Examinations of three Inconel pump impellers were made to establish the extent of cavitation damage and degree of carburization sustained during pump endurance tests. The pumps, two of which circulated fluoride salt and one sodium, operated for the bulk of the test programs in the temperature range 1000 to 1250 deg F. Cavitation damage was manifested in each of the impellers by the formation of deep pits (in excess of 1/4-in.), the location of damaged areas varying with impeller geometry. Pit formation appeared to have occurred by uniform rather than preferential removal of metal components. Each of the impellers exhibited heavily carburized zones along exposed surfaces. The cause of carburization may be associated with the type of gas purge utilized for these pumps. (auth)

The tendency of various classes of pure hydrocarbons to form zirconium- complexing ligands during chemical or radiolytic degradation was evaluated. Olefins and aromaticcycloparaffins (mixed type) formed the most ligands and normal paraffins the fewest. (auth)

A test was performed at the Shippingport PWR, whose purpose was to determine the amount of heat the fuel shipping container cooling system was capable of removing while in a state of equilibrium. Studies were also conducted to determine if after four hours of operation, the increase of the internal wall temperature was less than 30 deg F, and finally, to determine the effects of loss of cooling water from the fuel shipping container. (auth)

The effects of two contained H. E. explosions in volcanic tuff were examined by mining directly into the explosion sites. Ore explosion (516 lb of TNT) increased its initial shot chamber volume of about 9 cu ft by a factor of sbout 5 and produced in addition some 126 cu ft of broken rock. Around this explosion, only natural joints in one direction were filled with carbon to a maximum distance of 42 ft, and no new fractures in other directions were developed. The other explosion (973 lb of TNT) expanded its 17 cu ft chamber to 10 times this initial volume and led to rock breakage, mostly by subsequent roof collapse, of 345 cu ft. Because this shot vented on firing, very little of the carbon-carrying gases entered joints, and fractures caused by the explosion are almost absent. The features characteristic of these two explosions were compared to an earlier 1000-lb explosion in salt in which, by contrast, numerous radial carbon-filled cracks were produced, and the less expanded chambers survived without collapse. For the explosions in tuff it was concluded that joints exercised a primary role in locating the surfaces of fracture failure, early venting inhibits development of carbon-marked …

The beta spectra of In/sup 114/, P/sup 32/, and Y/sup 90/ were stud ied closely in an intermediate-image beta-ray spectrometer and compared to theoretical predictions in terms of a linear shape factor of the form (1 + aW). The values obtained for a were s for P/sup 32/, and (-0.0047 plus or minus 0.0008)/mc/sup 2/ for Y/sup 90/, all for electron kinetic energies from about 200 kev up to near the maximum beta energies. Tests were made to give indications for spectrometer fidelity. Because of the linearity of the shape-factor plots and the similarity in energy range, the comparative results from In/sup 114/, P/ sup 32/, and Y/sup 90/ are tak en as a definite indication that for at least two of these activities the shape factors have nonzero slopes, irrespective of questions of instrumental fidelity. (auth)

A test on the Shippingport PWR was described, whose purposes were to determine if sufficient reactivity was present in the core to override a peak xenon transient, and to obtain data for rod worth calculations. Equilibrium xenon was established at 60 Mw net electrical output for approximately 35 hours prior to shutdown. The flux was then reduced to approximately 100 mu mu a. The reactor was maintained critical by withdrawing or inserting rods as necessary. Startup rates were measured by a mu mu ammeter. The xenon transient was followed in this manner for 60 hours. Override of peak xenon occurred 8 hr 50 min after shutdown. (auth)

The dynamic (gas saturation) method was used to determine upper and lower limits for the dissociation pressure of the complex formed when MoF/sub 6/ is absorbed by NaF. The limits were 0.4 to 4.6 mm Hg at 100 deg C and 8.4 to 27 mm Hg at 150 deg C. A lower limit, 64 mm Hg, was determined at 200 deg C. As a check on the method the dissociation pressure of the complex UF/sub 6/ - (NaF)/ sub 3/ was determined at 100, 200, and 240 deg C. The measured values were in satisfactory agreement with accepted values of dissociation pressure for this compound. (auth)

A test was designed and performed to experimentally determine fuel burnup distribution in the SM-1 Core I spent fuel elements. It was believed to be feasible if the spatial distribution of the gamma rays emitted from a long- lived, unsaturated fission product could be measured. However, scintillation spectra indicated an intense peak between 0.7 and O.8 Mev, primarily attributed to the 63day Zr/sup 95/ fission product and 35-day Nb/sup 95/. The magnitude of this peak nullified the possibility of distinguishing a long-lived fission product that could be used for scanning purposes. The stationary elements of one quadrant of the core were scanned using the Zr/sup 95/-Nb/sup 95/ peak as the energy interval. The results represent a fair approximation of the power distribution in SM-1 Core I during the latter portion of operating history. Results of the experiment are presented with a description of the techniques and test equipment used. (auth)

