Single-phase solid solution UC-- PuC powders were prepared by the carbon reduction of a mixture of UO/sub 2/ and PuO/sub 2/. A simple method was developed to determine the completion of the reaction by analyzing the exhaust gas from the furnace for CO. Four groups of solid solution (U/sub 0.8/Pu/sub 0.2/ )C/sub 0.95/ pellets were prepared for irradiation tests. The groups differed in the enrichment of uranium and in the presence or absence of nickel sintering aid. Without sintering aid, densities averaged about 92% of theoretical; with sintering aid the average density was about 96% of theoretical. The second phase, promoted by the use of nickel sintering aid, was identified as sesquicarbide. IRRADIATION TESTS. The post-irradiation examination of UC specimens irradiated to 16,400 Mwd/tonne (avg) at 1400 deg F and 9.6 kw./ft was completed. The effect of radiation on UC was slight: 0.001 in. diametral increase, 0.4% fission gas release, and no microstructural changes. The (U/sub 0.8/Pu/sub 0.2/)C/sub 0.95/ irradiation tests were redesigned for insertion in GETR. All the irradiation specimens were assembled, and assembly of the capsules was started. One fueled and one dummy capsule were shipped to the test site. (auth)

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Using six hot-wire columns and three concentric tube thermal diffusion columns a cascade system was arranged to produce 0.04 g of 90% C/sup 13/ per day using methane as the feed gas-. The ten liter shipment of purchased methane enriched to 60% C/sup 13/ was received. This gas will be enriched to 90% C/slup 13/. Before removing the equilibrated gas from the concentric tube columns in preparation for using methane enriched in C/sup 13/ as feed material, a sample of methane taken from the bottom of the last column contained greater than 65% C/sup 13/. The hydrolysis of protactinium was found to be completely controllable and reversible and can serve as the basis for its separation from other elements, particularly its decay products. The tendency to hydrolyze is not a unlque characteristic of protactinium, but is exhibited, under appropriate conditions, by Th/sup 227/ and Ra/sup 223/ at trace levels. Traces of protactinium in 1N H/ sub 2/SO/sub 4/ can be removed from solution by a coarse glass wool filter through which the decay products pass readily. The reverse is true if the H/sub 2/SO/sub 4/ concentration is increased to 6N. The desorption of protactinium from platinum was a function of …

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.

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Two techniques for the end-of-life shutdown of orbiting SNAP reactors are presented. One technique consists of two alternative methods for the destruction of the reactor core. This technique (and others) have been investigated during the past year. A second technique, uses a naturally occurring phenomena, which works on the principle of a low neutron absorbing nuclide decaying to a high neutron absorbing daughter (poison). The present design criteria for the latter technique is that only a small reduction in reactivity should occur during the mission lifetime with the slow build-up of poison eventually shutting down the reactor at some later date. Tritium, an isotope of hydrogen is presented as a parent that appears to meet all of the requirements for such an end-of-life shutdown device. The daughter, He/sup 3/ has a high neutron absorption cross section. The results of a preliminary study of the tritium device are presented.

The length of the minimum outage, or period of time during which a reactor must remain subcritical following a shutdown from equilibriu, is a direct function of the available excess reactivity. In reactors with unlimited safety system capacities, it is quite feasible to ``build in`` sufficient excess to allow complete override of the shutdown xenon transient, and thus, in effect, reduce the ``minimum downtime`` to zero. Present Hanford production reactors do not possess this unlimited capacity, and thus total pile reactivity must be restricted by minimum safety strength conditions. Any effort to increase the pile reactivity must therefore be tailored to satisfy existing Total control and Speed-of-control criteria. Production Test IP-467-C. ``Reducing Minimum Downtime,`` was designed to evaluate the economic benefits of a system in which base reactivity can be increased in periods of minimum control requirements, and correspondingly decreased when reactivity or safety considerations become more demanding. The purpose of this document is to summarize initial operating history and results obtained under the production test.

