reactor has a 5 1/2 -foot square vertical thermal column for exponential work. The 10 watt unit is intended as a training and minimum research facility. These reactors and their operating characteristics are described. (M.H.R.)

Progress is reported in the study of ThO/sub 2/ sols and related systems and in the development of methods for measuring the physical properties of sols and slurries. (W.J.H.)

Irradiation by fast particles changes most physical and chemical properties of graphite by producing various lattice defects such as displaced atoms, vacancies, dislocations, etc. Attempts have been made to evaluate the contributions of different types of defects to the property changes. Such evaluations have proven rather successful for physical properties and will be extended to several chemical properties. Experiments are described which show that oxidation catalysts and inhibitors act differently on irradiated and on unirradiated crystals. The oxidation of graphite crystals in ozone was studied because it appears to provide clues to the enhancement of oxidation rates in the presence of ionizing radiation. The kinetics and mode of attack of -ozone on graphite crystals with or without prior neutron irradiation are described. (auth)

Measurements of the energy spectra and time distribution of the fission-associated gamma rays are described. New data for thermal neutron-induced fission in U/sup 235/ is presented covering the energy range between 0.3 and 8.0 Mev. Gamma-ray energy analysis was carried out with a multiple-crystal scintillation spectrometer employing either Compton scattering of pair production to give unique pulse-height response. The importance of unique spectrometer response is explained. The gamma-ray spectrometer was operated in coincidence with a spiral-wound fission chamber by the use of a four-fold coincidence circuit having a resolving time of 6 x 10/sup -8/ sec. Spectral measurements for delayed fission radiation were obtained with a similar gamma-ray spectrometer. Energy distributions from 0.3 to 5.4 Mev are presented for ten delay times between 1.7 and 1550 sec. Gamma radiation delayed between 6 x 10/sup -8/ and 3 x 10/sup -6/ sec after fission was observed following thermal-neutron induced fission. This radiation appeared to be about 6% as intense as the prompt radiation. No gamma-rays in the range from 3 to 7 x 10/sup -6/ sec were observed within limitations imposed by random backgrounds. No measurements were reported in the time range between 7 x 10/sup 6/ sec and 1 sec. …

The corrosion rate was determined and tabulated for stainless steels, nickel alloys, carbon steels, Zircaloy-2, and niobium in boiler water containing various concentrations of oxygen. The corrosion resistance of stainless steels and nickel alloys was compared with the resistance of the austenitic stainless steels in uranyl sulfate at 200 to 295 deg C. Additional loop runs with UO/sub 3/ --Li/sub 2/CO/sub 3/ --CO/sub 2/ so lution have confirmed previous data with regard to its nonaggressive nature to carbon steel. The corrosion of 347 stainless steel was investigated in 0.04M uranyl sulfate containing 0.04M beryllium sulfate and 0.006M copper sulfate, in 0.075M beryllium sulfate, and in 0.75M beryllium sulfate containing 0.25M dissolved uranium trioxide. centration to 0.03M or decreasing the uranium concentration to 0.02M in simulated HRT fuel solution (0.04M uranyl sulfate, 0.02M sulfuric acid, and 0.005M copper sulfate) has no significant effect on the solution stability or corrosiveness of the solution. The effect of varying the oxygen concentration between 250 and 2800 ppm in 0.17M uranyl sulfate at 250 deg C on the corrosion rate of 347 stainless steel was found to be negligible in the absence of added Cr/sup 4+/. The corrosion rate of 347 stainless steel in dilute …

Processes for the conversion of uranium compounds or uranium metal to uranium hexafluoride ordinarily involve the use of a powerful fluorinating agent. Elemental fluorine is used when the scale of operations justifies the construction of a fluorine generating plant, but for smaller operation the use of the interhalogens of fluorine has definite advantages. These compounds provide a high concentration of fluorinating power at moderate temperatures and pressures and are more easily stored and transported than fluorine. In addition, fluorinations in the liquid phase often proceed more smoothly than those with gaseous fluorine. However, the use of . the interhalogens introduces the problem of separating the uranium hexafluoride from the unreacted reagent and from any by-products which may have been formed. The present work is concerned with the determination of the phase equilibrai among the materials uranium hexafluoride, chlorine trifluoride, and hydrogen fluoride. metal with chlorine trifluoride-hydrogen fluoride solutions or as a result of treating many uranium compounds and ores with chlorine trifluoride. These phase equilibria define the physical conditions necessary for separating the components by the processes of crystallization or distillation and have made possinle the successful Operation of a pilot plant for the direct recovery of uranium hexafluoride from …

