Design analysis of a prepackaged nuclear power plant.

Design analysis of a prepackaged nuclear power plant.

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ABS>Published information is not available for accurate prediction of the electrical insulating characteristics of helium at high pressures and temperatures. In general the breakdown voltage increases as the gas pressure is increased and decreases as the gas temperature is increased. The relatively low breackdown voltage of helium accents the importance of additional investigation in this field. (auth)

A laboratory study of a gelatin headend process for feed from silicon- containing aluminum fuels and plant salvage solutions is described. The optimum conditions for the gelatin treatment of fuel solutions were to boil a 0.1 to 0.5N nitric acid solution with 100 milligrams of gelatin per liter for 30 minutes. This treatment improved filtration rates and decreased the surface activity of the filtrate for TBP extraction. A number of possible flowsheets for fuel solutions are presented using gelatin treatment and filtration. An adequate treatment was not found for salvage solutions of unknown composition because a gelatin dosage which was satisfactory for all solutions could not be selected. The optimum treatment for a salvage solution which was grossly contaminated with zirconium, soluble and colloidal silica, and dibutyl phosphate was to boil a 1N acid deficient solution with 600 milligrams of gelatin per liter, filter, and use a Hexone extraction system. A silicic colloid in fuel processing solutions was characterized as a surface active material by this study. (auth)

Several functions used in the calculation of x-ray crystallographic intensities are tabulated over large ranges. These tabulations include Lorentz- polarization factors as a function of Bragg angle, the Debye function as a function of THETA /T, and the Debye-Waller temperature factor as a function of B for selected sin theta / lambda values. (auth)

The equations and nomographs most frequently used intended calculating behavior of stack effluents are given and explained. (T. R. H.)

A process has been developed for converting nitricacid-insoluble uranium in ore concentrates into soluble form. Ore concentrates are treated with a reducing agent such ss carbon monoxide or hydrogen at temperatures or 670 to 730 C. In the laboratory, retention times nsoluble uranium vary inversely with the concentration or the reducing agent. Laboratory studies leading to the development of the process are reported. (auth)

Progress on various theoretical studies are reported. DC model magnet studies to determine the optimum size and position of correcting holes drilled in the magnet yoke are described The major design criteria for the ring magnet are given. The current in the magnet of the 12.5 Bev proton synchrotron was calculated. The power supply characteristics and operating conditions are described. The side coil assembly phase of the ring magnet ooil program is described. The radiofrequency system consisting of accelerating cavity, rndiofrequency program, noise-measuring systems, power amplifier, and beam inanction electrodes is discussed Detailed studies were made of the BNL Linac design and such modifications were made as are required to meet the specific needs of the ANL injector system. Two methods of fabrication of the ring magnet vacuum chamber are discussed. A preliminary study and desige was made of several vacuum pumpimg systems for the ZGS accelerator. Investigations on the vacuum properties of epaxy plastics, evapor-ion pumps, water flow control, and foundations are reported. (For preceding period see ANL-5564.) (W.D.M.)

A study was made of hydraulic characteristics of Yankee-type fuel rod assemblies using experimental and analytical methods. Two scale model fuel assemblies utilizing both ferrule and strap type arrangements were constructed and tested at atmospheric pressure and room temperature. Analytical methods using semiempirical relationships are substantiated by experimental results for both the fuel assembly having strap-type spacers and the fuel assembly having cylindrical ferruletype spacers. The experimental pressure drop across the assembly model using either straps or ferrules correlated within 5% of the value calculated by means of equations based on the equivalent diameter concept for flow inside pipes. The individual frictional drops along the rods and across the end plates and straps correlated within 15% of the predicted pressure drops. The indlvidual pressure drops across both the staggered ferrule sections and the full ferrule section correlated to within 17% of the predicted pressure drops. Comparison of the ferrule and the strap pressure drops indicates that the pressure drop across a level of straps was more than four times the pressure drop across a full ferruled section. It is concluded that the analytical methods based on the equivalent diametcr concept can be satisfactorlly used to calculate pressure drops for flow …

This annual report of Brookhaven National Laboratory describes its program and activities for the fiscal year 1958. The progress and trends of the research program are presented along with a description of the operational, service, and administrative activities of the Laboratory. The scientific and technical details of the many research and development activities are covered more fully in scientific and technical periodicals and in the quarterly scientific progress reports and other scientiflc reports of the Laboratory. A list of all publications for July 1, 1957 to June 30, 1958, is given. Status and progress are given in fields of physics, accelerator development, instrumentation, applied mathematics, chemistry, nuclear engineering, biology, and medical research. (For preceding period see BNL-462.) (W.D.M.)