Batch denitration of synthetic Purex waste was investigated in 12 batch runs in the pilot plant denitration unit. Sugar was continuously added to 25 liters of hot waste. After sugar addition was complete, the hot solution was digested for several hours. The reaction proceeded smoothly and was easily controlled. About 19 to 22 moles of nitric acid were destroyed per mole of sugar with a reaction pot temperature of 100 deg C and a digestion period of 12 hours. About 17 moles of nitric acid were destroyed per mole of sugar when the reaction pot temperature was reduced to 95 deg C. A possible plant flowsheet for batch denitration with sugar was developed. This ilowsheet presumes batch denitration of large 2,500-gallon batches of waste in a standard 5,000-gallon Purex Plant tank and incorporates 12 hours of sugar addition and 12 hours of digestion. The flowsheet was successfully demonstrated in the pilot plant equipment. A 1.4M sugar solution was added to 25 liters of hot (100 deg C) waste for 12 hours and the mixture was digested for 18 hours. The initial nitric acid concentration was 6.14M. The residual nitric acid concentration was 0.94 and 0.90M after 12 and 18 hours …

In two previous reports nucleon-meson cascade calculations were carried out for several cases of interest in the design of the transverse shield for the proposed 45-Bev linear electron accelerator at Stanford University. Results are now given for two additional cases. (auth)

Phase acceptance of the Alternating-Gradient Synchrotron Linear Accelerator is theoretically examined and found to agree well with an experimental determination of phase acceptance. Bunching in the AGS linac is also analyzed, the results indicating a satisfactory understanding of this process also. A double buncher that should be more efficient than the present single buncher is discussed, and space charge effects (as yet unobserved in bunching) are analyzed. (D.C.W.)

Information needed to solve nuclear safety problems is condensed into a reference book for use by persons familiar with the field. Included are a glossary of terms; useful tables; nuclear constants; criticality calculations; basic nuclear safety limits; solution geometries and critical values; metal critical values; criticality values for intermediate, heterogeneous, and interacting systems; miscellaneous and related information; and report number, author, and subject indexes. (C.H.)

This report talks about the Alloying Characteristics of the Rare Earth Elements with the Transition Elements

The model used to evaluate the single interstitial migration energy from property changes due to interstitials is extended to account for vacancy contributions. The annealing function obtained can be used to determine the relative contributions of the defects and is sufficiently sensitive to distinguish vacancy effects that are an order of magnitude less than interstitial effects. Application of the model to stored energy and thermal resistivity data yields the same values of the activation energy and temperature independent term obtained from c-axis and macroscopic length expansion rates. The results indicate that the stored energy associated with the di-interstitial is at least ten times greater than the stored energy associated with the vacancy. The minor role of vacancies in phonon scattering is discussed. Analysis of the annealing function obtained from electrical resistivity changes in irradiated graphite indicates that the ratios of charge-carriers to scattering centers varies with irradiation temperature below 55°C. Above this temperature the changes are attributed to equal contributions from vacancies and interstitials.

Vacuum technology is germaine to and is utilized in an extroardinarily widespread scope of the scientific disciplines. From the medical technician freeze drying hog cholera vaccine to the solid state physicist studying thin film phenomena, vacuum technology is an important auxiliary. When one visits the NASA center at Langley and sees the clustered space environmental chambers, looking like a field of grotesque mushrooms, one realizes that vacuum technology is a vital adjunct in this most recent section of our total national scientific effort.

The evaluation of iron absorption using a single crystal whole-body counter is complicated by the inherent difficulty of determining a correct "100% value". Shortly after ingestion, tracer radioiron can be found in the stomach, upper small intestine, portal circulation and liver. Fourteen to twenty days later, the time at which absorption is measured most effectively, the radioiron will be distributed between the red cell mass, liver, spleen, bone marrow and other storage areas. With this mixed distribution there will always be an error because of geometric factors, and hence in counting efficiency, in using the relationship of [formula not transcribed] to calculate iron absorption. In a previous iron absorption study reported from this group, the radioiron retention measured 4 to 10 hours postingestion was used as the "100% value". The present experiments were designed to evaluate the clinical usefulness of the 4 hour postingestion count as the "100% value" as compared to the immediate postingestion body count, and to compare these values with an intravenous Fe59 calibrated absorption. These studies were performed with the realization that there is no absolute solution to the problem.

