This report describes research, development, support, and test activities in the Sandia Laboratory Aerospace Nuclear Safety Program.

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The activation energy, activation volume, snd frequency factor were evaluated for yielding (delay time for yielding, upper yield stress, lower yield stress, and Luders band propagation) and flow (friction stress, flow stress, and dislocation mobility) for various irons and steels from data in the literature. It was found that the values of these flow parameters and their stress dependence were the same, within experimental error, for both yielding and flow, and for all the materials considered. This suggests that either the same dislocation mechanism is controlling in every case, or that one or more mechanisms possees approximately the same values for these parameters. The dislocation mechanism for which there was closest agreement between theoretical calculations snd experimental data was overcoming the Peierls stress. On the basis of the available experimental data and the present analysis, it is suggested that the upper and lower yield stresses in iron and steel may represent the sudden generation of a large number of dislocations by the double cross-slip mechanism of Koehler and Orowan, rather than the breaking away from a Cottrell atmosphere. (auth)

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Consequences of a generalization of the theory of superconductivity that yields a finite Knight shift are presented. In this theory, by introducing an electron-electron interaction that is not spatially invariant, the pairing of electrons with varying total momentum is made possible. An expression for Xs (the spin susceptibility in the superconducting state) is derived. In general Xs is smaller than Xn, but is not necessarily zero. The precise magnitude of Xs will vary from sample to sample and will depend on the nonuniformity of the samples. There should be no marked size dependence and no marked dependence on the strength of the magnetic field; this is in accord with observation. The basic superconducting properties are retained, but there are modifications in the various electromagnetic and thermal properties since the electrons paired are not time sequences of this generalized theory on flux quantization arguments are presented. (auth)

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Daily river temperature cycling has existed at reactor area river pumphouses from the beginning of operations. Of small account at first and due only to the daily air and solar radiation cycle, the phenomenon became significant with the initiation of daily river flow cycling at priest Rapids Dam to meet changing power generation requirements. The problem was compounded by the construction of the N reactor, placing a water intake and outfall at approximately half the previous distance between the K and D reactors. The decidedly non-uniform effluent distributions in the river at the shorter distances has caused apparent daily temperature swings at 181-D. This distribution was determined by the use of rhodamine B dye. Estimates of the relative contributions over a range of river flow to the temperature cycling at 181-N were made. A similar evaluation of the relative contributions at low river flow only at 181-D from K and N reactor operations has been requested by Douglas United Nuclear, Inc. This report is made to satisfy that request.

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Standardized test facilities were developed and operate for investigating the compatibility of structural materials and flowing molten fluoride salts. The standard loop accommodates various combinations of materials, fluid, flow, rates, and temperature differentials and permits fabrication of components in sufficient quantity for cost reduction. The test loop consists of a pump, two heated sections, a cooled section, a drain tank, and a frozen-plug-type valve. Automatic controls and equipment were developed to prevent solidification of the salt mixtures (mp, 800 to 1100 un. Concent 85% F) in the event of a loss of power. Most test loops were fabricated of 0.5-in.-OD, 0.045-in.-wall tubing, and operate with a temperature differential of up to 200 un. Concent 85% F, a maximum wall temperature in the range 1200 to 1500 un. Concent 85% F, and a salt flow rate of up to 3 gpm. Twenty-five test loops were operated for an accumulated operating time of 290,00 hr. Individual loops were operated continuously for more than one year. (auth)

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>The Yiftah, Okrert, and Moldauer cross-section set (ANL Set 135) was modified to include new measurements of nu and alpha for U/sup 235/, and to include, in an approximate manner, Hummel, Rago, and Meneghetti's corrections for flux depression at resonance energies in Al and stainless steel. This modified set, ANL Set 635, was used to compute values of k for 22 ZPR-III assemblies of widely varying composition. The DSN neutron transport code was used in spherical geometry and the S4 approximation; shape factors were used to convert from cylindrical to spherical geometry. Seventeen of the calculated values of k lie within plus or minus 1% of a mean value of 1.003, and the remaining 5 lie within plus or minus 2%. In terms of prediction of critical mass, it appears that the procedure used here can achieve an accuracy of 5% to 10% for a wide range of U/ sup 235/-fueled assemblies. (auth)

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The distortion behavior of graphite as a function of irradiation temperature is reviewed. The behavior of needlecoke and CSF graphite was examined over moderate exposures in the GETR. Results showed needle-coke to be less contracting than CSF. Details of contraction show a minimum contraction rate per 10/sup 21/ nvt at 600 to 800 deg C for both types. Limitations to be placed on the data presented are listed. (P. C.H.)

We are enclosing three copies of a proposal concerned with the preparation for preliminary evaluation of up to 128 Hanford CV size I and II fuel elements to determine an optimum gas-pressure-bonding cycle for the fabrication of this type of fuel element. This proposal is based on your request as outlined in your letter dated May 7, 1962, and document No. HW-72417. Included is a cost estimate of the funding required to conduct this experimental study. All of the aluminum-clad uranium fuel assemblies are to be prepared and furnished by HAPO for gas-pressure bonding at Battelle in existing equipment. To implement the proposed program we have also enclosed six copies of the BMI-AEC research agreement (Serial No. 88). The agreement provides for a six-month research period with an estimated total cost of $24,780. This sum includes $1,180 find fee as established in Contract No. W-7405-ENG-92. Receipt of two fully amounted copies of the agreement, classification guidance, and the specimens will allow us to proceed.

The solubilities of uranyl dlbutyl phosphate, uranyl monobutyl phosphate, ferric dibutyl phosphate, and ferric monobutyl phosphate were measured in aqueous nitric acid solutions ranging from 0 to 3 M and in 30% TBP in Amsco 125-82 solution containing 0--0.7 M HNO/sub 3/. For the respective compounds in the aqueous phases, as the acidity increased from 0 to 3 M, the solubilities increased from 0.004 to 0.7 g U/liter, O.O5to 50 g U/liter, <1 to 30 mg Fe(III)/ liter, and 0.003 to 3 g Fe(III)/liter; corresponding solubilities in the organic phases increased with acidity from 14 to 165 g U/liter, 11 to 110 g U/liter, <O.5to 4 mg Fe(III)/liter, and <0.002 to 1.5 g Fe(III)/liter. All these compounds foamed or formed very flocculent solids in the aqueous phases snd tended to settle slowly in the organic phases and rise to the surface in the aqueous phases, suggesting that they would be interface seekers in two-phase aqueousorganic systems. (auth)

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This report itemizes the irradiations performed by Testing for Battelle-Northwest. It lists the material being irradiated, awaiting disposition and material shipped during the report period.

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