The experimental results on the oxidation of H from a He stream with CuO pellets were very close to the predicted behavior based on the mathematical model. Experimental measurements of uranyl sulfate loading rates on chloride equilibrated resin showed little variation with solution concentrations. A tentative flowsbeet was proposed for cost analysis of processing a Pebble Bed Reactor. A U-Zr plate was dissolved in nitrate-free Zirflex solution. An authentic TRIGA prototype was processed in engineering-scale equipment. Three 4- stage leacher model dissolution runs were made, two of which used 8 M HNO/sub 3/ and one used 4 M HNO/sub 3/. Flooding rates and holdup data were obtained for sieve plate pulse columns under 5% TBP - l.8 Mi Al(NO/sub 3/)/sub 3/ flowsheet conditions. A Purex waste calcination run (R-37) was made using sodium anid imagnesium to reduce sulfate volatility. (auth)

Tests were performed to obtain station performance data at various steady-state generator loads. The station 0 was operated for four-hour periods at steady state conditions and levels of 5, 21, 42, and 61 Mw gross generator output. The various readings are presented in tabular form. A list is given of equipment in service during the test. All plant components operated satisfactorily during the test. (M.C.G.)

Information is presented in tabular form on the contributions of the individual resonances to the resonance integrals in U and Th. The cases considered are for isolated cylindrical rods and involve U/sup 238/, U/sup 238/O/ sub 2/, Th/ sup 232/, and Th/sup 232/O/sub 2/ (M.C.G.)

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In the Plant Improvement Program, it is proposed to retube the K-Reactors with standard size Zircaloy-2 smooth-bore process tubes and to charge self supported fuel elements starting March 15, 1964. The first step in support of this transition program is to confirm compatibility of the fuel-tube geometry and secondly to obtain fuel-tube performance information prior to full scale commitment of the K-Reactors to this design. In view of the testing of self-supported fuel which has been accomplished to date and that which is planned, there is little incentive to install more tubes in a K-Reactor than are required to make the fuel-tube geometry check. To accomplish this, ten tubes are viewed as the maximum number that would be required. This report presents the design of a test to fabricate and irradiate ``K`` self-supported fuel elements in limited quantities.

This report contains an analysis of PCCF tube flow and Panellit pressure relations at DR reactor. Supply curves are presented at front header pressures from 480 to 600 psig using cold water and the standard 0.236 inch orifice with taper down stream and the pigtail valve (plug or ball) open. Demand curves are presented for slug column lengths of 200 inches to 400 inches using 1.44 inch O.D. solid poison pieces (either Al or Pb-Cd) and cold water with a rear header pressure of 50 psig. Figure 1 is a graph of Panellit pressure vs. flow with the above supply and demand curves and clearly shows the effect of front header pressure and charge length on flow.

This report discusses the delayed neutron characteristics of a reactor which are a function of the distribution of fissions in the various fissionable isotopes. The delayed neutron characteristics of the NPRL delayed fraction and decay constants, are presented as functions of exposure to 2000 MWD/T for both room temperature and operating temperature. It is of importance to note that the delayed neutron fraction decreases from 0.693% to 0.539% with increased exposure. Thus 22% less reactivity change represents a prompt critical condition at 2000 MWD/T, compared to the zero exposure condition.

The KSE-3 element, a 1.6% enriched Zr-2 Jacketed tubular element nominally 1.74 inch O.D. by 1.05 inch I.D., was designed for irradiation in the KER loops to simulate the behavior of an N-reactor outer fuel tube. Three charges of these fuel elements have been irradiated under PT-IP-363-A: one in KER-2 to 1985 MWD/T, one KER-3 to 3555 MWD/T, and one in KER-4 to 1.195 MWD/T. This document provides the calculated powers and temperatures for each fuel element during the time it was irradiated.

