This report summarizes the results of the fifth of a series of tests completed in the A-11 test program.

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The activity coefficients of HCl and NaCl in HCl--NaCl mixtures were computed from literature data. The calculations are based on the observation that at constant ionic strength and temperature the logarithm of the activity coefficient of HCi in HCl--NaCl mixtures varies linearly with NaCl concentration. (auth)

After shutdown heating rates have been calculated for the target, control plates, and the beryllium reflector of the HFIR. Hilvety previously calculated the after shutdown heating rates in the element and his results are reported in ORNL CP-60-4-110. Decay times of 1.0 10, 10^2, 10^3, 10^4, and 10^5 seconds have been considered, and heat fluxes have been computed for all of the mentioned components. The greatest heat fluxes were found to be at the surfaces of the control plates and the permanent beryllium reflector.

Report presenting a bibliography of about 550 references of the soft X-ray literature since 1950 and through 1960. The emphasis is on the application of soft X-ray spectroscopy to the study of valence band electronic states in metals and alloys. Therefore, the spectral region of 25 to 800 angstroms involving ruled glass grating spectrometers is of principal interest. In addition to soft X-ray data, references on all pertinent aspects of the apparatus and experimental problems are included. Also listed separately are references of value in corroborating soft X-ray data with other results. Subject, author, X-ray band, material, and other indices are included.

A gasometric apparatus for rapidly characterizing dissociation pressures, sorption equilibrium and kinetics, chemical states, and decomposition conditions was built and tested. The method involves the measurement of quantities of gases reacting with or evolving from known quantities of solid. Accuracies of better than plus or minus 1% were attained. In testing the capabilities of tue apparatus, the dissociation pressures of hydrogen fluoride and uranium hexafluoride over their respective complexes with sodium fluoride, and the decomposition of the uranium hexafluoride complex to give elemental fluorine were verified. Additionally, a test for sorption of uranium hexafluoride on sodium fluoride was developed, the existence of the compound Na/ sub 2/UF/sub 8/ was demonstrated, a more active form of sodium fluoride was made, the stability of the pentavalent uranium-- sodium fluoride complex was studied, data leading to a postulated new compound (NaF)/sub 2/(UF/sub 6/)(HF) was obtained, and the interaction of hydrogen fluoride and uranium hexafluoride on sodium fluoride was studied. (auth)

This report documents the use of the dislocation theory to analyze measured vertical displacements across a fault near the Duryea underground nuclear explosion.

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Preparation of enriched fuel elements and target (N) elements for a full H-Reactor E-N demonstration loading was authorized in April, 1960. The objective of this loading was to demonstrate the feasibility of operating a Hanford reactor economically as a plutonium-tritium producer to increase over-all conversion ratio and diversify product output. Irradiation of the E-N load began in May, 1961 and was completed in January, 1962.

This report is categorized into three categories: (I) Regional Problems and the Arms Race, (II) Outside Powers and the Arms Race and (III) Difficulties in Comparing Military Strength of Middle Eastern Countries.

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From abstract: The PT-750 is designed to be used in conjunction with a production tester which requires automatic recording of test data. This manual provides a source of procedures and reference material necessary in automatic recording and in use of the PT-750.

The technical bases for Phase I of the Fission Product Program have previously been presented for Phase I design. This report represents its sequel for Phase II of the program. Phase I provides the means of segregating, concentrating, and aging crude fission product fractions with market value. Phase II is to provide the means for single-line purification and packaging of megacurie quantities of fission products (principally strontium-90). The technical bases for Phase II project scoping studies are presented herein in the form of process flowsheets and tabulated data. Equipment needs are also described. Conceptual processes and flow diagrams for Phase III are presented for the Waste Management Program and the Fission Product Program.

The K Reactors were originally scoped to have three independent electrical power supplies and to be able to transfer process water, filtered water, raw water and electrical power from one K Plant to the other. It was required that shutdown flow to each reactor be available from at least four separate pumping stations. The originally scoped power level was 1300 MW, yet a plentitude of coolant supply means were provided, as can be seen from the above statements. Today, 1963, the K Reactors operate at 4400 MW and are capable of operating in the vicinity of 5000 MW during low inlet water temperature conditions. Requirements on coolant supply systems are more extensively defined today as a result of this larger potential liability and because of improved technology. This document discusses modifications to the K Reactors` secondary backup systems` equipment arrangement that will improve backup adequacy and reliability while permitting greater operating convenience as regards backup equipment maintenance. The modified secondary system proposed by K Maintenance Engineering is endorsed, provided a reliable means of avoiding overloading a boiler is included and provided the independence of the emergency generators can be reasonably assured. Preliminary discussions indicate that a control circuit to prevent …

"The purposes of the program being conducted under the present contract are: 1) To determine the feasibility of cladding zirconium on uranium by a direct casting process. 2) To investigate the diffusion of liquid metals in the fusion zone."

This report covers the following titles: (1) A versatile solvent to replace phenol for the paper chromatography of radioactive intermediary metabolites; (2) Chromatography of plant lipids on alumina paper; (3) Quinone and pigment composition of chloroplasts and quantasomes from Spinacea oleracea; (4) The lipid composition of chloroplast lamellae from Spinacea oleracea; (5) Metal chelates and photochemistry of flavins; (6) Photoinduced ESR in some solutions of organic electron donors and acceptors; (7) Fluorescence of oriented dye-macromolecule complexes--Theoretical study; (8) Formation of adenine by electron irradiation of methane, ammonia, and water; (9) Uptake of organic compounds by planarians; (10) The planaria: Absorption spectrum, cell disaggregation, and studies on homogenates.

