A mathematical analysis is presented concerning the performance of the radial or vane type steam separator. The analyses are concerned with the spread of flow on the vanes because of centrifugal force (which requires that the vane height be greater than the nozzle), and with separation of the vapor from the liquid. (J.R.D.)

From abstract: "A single focusing mass spectrometer has been converted into a double focusing instrument. Relatively high resolution is obtained by decreasing the slit widths and minimizing the ion-optic aberrations. A relatively low ion accelerating voltage (2000 volts) is utilized compared to those normally used for high resolution work. The entire construction was performed at these laboratories. Essentially all of the original equipment was reused in the double focusing system. Although the original source slit was decreased from 10 to 0.4 mils and the source α value was decreased from 0.04 to 0.008 radians, sufficient sensitivity is obtained for quantitative gas analysis with the ordinary electrometer tube amplifiers utilizing 4 x 10[^]10 ohms input grid resistors and 100 per cent inverse feedback. Carbon monoxide-nitrogen mixtures were analyzed quantitatively. The results indicate that direct quantitative analysis can be obtained on mixtures ranging from 99 per cent to 10 per cent carbon monoxide in nitrogen. Analysis of lower percentages may be made possible through indirect reading of the peak should it be necessary. It appears that the instrument should be adaptable to research problems concerning these two gases. The immediate problem posed is the analysis of oxygen and nitrogen in metals. Other …

Summary report of final hazards for the Boiling Nuclear Superheater (BONUS) Power Station with illustrations.

Report discussing state of the art design and operation of heat transfer and hydraulics equipment and technology in boiling water reactor power plants.

>Information on heat transfer and hydraulics pertinent to the design and operation of boiling water reactor power plants is presented. The following areas of discussion are covered: heat transfer, two-phase density studies, twophase pressure drop, critical heat flux and burnout, boiling stability, calculation procedures for boiling systems, and thermal-hydraulic design procedures for boiling water reactors. (M.C.G.)

Single phase, solid solution, UC-PuC powder was synthesized reproducibly from a mixture of the oxides and carbon. A simple method of monitoring the reaction was developed. UC-PuC-0.1 wt% Ni pellets of 93% theoretical density were made reproducibly, with some samples as high as 95% of theoretical denstty. The pellets contain minor amounts of (U,Pu)/sub 2/C/sub 3/ most of the time. Efforts to make reproducible 95%, single-phase material are under way. Microprobe analysis of UC-0.1 wt% Ni specimens was completed. A second phase apparently promoted by the nickel was shown to be probably U/sub 2/C/sub 3/. Essentially all the nickel was found in solution in the matrix UC. The postirradiation examination of the UC specimens completed to date showed that the UC pellets had the same appearance after irradiation as before irradiation. Their dimensional changes were very slight (1.4% volume increase). Fission gas release was low and within the sensitivity of the initial measurement (3.5% max). The average specimen burnup was 18,500 MW-d/tonne at an average maximum fuel temperature of 760 deg C (1400 deg F). The plutonium facilities continued satisfactory operation at zero contamination level. (auth)

Cs-137 has been chosen as a possible index of the plutonium and uranium in coating waste. This index is a stable ratio as long as the plutonium formation rate (Pu/MD) is stable. Calculations are presented for Purex and Redox. It is recommended that the Cs-137 index method be used for determining nuclear materials content in coating waste at both Purex and Redox; this will result in higher but more accurate statements of Pu, U losses in coating waste.

The chemical and industrial literature and laboratory work concerned with processing of niobium-containing nuclear fuels are reviewed. 57 references. (auth)

Technical report giving an overview of the use of nuclear energy to produce chemicals including a rough estimate of the economic potential.

Activities in a phase of CANDU I refueling machine development are reported which are concerned with obtaining test data for various system subcomponent parts. The basis for selecting those units requiring test was established through engineering evaluation of available information. Results of tests based on these requirements are included in the form of test reports. (J.R.D.)

The use of continuous solvent extraction was proved quite satisfactory in separating Y/sup 91/ from Pm/sup 147/, using synthetic mixtures of the nuclide pair on a tracer level. The separation was conducted in a compound perforated plate pulse column using a solvent containing 10% HDEHP, di(2 ethylhexyl) phosphoric acid, in toluene. Flow rates to the extraction column were maintained around 1 ml/min of feed, 3 ml/min scrub and 12 ml/min solvent giving one volume change per hour. Pulse frequency was maintained at 50 cycles/min and pulse amplitude at 1 cm. Varying Pm: Y ratio (by activity) in the feed from 0.08 to 135, and using the above conditions, Pm in excess of 99% and Y in excess of 97% purity were obtained. The steady state condition was reached in 12 hours, or l2 volume changes. The approach to steady state was found to be the same for any one component in all runs conducted. However, this approach was much slower than that predicted by calculations reported in the literature for discrete stages. (auth)

Monthly newsletter of the High Plains Underground Water Conservation District No. 1, discussing the field of underground water. Topics include profiles of water conservation research, annual pre-plant soil moisture survey data, annual Winter Water Level measurement data, and information about the latest water conservation tips.

A record is presented of radiation contamination levels observed in the work area during the Core I Seed 2-Seed 3 refueling operations. The radiation levels for Seed 2-3 refueling were somewhat higher thand those for Seed 1-2 refueling in certain areas and are ascribed to operations being carried out under dry conditions. Maximum contamination levels were also higher, but the general contamination level was lower. The activity of canal water was higher and characterization was made on some of the canal water samples. (D.L.C.)