Specimens (type 347 stainless steel, zirconium alloys, and titanium alloys), exposed in the Blanket region of the HRE-2 during runs 13 and 14 as well as during some prior high temperature operations, were examined and weighed. The visual observations and weight data are presented together with the chemical analyses of scale removed from some of these specimens. The evidence indicates that the corrosion of the specimens was moderate. Some possible interpretation of the results of the scale analyses as related to core tank corrosion are also reported. (auth)

Three groups of experiments were carried out to determine ihe disiribuiion of Ra in HNO/sub 3/ digesiion of rich pitchblende ores. The various experimenis were designed to determine the effect of washing on the removal of Ra from the gangue, effect of excess HNO/sub 3/ and time of digestion on the removal of Ra from the ore, and effect of the concentration of HNO/sub 3/ on the extraction of Ra. (W.L.H.)

Theoretical studies of the ANL 12.5-Bev synchrotron are presented. Detailed studies have been made on the straight one-seventh scale model, where changes in hole size and position can be made with relative ease. Several tests were made to check the operation of the analog-to-digital converter. Generator regulation is discussed. Comparative analysis of a number of schemes for ring magnet power supply are in progress. Calculations have been made of the forces expected on the various components of the synchrotron. Ring magnet and ring magnet coil design progress is reported. Studies of the r-f accelerating voltage are described. The design of the 50-Mev BNL linear accelerator has been adapted for use in the synchrotron. Initial design studies were completed for the 124 quadrupole magnets for the linear accclerator. The injection system for the ANL synchrotron will consist of in ion source, a 750-kv preaccelerator, and a 50-Mev linear accelerator. The acceleration of proton beams is being studied. Epoxy plastics were studied to obtain their vacuum, radiation damage, and bonding properties. Recommendations for the layout of experimental areas. the power requirements for these areas, and the characteristics of the various beams are presented. (for preceding period see ANL-5803.) (W.D.M.)

Tests on 1-gpm and 0.5-gpm hydroclones showed them to be unnecessary. Solvent-aqueous phase separation, although effective when optimized, was infrequently required. The 1-gpm hydroclone produced better water separation than the 0.5-gpm hydroclone for similar control parameters. Decontamination factors for widely varying flow conditions ranged from 1 to 3. Introduction of water into the hydroclone feed stream had no effect on decontamination or particle removal. (auth)

Maximum thermal-neutron fluxes obtainable for the case that maximum power density is limited to 100 w-/cm/sup 3/, and for the case that total reactor power is 100 Mw are listed for a homogeneous reactor, and for five moderators. (auth)

Irradiation effects at 500 deg C in experiemtal graphites with varied density, crystallinity, surface area, and pore distribution are discussed. Changes in macroscopic properties are dependent upon the initial crystallite structure; however, the mechanism by which the increase of interlayer spacing and decrease of apparent crystallite size effect these changes is not well understood. Macroscopic properties are also dependent upon the arrangement of crystallites and whole coke particles within the over-all structure which raniation may change slightly. Graphite irradiations in the Materials Testing Reactor extend exposure temperatures from 800 to 1000 deg C. The temperature coefficient of property damage decreases with temperature, aad only slightly less damage occurs at 1000 deg C than at 500 deg C. Thermal conductivity decreases by a factor of 50 with 30 deg C irradiation, a factor of 3 with 500 deg C irradiation, and a factor of 2 with 750 deg C irradiation. Within the irradiation temperature range 500 to 1000 deg C, the contraction rate after the first 1500 Mwd/t is measurably the same: C/ sub 0/ spacing expands slightly: and apparent crystallite size decreases by one- half. The total stored energy content is decreased with increased irradiation temtemperature. The way in which …

The 5509 fuel rods for the Yankee Atomic Electric Company critical experiment were made by sealing sintered UO/sub 2/ pellets in stainless steel tubing by welding end plugs to each end of the steel tubes. The complete history of the fabrication of these fuel rods from the receipt of pellets to the radiographic inspection of the completed rods is discussed in detail. The control of the quality of the UO/sub 2/ powder was exercised by com paring certified analyses supplied by the vendor with analyses made by APD on correspondng lots. Chemical analyses, inspection data, procedures and processes are presented in tables and graphs. (auth)

The heat geueration and thermal stresses in spherical HRE-4 vessels 3 to 4 1/2 ft in diameter with clad and solid stainless steel walls were invegtigated. Parameters included thorium slurry concentrations and moderator material (D/sub 2/ O and H/sub 2/O). The prirnary purpose of this study was to determine the influence of thermal stresses on the selection of the core size for the HRE4 reactor. Curves are presented which facilitate relatively rapid determination of stresses for the range of vessels considered. It is concluded that steady- state thermal stresses in the clad or solid stainless steel vessels considered will not have to be a determining factor in the selection of a core size, provided the power density does not exceed approximately 15 kw/l in the clad vessels and 8 kw/l in the solid stainless steel vessels. (auth)

