Forty-two instrumented burnout points are reported for the second l2-rod test section which had 0.440-in diameter rods with a minimum spacing of 0.022 in. be een rods. Each rod was wrapped with a 0.022-in. wire. The rods were arranged in a 3 x 4 array to form a 60 deg parallelogram. A contoured housing maintained the minimum spacing between the outer rods andd the housing wall. The tests were performed with vertical upflow at 1200 psia. The ranges of variables studied were: mass velocities from 0. plus or minus to 4.1 x 10/sup 6/ lb/hr-ft/sup 2/, exit steam qualities between 2 and plus or minus 2%, and instrumented burnout heat fluxes as high as 1.28 x 10/sup 6/ Btu/hr-ft/sup 2/. The burnout results showed a strong direct mass velocity effect at exit qualities below 10%. Above 10%, and inverse mass velocity effect was seen to develop particularly at high mass velocities. All the burnouts were observed to take place on outer rods facing the unheated housing walls. Hence, these results provide and estimate of the burnout performance of only the outer rods since the irterior rod surfaces have higher burnout heat flux limits in this geometry. A qualitative analysis is …

A twin rod-conduction calorimeter for routine assay of small radioactive sources is described. The equilibration time is about forty minutes and the detection limit about 1 x 10/sup -4/ watt. A thermistor circuit and nonlinear potentiometer are used for the differential temperature measurement. Use of a plutonium sample for calibration is described. (auth)

The Consolidated Nuclear Steam Generator H consists of a pressurized water reactor, a steam generator, and a pressurizer combined in a sirgle pressure vessel. The design of the 66000 shaft horsepower system is presented, together with basic plant irformation for designs of 15000, 22000, and 30000 shaft horsepower. The economics, safety characteristics, and operational procedures of the plant are also discussed. (D.C.W.)

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Work in the development of fluid-bed fluoride volatility processes is described. In these processes, uranium and plutonium in spent nuclear fuels are converted into hexafluoride compounds in a fluid-bed reactor. The uranium and plutonium hexafluorides are volatile and can be separated from fission products, cladding, and alloying materials by techniques such as vaporization and distillation. The experimental work was directed toward devising a fluorination procedure for uranium and plutonium dioxides which would result in a high degree of removal of uranium and plutonium as hexafluorides. In these experiments synthetic mixtures made up to simulate a charge for a fluidized bed reactor (100 kg U, 0.4 kg Pu, approximates 1 kg F.P., and 30 kg inert solids) were used. High-purity recrystallized alumina was found to be a suitable material for use as the fluidized inert solid. After a 10-hr fluorination period at 450 deg C, the concentrations of residual uranium and plutonium on the alumina were 0.01 and 0.03 wt%, respectively. A reaction temperature of 450 deg C was found to be optimum, since experiments at 500 and 550 deg C resulted in plutonium retentions on the alumina of 0.060 and 0.090 wt%, respectively. At all these temperatures, the residual uranium …

The conventional sampling methods of filtration and impaction are generally utilized in the collection of air samples at Hanford. In addition, a Goetz aerosol spectrometer is available for special studies. Particle-size determinations are made by autoradiographic studies making use of both optical and electron microscopes. A supplementary tool sometimes utilized is the Royco Particle Counter. The study included an analysis of the potential usefulness and the limitations of these air sample study methods for plutonium aerosol particle size measurement. Preliminary results, from a continuing study of the particle size distribution in normal and abnormal air, show particle sizes ranging from hundredths to tens of microns. The studies include considerations of the usefulness of particle size data in planning biological experirnents and in the application of these data to human internal deposition cases. (auth)

The assessment (by ground testing) of effects of mechanical actions, thermal and chemical interactions, and nuclear reactions upon tue safety of nuclear power sources that are intended for aerospace applications is discussed. Progress in general studies and in testing of SNAP-9A and -10A is reviewed. (T.F.H.)

Statistical rules to be used in estimating and interpreting the net sample counting rate in the presence of appreciable background are developed. The importance of good background estimation is considered. (D.C.W.)