Tests were conducted to determine the direction and magnitude of any short- or long-term drift in core thermocouples, primary loop and pressurizer resistance thermometers, and resistance thermometers located in the secondary side of the boilers for Seed 2 at 2303 EFPH. It was found that drift in the core thermocouples is definite but random. Other findings are discussed and calibration data are presented graphically. (J.R.D.)

CORE 1, SEED 2. Test Results T-612081. Section 3. (Duquesne Light Co., Shippingport, Penna.). First issue, Apr. 20, 1961. 28p. . The reactor was operated at full power to obtain equilibrium xenon concentration and then shutdown for 8 1/2 hr to obtain peak xenon concentration. It then was brought to 75 and then 67% of full power; the xenon concentration returned to an equilibrium value 4 hr after reactor startup. There was no apparent effect on the nuclear instrumentation caused by xenon concentration changes. Values of rod worth were determined, and operating characteristics during the test are given. (D.L.C.)

Film growths on aluminum and two aluminum-1 wt.% nickel alloys in water at 250 and 350 deg C were studied. It was found that oxide growth does not advance on a uniform front but, to the contrary, the advancing surface contains many outcrops in the form of thin platelets, chunky outcrops, and whiskers. With both the pure metal and the alloys considerable intergranular attack was observed. The general corrosion product was usually more uniform in crystal size when formed on the pure metal, but variations in crystal size were observed on both aluminum and alloys with varying features of the metal surface. The roughness of the general oxide surface (includlng outcrops) was found to increase rapidly to about 0.2 micron and then remain relatively constant with increasing film thickness. The composition of films formed under all investigated conditions, except one, was found to be boehmite ( alpha -Al/sub 2/O/sub 3/- H/sub 2/O). This exception was films carried by the alloy specimens after testing for 32 days at 350 deg C. In this case the main corrosion film was still boehmite, but in addition the outer surface supported long needles of diaspore ( beta -Al/sub 2/ O/sub 3/- H/sub 2/O). (auth)

A summary is presented of the development status, through 1960, of work done on: Core A, the U--10 wt.% Mo fuel and U--3 wt.% Mo blanket, and Core B, the U0/sub 2/--SS cermet and the UO/sub 2/ axial blanket for the Fermi Fast Breeder Reactor; advanced fast reactor fuels; and paste fuels. (B.O.G.)

Two concepts were investigated as possibilities for the next loading of EBWR. One is a light water spiked plutonium recycle system; the second is a conventional uniformly loaded system with the option of different enrichments in two radial zones. It is concluded that the plutonium recycle scheme is not feasible in EBWR at 100 Mw, and recommendation for a two-enrichment loading for various burnups is made. (auth)

Corrosion tests in dilute phosphoric acid (pH 3.5) at elevated temperature are described for X8001 aluminum, 18-8 stainless steels, aluminized carbon steel, and Zircaloy. In a 307-day dynamic test at 18 ft/sec and 315 deg C, X8001 aluminum corroded at a rate of 1/2 mdd for the first 240 days. In subsequent exposures, the corrosion rate increased, but the total average penetration at 307 days was only 0.0005 inch. At 200 days, the total corrosion in this test was one-fiftieth that in distilled water. Static tests at 225 deg C gave corrosion rates too low to measure (<0.2 mdd). Of several different 18-8 stainless steels tested in this solution at 315 deg C, only sensitized type 316 suffered intergranular attack. General attack rates of the other samples, of the order of 1/4 mdd, were obtained for the period from 94 to 186 days. Although this is much larger than the rate in distilled water, it represents a penetration rate of only about 5 x 10/sup -//sup 5/ inch/year. Aluminized carbon steel did not suffer rapid corrosion in this solution at 315 deg C, even when large areas of the carbon steel were exposed. There was a tendency for corrosion to …

Tests were conducted to obtain data on the dynamic response of the plant to various power range control rod withdrawal transients. The Reactor plant responded generally as expected. Comparison of data with simulator studies revealed that transients were more severe and had less measurable differences between the 20, 40, and 60% power runs than those transients predicted. (J.R.D.)