The high temperature enthalpies of five rare earths were measured from 0 to 1100 deg C using a Bunsen ice calorimeter. The enthalpy of yttrium metal was studied from 1100 to 1675 deg C using a modified high temperature vacuum Bunsen calorimeter. The data were fitted to empirical equations from which the heat of transition and fusion, the heat capacity, and the related thermodynamic quantities were calculated. These results confirmed indications from other properties that europium and ytterbium metals are primarily in the divalert state. Small anomalies observed in europium and ytterbium were attributed to transitions between electronic states when some trivalent ions occur in these metals. The ertropy of the fcc-bcc transition for ytterbium was found to be approximately two- thirds that of the other rare-earth metals for which a close-packed to bodycertered cubic transformation was observed. (auth)

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Bare and zirconium-clad uranium-10 wt% molybdenum specimens were irradiated in NaK-filled capsules in the MTR. Irradiation conditions varied to include central-core temperatures ranging from 300 to over 1200 deg F, fuel burnups ranging from 0.36 to over 3.0 total at.% and fission rates in the range of 0.35 to 1.9 x 10/sup 14/ fissions/(sec)(cm/sup 3/) of alloy. Other parameters studied included the effects of heat treatment, changes in composition, different fabrication techniques, and changes in cladding thickness on the behavior of the fuel alloy. The objective of the irradiations was to determine the behavior of the fuel alloy under conditions approaching as closely as possible those to be encountered in the Enrico Fermi Atomic Power Plant as they were known at the time. The results indicated that the volume of the fuel alloy would increase conservatively at a rate of about 3.0% per at.% burnup as long as the critical temperature of 1000 to 1100 deg F was not exceeded and the gamma phase of the alloy did not transform during irradiation. If the critical temperature was exceeded, the alloy swelled until rupture or complete disintegration occurred. The occurrence of transformation during irradiation was noted at burnups in the range …

The voltage and frequency response of selected SM-1 plant system parameters to step load changes was analyzed using analog computer measurements. The analog model was that developed for analysis of the SM-2 design. The approach to the analysis, formulation of the model, and analog recordings are presented. The data will be used to prove reliability of the analog model by comparing analog data with test data to be taken at SM-1. (auth)

An experimental investigation of the interdiffusion and forced-flow behavior of helium and argon in Speer Moderator No. 1 graphite was performed. The data were employed to determine a mutual diffusion coefficient and to verify certain superposed-flow equations. In addition, two series of experiments at high values of the forced-flow component were conducted to investigate contributions of the backdiffusion mechanism of those pores whose diameters are equal to or smaller than the mean free path of the gas molecules, approaching Rhudsen or free-molecule difiusion. At small forced-flow rates, normal diffusion was the controlling diffusion mechanism, while Knudsen effects were negligible. Flow equations employed previously are applicable to these data. Experiments conducted at high forced-flow rates show the contribution of small channels, which appears to follow the Knudsen diffusion mechanism. A critical value of sweep rate was determined. If the sweep rate is lower than the critical, the contamination will increase, whereas sweep rates greater than this would require large reprocessing capacities without additional decrease in contamination. (auth)

ALGOL 60 is a universal, algebraic, machine-independent programming language. It was designed by a group representing computer societies from many different countries. Its primary aims are: (1) simplification of program preparation, (2) simplification of program exchange, and (3) incorporation of the important programming techniques presently known. An elaboration of the concepts of ALGOL 60 is given, mostly with the help of illustrative examples. (auth)

Neutron losses to Pa/sup 2//sup 3//sup 3/ in the blanket of the AHBR were computed and compared for two cases: (1) concentration of Pa/sup 2//sup 3// sup 3/ is maintained uniform by continuous mixing, and (2) batches of fertile material are shifted periodically from high- to low-flux regions of blanket. It was found that, if the fertile material is cycled through three radial positions in three days, the loss of neutrons to Pa/sup 2//sup 3//sup 3/ is no more than one per cent greater than if it is mixed continuously. (auth)

Uranium ore concentrates from seventeen world sources were compared to a standard to determine variations in isotopic content. A spread of about 0.06% in U/sup 235/ content was indicated for the concentrates analyzed. Domestic sources showed much wider variations than those from other parts of the world. (auth)

BS>The approach taken in measurements on the AGS experimental magnets is discussed, and results of various measurements are examined. Application of information to calibration of beam lenses is also mentioned. Graphs of several magnet properties are included. (D.C.W.)