The work of the second year to produce ductile beryllium composites by liquid-phase sintering is reported. Ductility in a predominantly beryllium composite was sought through the attainment of a structure in which beryllium particles are enveloped in a ductile metallic matrix. As the result of the investigation of aluminum-silver binary al!oys, aluminum-40 to 50% silver compositions were added to the silver-5 to 8% aluminum compositions as candidate matrices satisfying the requirenent that the flow stress of the matrix be matched to that of the principal phase. Composites produced for final evaluation contained defects originating from the processing schedule. The feasibility of applying liquid- phase sintering to produce beryllium composites has been established. However, in order to obtain a fair evaluation of the question of ductility improvement, it is necessary to develop compacting and sintering procedures which will yield sound material for mechanical testing.

Development work leading to comparison of co-precipitated and mechanically blended UO/sub 2/-- PuO/sub 2? powders is reported in which special emphasis was placed on blending trials, pellet sintering studies, and subsequent evaluation of pellets made with blended material. Homogeneity studies indicate that currently used procedures are unsatisfactory because particle buildup occurs during blending. Powder preparation via the oxalate route was continued along with PuO/sub 2/ moisture pickup studies. Homogeneous precipitation studies on UO/ sub 2/ were continued to determine feasibility of direct preparation of dense UO/ sub 2/-- PuO/sub 2/ feed materials. Plasma-torch-produced PuO/sub 2/ spheres are being evaluated. (J.R.D.)

The distorted-wave theory of direct nuclear reactions is presented in a unified manner, in which the effects of assuming various reaction mechanisms and nuclear models appear only in certain radial form factors. The zero-range approximation is used, and spin-orbit coupling is neglected in the distorted waves. Formulas are given for transition amplitudes, cross sections, and polarizations. A description is given of the IBM-704 computer code SALLY that is based on these formulas. (auth)

Conditions leading to thermal instability in air-cooled channels are mathematically expressed. It is shown that thermal instability occurs only if the air temperature approaches the graphite temperature. The length of channel necessary to yield a particular air temperature is derived. The effects of enhanced reactivities on the instability conditions are discussed. (R.J.S.)

The efficiency of multiple traversal targets is defined as the probability that a proton dies by making a nuclear collision in the target rather than by hitting the limit of the synchrotron aperture. The efficiencies of Be, Al, Cu, and Pb targets are shown for 15 and 30-Bev protons in the Brooknaven AGS. Beryllium was found to be the most efficient. (M.C.G.)

Compacted UO/sub 2/ powder specimens with purposely defected stainless steel cladding were erosion flow tested under simulated boiling-water reactor operating conditions, excluding neutron flux. The type of clad defects were 0.026inch wide slits, completely through the clad, varying in length from 0.25 to 1 inch. Maximum erosion flow test exposure was 6000 hours in 7 ft/sec, 536 deg F flowing water. The results of post test examination indicated that defected stainiess-clad swaged fuel with UO/sub 2/ densities greater than 90% T.D. is comparable to pellet type fuel with respect to erosion resistance. Within the test parameters, the stresses and imperfections introduced into the stainless cladding as a result of swaging did not adversely affect the corrosion characteristics of stainless steel in a boiling water reactor coolant environment. As a result of the test data, two swaged fuel rods containing 0.50-inch long slits were inserted into the VBWR reactor. The defected rods are performing satisfactorily after accumulating 1000 Mwd/t exposure, with activity due to fission gas release below 20 mu c/sec. (auth)

Six groups of U-2 wt% Zr fuel slugs were irradiated in the first core of the EBR-I to burnups of 0.080 to 0.189 at.% at calculated temperatures of 307 to 353 deg C. Two groups of cast specimens were found to be more dimensionally stable than four groups of wrought slugs. Of the wrought slungs, the as quenched group showed less tendency to grow than the three groups which had some annealing after quenching. Specimens at burnups of about 0.189 at.% and at 383 deg C showed the onset of swelling as indicated by density measurements. The hardnesses of these specimens seemed but little affected by radiation, but there was an indication of softening with increasing irradiation temperature. (auth)

Technical report. From Abstract : "Arc-fused UO2 was vibrationally compacted to as high as 93.4% of theoretical density inside a stainless steel sheath tube. Selected particle sizes were used, and the assembly was vibrated axially in the frequency range of 300 to 1500 cycles per second. The same blend of UO2 particle sizes was vibrationally compacted to 87.5% of theoretical density within the annulus between two concentric stainless steel sheath tubes. The effects of particle size distribution, vibrational compaction procedure, sheath thickness, and fuel element shape on the maximum obtainable density were investigated."

From introduction: A prototype Strontium-90 fueled generator will be used to fulfill the power requirements of an unattended automatic light buoy...Primary objectives are to provide continuous absolute containment of the radiostrontium fuel...and biological shielding of the direct radiation from the heat source.

Declassified 26 Nov 1973.<><DSN>29:020150<ABS>has resulted from a sophisticated consideration of its application as a ramjet engine. An idealized reactor power profile was derived directed toward optimizing the transfer of heat energy to the airstream. Some twenty-six classes of fueled tubes have been used to tailor both axial and radial reactor power profiles accordingly. Procedures for the fabrication of components and assembly of the reactor have consequently become tedious and lengthy to safe-guard agalnst errors. The calculations presented were done to estimate the price, in terms of engine performance, of one simplification in design. At present the Tory II-C reactor has an axial fuel loading pattern with concentrations decreasing in six steps. The simplification considered is the removal of this axial variation while preserving the radial power profile. Neutronics calculations were done with the Angie code to find the resulting power profile. This in turn provided the input for the reactor performance code DASH N. (auth)

This report investigates the "formation of hydrazine from the cobalt-60 gamma radiolysis of ammonia in the presence of mineral solids"--from abstract.