A set of calculations has been done to determine the amount by which the volume of solid material in a Tory II-C core can be reduced with respect to the total core volume. Three separate problems were studied. In each case, some change was made which by itself would increase the K[sub eff] of the reactor. Then, in order to keep K[sub eff] unchanged, a certain amount of core material was removed. The calculations were done by means of the one-dimensional neutronic diffusion code ZOOM. The base problem ZR 1008 on which the variations were made is a cross section of Tory II-C as represented in two dimensions by ANGIE problem RZ 501. The cross section is taken at a distance of 0.3 of the length of the reactor from the front surface, and the Z dimension is adjusted in ZR 1008 so that K[sub eff] is the same as for RZ 501.

This study was undertaken to answer questions asked regarding the required rod stroke for control of modified Tory II-C reactors. All problems described were solved with the Angie code and based on Tory-II-C design problems, RZ 501 and RZ 502, representing hot and cold reactors respectively.

Quarterly report regarding the activities of the Yankee Core Evaluation Program, the purpose of which is to evaluate the performance of the core used in the Yankee Plant and to compare actual performance with predictions, as well as the revision of designs to address any differences between actual and predicted performance.

Introduction: The purpose of this experiment is to determine the loss of electrical power output due to operating many unequally-heated cesium diodes, connected in series and parallel circuits.

The diffusion of lithium in aluminum was measured at various temperatures with diffusion couples of aluminum-LiAl. The activation energy, E, is 33.3 kcal/mol, and the diffusion factor, Do, is 4.5 cm{sup2}/sec. (auth)

The development of equations used for determination .. starting weights of the individual mix batch constituents is presented. Experimental data resulting from batches compounded in this manner are shown for uranium loading, carbon density, and composite density of as graphitized natural uranium loaded fuel elements.

Tests were run to determine burnout conditions for sn electrically heated rod in a circular tube with an annular flow path for the upward water flow. The conditions correspond to those which might exist in a reactor core. The burnout results for the basic test geometry (straight concentric annulus) showed that a plot of burnout heat flux vs quality is a straight line with a negative slope, and that the burnout heat flux is increased by a decrease in flow or an increase in pressure, while the hydraulic diameter has a maximum effect on the flux at 0.25 to 0.5 inch. A correlation of the results is given for a certain range of conditions. The following modifications of the basic test geometry were also tested: eccentric rod, simulated spacer, sandblasted rod, and rough liner. The eccentric rod and sandblasted rod decreased the burnout heat flux, while the simulated space had no effect, and the flux for the rough liner is greater than for the smooth liner. The basic test geometry data are compared with other internally heated annular data and with multirod data. (D.L.C.)

This report addresses the comments on proposed LASL LN$sub 2$ system.

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A review is presented of work on deformation twinning in fcc metals. Experiments which prove the existence of deformation twins are described, the characteristics of the twins are reviewed, and the stresses required for their production are analyzed. The dislocation models which have been proposed to account for the nucleation of deformation twins are reviewed. A model is proposed for the propagation of twins. (D.L.C.)

The Large Component Test Loop is a facility for ASCR providing experimental capacity for subjecting large components, such as moderator assemblies and control rods, to thermal gradients and transients at varying rates of sodium flow to simulate reactor operating conditions. Two separate loops are used for heating and cooling the sodium as the testing is performed. The 3-inch pump loop, modified to operate at 1200 deg F, was operated at a flow of 130 gpm and a head of 25 feet. The 6-inch pump loop, limited to 1000 deg F operation by materials of construction, was operated at a flow of 2000 gpm and head of 65 feet. The rest of the facility has operated satisfactorily at 1200 deg F. (auth)

Modern {beta}-ray spectrometers are based upon the concept, first introduced by Svartholm and Siegbahn in 1946, of focusing in both the radial and vertical directions. The theory of axially symmetric devices has been carefully studied by a large number of workers, culminating in the analysis, in 1956, of Lee-Whiting and Taylor. These last authors calculate aberrations through the sixth order and show that by appropriate choice of the magnetic field a spectrometer can be designed with a relatively large transmission and a high resolution. The acceptable transmission is remarkable because the second-order 'spherical' aberration in the median plane of the image cannot be made to vanish identically, and consequently the design is forced to a tall thin aperture (or a slightly less advantageous short wide aperture) which a priori would seem to imply a low transmission. It is the purpose of this communication to show that if the arbitrary restriction to axially symmetric fields is removed, then both the radial and the vertical contributions to the 'spherical' aberration can be made to vanish in second order. That azimuthally varying field (AVF) afford the freedom to accomplish this end may well be suspected in view of the technological revolution that the …

This document reflects our comments on the drawings and design information that we have received. It is therefore contingent upon the drawings and specifications which we have not as yet received from Vitro Engineering Company.

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The basic heat transfer and flow equations applicable to studies of flow oscillations in NERVA engines are first linearized, then expressed as difference-differential approximations, and finally written in a form suitable for analog computer solution. Block diagrams are presented which illustrate on analog procedure for solving the linearized, difference-differential equations.

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A method of calibrating control drums in a subcritical assembly with a source is given here as an to WANL- TMI- 458 which discusses the measurement of shutdown reactivity in a subcritical core

This report talks about the Comments on E-MAD Phase II drawings received between 2/14/63 and 2/19/63

A new, dry process for the production of UO/sub 2/ powder from UF/sub 6/ by fluidization and particle-coating techniques was developed. The process involves direct conversion of UF/sub 6/ to a solid, UO/sub 2/F/sub 2/, by hydrolysis with steam and the reduction of the UO/sub 2/F/sub 2/ to the dioxide by reaction with was carried out in 3-in.-dia. Monel reactors. In continuing studies, dense, spheroidal UO/sub 2/ particles in the range --20 +200 mesh are being prepared. A simultaneous (steam and H/sub 2/) reaction procedure at temperatures up to 7OO deg C is being used. Particle densities ranged to 9.75g/ cc or about 89% of theoretical. Sintering in H/sub 2/ at about 1700 deg C for 2.5 hr gave final densities of 10.4 to 16.6 g/cc or up to about 96.5% of theoretical density. (auth)

Discussion of theories on particle motion in electric and magnetic fields precedes examination of theories on the source of the inner and outer Van Allen belts. Theories for the inner belt propose solar cosmic ray injection and galactic cosmic ray injection as the source of the protons. Neutron albedo is particularly examined but seems to be unaccountable for the proton belt. Neutron albedo and injection from the sun are also considered as possible sources of the electrons in the outer belt. Fluctuations, intensities, and distributions of the belts are also discussed, and the connection between the belts and aurora displays is examined. Fluxes, spectra, and particle intensities are displayed, and the effects of magnetic storms on the belts are analyzed. 150 references. (D.C.W.)

A system of six codes is described that permits the solution of a broad class of problems encountered in the study of neutron thermalization, average cross sections, and spectral models. These programs are all compatible with use on MONITOR for the IBM 7090. The Fortran listings are given. (auth)