The study of meteorite Murray has been reported in previous Quarterly Reports. This report gives further results with Murray, and information on another meteorite, Orgueil. A sample of Orgueil was sent from the Museum National d Histoire Naturelle, Paris. It fell in several pieces over an area of 2 square miles near Orgueil, France, in 1864. The elemental analysis of this meteorite is shown in Table 1. They extracted a 10.07-g sample of this meteorite with water, using the same procedure as that for Murray. The water extracted 1.32 g, which is at least twice as much material as was water-extracted from Murray. The elemental analysis of the water extract is given in Table II and its uv spectrum is shown in Figure 1. From an x-ray diffraction pattern it was determined that the water extract contained mostly MgSO{sub 4} {center_dot} 6H{sub 2}O with some calcium sulfate. Their spectrum (Figure 2) shows a strong SO{sub 4} band at 1100 cm{sup -1}, = strong H{sub 2}O bands at 1650 cm{sup -1} and 3200-3600 cm{sup -1}, and some unidentified peaks at 2300, 1400, and 980 cm{sup -1}. The approximately 8 g of Orgueil left after the water extraction was then extracted with …

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The introduction of poison splines as operating aid at the Hanford reactors has resulted in an impressive production increase. This increase is mainly due to the effect on startup control and to better equilibrium flux shaping. In providing sufficient reactivity effect for startup control, however, present splines sometimes increase rather than decrease flattening and distribution control problems when utilized during equilibrium operation. In additional being of constant poison strength along their length, they have limited effectiveness for axial flux control and shaping. It has therefore been proposed that in addition to the present spline, the use of two other types of splines with finer reactivity effects might be advantageous. These splines are as follows: (1) To reduce large rod movements and increase flattening efficiency - a spline with uniform poison distribution along its length but only about 50 per cent of the present spline reactivity strength. (2) To increase axial flux control and shaping -- a spline with poison only on the downstream end, no poison on the upstream end.

The processing of Al fuel, principally of the MTR-ETR type, is reported. Processing rate averaged 90% of flow sheet values for the entire operating period, and a U recovery of 99.85% was achieved. Aqueous Zr fuel processing studles continued with the objective of adapting the HF process to continuous dissolution-complexing in order to increase the capacity of the ICPP process while using as much existing equipment as possible to minimize costs. Good results were indicated in a 190-hr run dissolving 2% U-Zr fuel in a Monel dissolver using 4.8M HF-0.03M HNO/sub 3/ dissolvent at 200 deg F; insoluble material did not accumulate in the dissolver, although a U-containing film was formed, apparently in small, equilibrium quantity. Shorter term continuous laboratory dissolutions indicated that 4.8M acid was preferable to 10M acid for the acid feed rate/fuel surface ratios proposed, resulting in dissolver products of greater stability and higher uranium content. Additional laboratory data are presented on UF/sub 4/ hydrate form and solubility, together with maximum dissolvable U compositions with Zircaloy under various flowsheet condltions. Processing of Al alloys containing high Si was found to present no unusual problems in laboratory studies. Siliceous residues resulting from dissolution of Al-U alloys containing 2% …

The development of foam separation as a unit operation was considered from the distributor design and gas rate standpoints. The development of a shear and leach process for power reactor fuel processing is reported in which carburized Yankee prototype fuel assemblies were sheared to determine the effect of fuel element condition on the nature of the chopped pieces. A Squarkeen No. 3 moving blade lasted for 5894 cuts while a Kleencut blade failed at 320 cuts under normal program use. A plastics and coating material testign program for the Transuranium facility is under way. The Vo1atility development program is stadying the recycle of the salt charge for Zr fuel element dissolution and has completed the fourth recycle test. The radioactive waste processing program has completed the test R-65 which studied the movement of mercury out of the calciner during the processing of TBP-25 waste. (auth)

The salivary gland chromosomes of Chironomus tentans larvae collected from White Oak Creek, an area contaminated by radioactive waste from the Oak Ridge National Laboratory, and from six uncontaminated areas were examined for chromosomal aberrations. White Oak Creek populations were exposed to absorbed doses as high as 230 rads per year or about 1000 times background. Chromosomal maps were constructed to make a general comparison of the banding pattern of the salivary chromosomes of the C. tentans in the East Tennessee area with those of Canada and Europe. These maps were used as a reference in scoring aberrations. Fifteen different chromosomal aberrations were found in 365 larvae taken from the irradiated population as compared with five different aberrations observed in 356 larvae from six control populations, but the mean number of aberrations per larva did not differ in any of the populations. The quantitative amount of heterozygosity was essentially the same in the irradiated and the control population, but there were three times the variety of chromosomal aberrations found in the irradiated area. From this evidence it was concluded that chronic low-level irradiation from radioactive waste was increasing the variability of chromosomal aberrations without significantly increasing the frequency. It was …

From introduction: "Cytological examinations of the irradiated and some unirradiated populations in the radioactive sediments of White Oak Creek and the Clinch River were made."

Potential cladding materials for a flat-plate fuel element containing a dispersion of UC or UC/sub 2/ in U--15 wt.% Mo alloy were surveyed on the bases of compatibility with the fissile compounds, matrix material, protective cover materials, and liquid sodium as well as the feasibility of fabricating fuel plates by roll cladding. Radiative-capture cross sections, thermodynamic data, eutectic and intermediate compound formation, mechanical properties, and corrosion by 1000 tained F Na are reported for austenitic stainless steels, chromium, nickel, niobium, molybdenum, tantalum, vanadium, and zirconium. It was recommended that "A" nickel (molybdenum barrier), Zr-3 wt.% Al. Nb--2 wt.% Cr, and Fansteel 82 be relected for investigation. (auth)