An analysis of the EGCR core structure was made to determine the lateral deflections (bowing) of the graphite columns resulting from shrinkage caused by fast-neutron irradiation, the life expectancy of each column due to restraints imposed on the bowing, and the reaction forces induced in the supporting structures. Based on currently avallable data for EGCR type graphite shrinkage and assuming experimental loop operation, a maximum bowing potential of 3.61 in. was calculated for an interior column. It was found that strains equivalent to the rupture strains observed from tensile tests could be expected after 4 to 6 years of full-power operation. Over half of the columns will reach these strains before the 20-yr reactor design life is reached. (auth)

ABS>An experiment was performed to determine the effects of nonpickling versus pickling to depths of one and two mils on the corrosion resistance of Zircaloy-2 machined by various methods. No significant difference in corrosion rate between pickled and unpickled Zircaloy-2 was found, provided that properly sharpened and hardened tools were used. (auth)

Thermodynamic data for liquid and gaseous water were compiled and extended to limits of pressure and temperature imposed by Hugoniot, adiabat, and Thomas-Fermi model considerations. The internal energy variation is discussed. (auth)

A structural evaluation is presentsd of the Hallam Power Reactor fuel elements. The fuel rcd spacer examined is an interim design, but the final spacer is considered to be adequately represented by the analysis of the interim design. Loading of the spacer is considered at temperatures up to 600 deg F. The maximum stress in the hanger rod is found to be 4700 psi. Creep in the fuel rod cladding from internal pressure is predicted to be 5.2% after 48 months of operation, based on a predicted volumetric growth of 15% caused by irradiation. Data indicate that the actual volumetric growth is only 6%, so that the predicted results are quite conservative. (T. F.H.)

A program was written to perform polynomial least squares fits on the IBM 7090 computer. Weighting factors may be included with the data if desired. The program includes a subroutine which does the fit and furnishes the calling program with the coefficients, standard errors in the coefficients, staandard error of fit, and information necessary to compute a complete error analysis; and a calling program which reads input, calls the subroutine, and writes requested output. The subroutine may be used separately in any Fortran or FAP program where a least squares fit is needed. (auth)

The proposed use of unclad, urania-impregnated graphite fuel elements in experimental and power reactors raised the question of how best to reprocess the elements after irradiation. A grind-leach process using boiling nitric acid was previously suggested as alternate to earlier combustion techniques. Besides requiring pre-grinding of the elements the process did not leave a residue sufficiently low in radioactivity when the elements contained initially less than 3 wt% uranium. Application of ultrasonic vibratory energy tc the graphite during this process increased leaching rate and completeness tc such an extent that the practical process limit of 3% uranium is no longer a problem. The ultrasonic studies were carried out with non-irradiated specimen plates and ground pebble specimens. The plates apparently can be leached in practical time span to such a low level of radioactivity that disposal of the graphite residues is simplified. Furthermore it appears that the pre-grinding of the spent elements can be eliminated. Direct activation of the intact fuel plate specimens resulted in leaching efficiency at least as good as with ground specimens. (auth)

It is shown that the magnetic moments of odd-A deformed nuclei can be interpreted in terms of the independentparticle model with interconfigurational mixing due to the very-short-range residual forces. The latter are implied by using the empirically reduced spin gyromagnetic ratios. The effects of these residual forces on the collective gyromagnetic ratios g/sub R/ are discussed in terms of pair correlation. The effect of particle-rotation interaction on the magnetic moment and the collective gyromagnetic ratio are shown. The g/sub R/ values are obtained from the magnetic moments and the matrix elements for M1 transitions in tais band. It is found that these mechanisms give a satisfactory account of the collective gyromagnetic ratio of Dy/sup 161/, Ho /sup 165/, Er/sup 167/, and Hf/sup 179/. (auth)

The surface areas of several thorium oxide and thorium oxide--uranium oxide preparations were measured by the emanation method. The radioactive gas- counting system employed is described, and a discussion of the procedure for converting counting data to terms of emanating power and finally to surface area values is given. Surface area values by the emanation method were compared with BET values from like samples. The difference between values obtained by the two methods was attributed to the efficiency of the radioactive gas-detecting system and the porosity of the oxide samples. The contribution of Rn/sup 2//sup 2//sup 2/ from the oxide samples containing uranium was found to be negligible and presented no problem. Samples fired at temperatures above 1500%DEC for one hour in air exhibited a marked increase in "room temperature" emanation rates. The predicted lattice-loosening temperature of metal oxides is approximately one-half their absolute melting point. Above this temperature, sufficient thermal agitation is induced to permit exchange and possibly permanent displacement of atoms in the crystal lattice. Therefore, firing these oxide preparations at temperatures above 1500 deg C would probably result in lattice defects throughout the crystal structure, with the surface defects contributing to an increase in surface area and …

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