It has previously been shown that the polymer formed in solid state polymerization of acrylamide is amorphous in spite of the fact that the reaction takes place within a crystalline solid. The stage at which it becomes amorphous is not known at present. Work with dilute solid solutions of acrylamide in propionamide suggests that this occurs after the addition of, at most, a very few monomer units.

Reciprocal labelling in double-labelling experiments with H3- and C14- thymidine showed that when H3- thymidine (1μc/ml for 0.5 hr) was given first in the labelling sequence followed by a 4 hr interval before the C14- thymidine treatment, that passage of cells into and out of DNA synthesis was normal. When C14 was first in the sequence, the rate at which cells entered DNA synthesis was decreased. This was attributed to a radiation effect produced by the β-rays from the C14. The rate at which cells entered DNA synthesis was studied after 0.1, 1 and 10 rads of x-rays. A dose of 1 and 10 rads decidedly depressed the rate. Treatment of roots with 2, 20, and 200 μc/ml of tritiated water for 0.5 hr showed that the 2 higher concentrations produced an effect similar to the x-rays. This indicated that somewhere between 1 and 8 disintegrations per cell per 0.5 hr will produce a decrease in the rate at which cells enter DNA synthesis. In both the x-ray and H32O experiments the depression of the rate that cells entered DNA synthesis seemed to reach saturation at the higher doses.

The new sector-focused cyclotrons have more energetic and better focused beams at the extraction radius than do ordinary cyclotrons. While the first characteristic requires a more intense electric field, the second permits this field to extend over a smaller volume. By tailoring the electrode geometry to these characteristics of the beam, the required deflector gap and electrode surface become smaller, and a higher gradient can be held without sparking. A different compromise between radioactivity, power dissipation, and resistance to spark damage must be made in selecting electrode materials. Carefully designed electrostatic deflectors perform very well in sector-focused cyclotrons of intermediate energy. Deflector efficiencies of about 50% and external-beam intensities of 20 {micro}A have been obtained in the Lawrence Laboratory's 88 -Inch Cyclotron.

To evaluate the crudding characteristics of ammonium hydroxide conditioned coolant it is necessary to use a thermocouple element. The present design has accentuated structural integrity, reliability and constant heat flux. A radical departure from past designs was made by selecting a stainless steel cladding and enriched ceramic fuel. Three thermocouples are inserted in the cladding to increase the reliability. By the use of two thermocouple elements it will be possible to obtain important preliminary information on preferential crud deposition while simultaneously evaluating the crudding characteristics of ammonium hydroxide conditioned coolant.

From Introduction: "These first three chapters from a background of introduction and general ideas about dislocations. The next two chapters are concerned specifically with properties of ceramic materials, with emphasis on single crystals."

An accurate determination of the parameters of the resonance excited by the interaction of the 132 eV neutrons with the Co 59 target nucleus has been made, using the fast choppers at Brookhaven National Laboratory in the United States and Chalk River Laboratory in Canada. Neutron transmission through thick and thin samples resulted in the following parameters: [parameters not transcribed]. In addition, measurements of the resonance capture γ-ray intensity gave the value for the radiation width Γγ= 0.40 ± 0.04 eV, based on the known thermal capture cross section of cobalt of 37.5 barns. The reduced and total resonance capture integrals are calculated from the above parameters to be 50.5 ± 5.5 and 67.0 ± 5.5 barns, respectively. The above results are compared with previously determined resonance parameters and also with direct measurements of the total resonance capture integral.

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The pile power level curve, which includes data from PT 528 High Tank Drawdown Test and heat decay test, represents allowable power level for a given average High Tank temperature.