The absorption spectra for single crystal and polycrystalline UO/sub 2/ were measured between 0.6 and 15 mu at room temperature. The spectrum for UO/ sub 2/ resembles that of a typical semiconductor, opaque in the visible but transparent over a large portion of the infrared. The absorption edge is located at approximately 0.6 mu (2.0 ev). A large optical window extends from 3 to 13 mu . The absorption coefficient for single crystal UO/sub 2/ was determined between 1.5 and 15 mu . A maximum value of 57 cm/sup -1/ was measured at 1.70 mu with minimum values of 6 cm/sup -1/ at 2.75 and 8 mu . The absorption coefficient of polycrystalline UO/sub 2/ at wavelengths less than 8 mu is estimated to be ten times larger than for single crystal UO/sub 2/. (auth)

Irradiated specimens of 39 wt% U/sub 3/O/sub 8/ dispersed in aluminum and of aluminum-17.3 wt% uranium alloy were andnealed. Each specimen was partially clad with aluminum. Gross swelling was not observed for the aluminum- 39 wt% U/sub 3/O/sub 8/ dispersion specimens for burnup and annealing temperature levels ranging up to 1.0 x 10/sup 20/ fissions per cc and 550 deg C, respectively. Small volume increases were found, however, and these were attributed to the aluminum reduction of U/sub 3/O/sub 8/, which is accompanied by measurable volume increases. X-ray diffraction andalyses confirmed the reaction between the U/sub 3/O/sub 8/ and the aluminum matrix. The dispersion specimens and, in particular, the U/sub 3/O/sub 8/ particles sintered during irradiation at temperatures from 55 to 90 deg C in an effective thermal-neutron flux of between 1 and 3 x 10/sup 13/ nv. Annealing at 550 deg C produced severe localized blistering on specimens of aluminum-17.3 wt% uranium alloy having burnups of 5.9 x 10/sup 20/ fissions per cc. Similar conditions produced only a small uniform volume increase when the burnup was 1.4 x 10/sup 20/ fissions per cc. The observed stability is attributed to a defect structure in the compound UAl/sub 4/ in which …

The resonant beam extraction system of Cambridge Synchrotron is described, and measurements of the extraction efficiency and extracted beam properties are compared with values predicted by calculations. (auth)

A spherical component is frequently supported by a hemispherical lightweight cellular core which is in turn supported by a flexible elastic support shell. Design information is given on computing the normal and shear stresses in the core as well as circumferential and meridional stresses in the flexible support shell. A set of graphs is given showing the ratio of these stresses for the case of a flexible support shell to the corresponding maximum stress for the case of a rigid support shell, plotted against the meridional angular coordinate of the hemisphere. Two dimensionless geometrical and material parameters appear as variables in these graphs. A second set of graphs to be used for obtaining displacements of the flexible shell with respect to the supported sphere are also plotted in this manner. For computing the maximum stresses in the shell or core, a graph is given showing the maximum value of the stress ratio plotted against a dimensionless material-geometrical parameter. (auth)

A summary is presented of the broad field of graphite irradiation capsules. The various capsule designs are considered; they include temperature- controlled and temperature-monitored capsules. The components and materials of the capsules are described. Finally, methods are given for carrying out heat trandsfer calculations in capsule design and neutron spectra calculations for correlation of radiation data from different reactors. (D.L.C.)

Progress in the development of the Sioux Falls Power Reactor is reported. Information is presented on: reactor physics of first core high-enriched boiler fuel elements; design and performance testing of in-core ion chambers, calibration wire, and monitoring system; testing and inspection of core components; irradiation testing of reactor vessel material; instrumentation development; and startup testing program. (N.W.R.)

By taking into consideration temperature differences between the glovebox atmosphere and the liquid, it was possible to make density measurements in gloveboxes by the hydrostatic weighing method with monobromobenzene as a liquid with an accuracy of plus or minus 0.005 g/cm/sup 3/. This is an improvement by an order of magnitude over the prior state. This accuracy allows structural changes to be detected in thorium--uranium and thorium--plutonium alloys. (auth)

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This report contains tie rod component pressure drop coefficients computed from data obtained in tests in which gaseous hydrogen was used as the working fluid.

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This report contains seven different configurations of support blocks.