Progress is reported in the following studies: determination of the liquidus curve for U alloys having 0 to 4.8% C; the preparation and properties of the U - Cu, U -Sn, U-Bi, and U-Hg systems; the preparation of U by extraction of the hydride as amalgam; laboratory methods for the preparation of U and Th; the purification of Mg; determinations of B in lime; the effect of furnace temperafure and firing time on the yield of U; a comparison of the properties of Mg from various sources; and methods for casting U metal. (C.H.)

The plant arrangement, component design, and the functions of various systems are described and illustrated. Relative estimated costs of the systems and major components are indicated. The reactor core is designed around requiremouts for 254 thermal megawatts, 950 deg F maximum sodium temperature, stainless steel clad graphite moderator blocks, and low enrichment (0.015 to 0.04 U/sup 235/) uranium fuel elements. The fuel cycle is described for the possible fuel elements. The fuel cost factors are discussed. Burn-up limitations encountered for metallic fuel in the SGR temperature range indicate UO/sub 2/ the more desirable choice. The estimated cost of electrical energy associated with the UO/sub 2/ fuel is given. (auth)

The results of a recent experimental investigation of the fission properties of some actinide elements are presented. The study includes: fission fragment kinetics, fission neutron spectra, prompt gamma rays from fission, and delayed neutrons from fission. The kinematic distributiou of the fission fragment modes of Th/sup 229/. Pu/sup 240/, P/sup 241/, Cm/sup 242/, Cm/sup 244/ , Cf/sup 252/, and Fm/sup 254/ were determined using a high resolution back-to- back ionization chamber. The fission neutron spectra of U/sup 233/, Pu/sup 241/, and Cf/sup 252/ were measured from 0.2 to 10.0 Mev. The prompt fission gamma spectrum of Cf/sup 252/ was measured from 0.075 to 10.0 Mev using single and double crystal scintillation spectrometers. The periods and yields of the delayed neutron groups emitted in the fission of Cf/sup 252/ were measured. The integrated field per fission was found to be ~ 1/100 that U/sup 235/. (W.D.M.)

Activity ratios for the important members of the U/sup 232/ chain are presented in tabular form. These ratios are presented for initially pure U/sup 232/, initially pure Th/sup 228/ and initially pure Ra/sup 224/.- (auth)

Papers are presented in the following major categories: applied metallurgical research, natural-uranium metallic fuel elements, enriched-uranium metallic fuel elements, nonmetallic fuel elements, corrosion of U alloys, irradiation effects on U, its alloys, and its compounds, and Pu fuel elements. (M.H.R.)

The laboratory and pilot plant evaluation of Dyno concentrate is presented. This concentrate meets all FMPC impurity tolerance limits except thorium and chloride limits. The thorium limit can be met by the m-containing this material will necessitate blending of the material with a good quality low- chloride-containing concentrate in the National Lead Company of Ohio refinery process. Laboratory digestion and extraction tests indicate that this material should present no other problems in pulse colunn processing. A pilot plant pulse column test indicated that this material should present no operational problems in the National Lead Company of Ohio Refinery. (auth)

A general survey is presented of information in the uranium alloy field. Emphasis is centered on alpha uranium-rich alloys of special interest as uranium- base fuel element materials. The systems treated include uranium-molybdenum, uranium-silicon, uraniumzirconium, uranium-niobium, and uranium-zirconiumniobium (high uranium compositions). The uraniumfissium alloys are discussed in relation to their projected applications as fast reactor fuels. Equilibrium diagrams, transformation kinetics, and other pertinent data are presented for the uranium plus fissium'' element systems, e.g., uranium-ruthenium, uranium-rhodium, uraninum-palladium, and uraniummolybdenum-ruthenium. The properties covered include constitution phase diagrams, metallographic structure, physical and mechanicaly properties, transformation kinetics, crystallographic structure, thermal cycling, ad irradiation stability (where pertinent). Correlations between microstructure, heat treatment, and dimensional stability are emphasized, with particular reference to the U-2 wt.% Zr, U-5 wt.% Zr, and 1 1/2 wt.% Nb alloys. A discussion of the role of alloying and heattreatment in improving the dimensionaly stability and corrosion resistance of uraaium is presented, and an evaluation is made of the present status in attaining these objectives. (auth)