Niobium was found to react linearly with air (600 to 1200 deg c) and with oxygen (400 to 1400 deg c). At 1400 deg c, a very rapid reaction with oxygen was observed. Contamination hardening during oxidation was attributed to diffusion of oxygen into the metal from the predominantly Nb/sub 2/O/sub 5/ scale. Alloying effects could be correlated with relative ionic size and valence of the alloy addition and with properties of the alloy-element oxides. Additions with smaller ionic size or higher valence improved oxidation behavior up to 15 at.% alloying. These additions included chromium, molybdenum, tungsten, and vanadium. Size effects predominated over valence effects. At alloying levels greater than 15 at.% elements having solid stable oxides, such as titanium and zirconium, improved the oxidation behavior. Elements with volatile oxides, such as molybdenum, rhenium, and vanadium decreased the oxidation resistance when added in amounts greater than 15 at. %. The most effective binary additions for improving oxidation resistance were chromium, molybdenum, titanium, and vanadium. A molybdenum-chromium alloy oxidized about 20% slower than the best binary alloy. The degree of improvement for the best alloys over unalloyed niobium ranged from a hundredfold at 600 deg c to sixfold at 1200 deg …

The possibility of measuring the electromagnetic form factor of the pion by extrapolation of the cross section for e/sup -/ + p 1100 deg C are n + The effects of /sup +/ + e/sup -/ was investigated. The method is based on the existence of a pole in the electropionproduction scattering amplitude as a function of the invariant momentum-transfer of the nucleon. The residue of this pole is the pion form factor multiplied by a known coefficient. Since the pole lies slightly outside the physical region of the invariant momentum transfer, an extrapolation of the experimental data is required. An approximate calculation of the electropion-production cross section was made in order to estimate the experimental accuracy necessary for a significant extrapolation. Accuracy is required which is an order of magnitude better than that achieved at present in similar experiments. (auth)

The reactivity changes resulting from slurry settling were computed for a number of small one-region slurry reactors using an IBM-704 routine. Calculations were performed for three temperatures, two sizes, and five initial thorium concentrations. In general, reactivity additions on settling were observed which decreased with increasing thorium inventory, increasing temperature, and decreasing diameter. For example, at l00 deg C a 2.5-ft diameter square'' cylinder (height equal to diameter) showed a maximum reactivity introduction of 4% sigma k/k with an initial concentration of 100 g Th/l and a moderator composition of 75% D/sub 2/O, 25% H/sub 2/O; at 200 deg C the maximum reactlvity introduction was 3.6%. With the same conditions, a 2-ft diameter square'' cylinder was subcritical on settling. For an initial thorium concentration of 400 g Th/l the 2.5-ft reactor showed a reactivity introduction of 1.4% at 100 deg C and 0.7% at 200 deg C. (auth)

Thc objective of the project was to determine the velocity-time and distance-time histories of anthropomorphic dummies and equivalent spheres (idealized models having an acceleration coefficient alpha equal to that of the dummy) displaced by blast winds. The dummies and spheres were located at stations within regions of about 5 and 7 psi overpressures. The technique used for recording the movement of these objects was phototriangulation. Analysis of the films obtained gave the ond shot the field of veiw was obscured by smoke (perhaps dust too) before any motion could be recorded by the cameras. In one phase of the experiment, equivalent spheres were caught in flight at near predicted maximum velocity by missile traps. The depth of sphere penetration in the calibrated capture medium was then used to compute the sphere velocity. (auth)

Dogs, pigs, rabbits, guinea pigs, and mice were exposed to nuclear detonatiors in two open underground pantitioned shelters. The shelters were of similar constructions and each was exposed to separate detonations. Each inner chamber filled through its own orifice; thus four separate pressure enviromments were obtained. An aerodynamic mound was placed over the escape hatch of each structure to determine its effect on the pressurecurve shape inside the chamber. In one test a sieve plate bolted across the top of the mound was evaluated. Wind protective baffles of solid plate and of heavy wire screen were installed in the shelters to compare primary and tertiary blast effects on dogs. The shelters also contained static and dynamic pressure gages, radiation detectors, telemetering devices, and, in one test, air-temperature measuring instruments, dustcollecting trays, and eight pigs for the biological assessment of thermal effects. One dog was severely injured from tertiary blast effects associated with a maximal dynamic pressure (Q) of 10.5 psi, and one was undamaged with a maximal Q of 2 psi. Primary blast effects resulting from peak overpressures of 30.3, 25.5, 9.5. and 4.1 psi were minimal. The mortality was 19 per cent of the mice exposed to a peak …

(((Abstract unscannable)))<><DSN>13:014503<ABS>Thc Nb-O equilibrium system was determined by metallographic examination of arc-cast alloys made ot electron-gun-refined Nb metal and special purity Nb/sub 2/O/sub 5/. Two intermediate oxides. NbO and NbO/sub 2/, melt without decomposition at 1945 C and 1915 C, respectively. Eutectic reactions exist between Nb and NbO at 1915 C and between NbO and NbO/sub 2/ at 1810 C . Experimental evidence supports a peritectic reaction between NbO/sub 2/ and Nb/sub 2/O/sub 5/ at 1510 C. The maxinium solid solubility of 0 in Nb metal is 0.72 wt.%. (auth)

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The mechanical design of and apparatus in which crossed electrostatic and electromagnetic fields are used to separate high-energy charged particies of different masses is described. The coaxial geometry of this device allows the separation in about 2/3 the space required with a parallel-plate deflector. The velocity spectrometer described was built specifically to produce enriched beams of K mesons or antiprotons, but it can be utilized in other applications by changing its parameters. The ratio of particle fluxes in a detector with the spectrometer off and on is 700 to 1. (auth)

A description of the Argonne 60-in. cyclotron along with its performance, operstional characteristics, and housimig with its associated facilities is presented. (J.E.D.)

Information concerning graphite contraction applicable to high- temperature, graphite-moderatored reactors is presented. The scope includes relevant data from all available sources, interpretation and extrapolations as can reasonably be made, and a discussion of the effects observed in terms of current radiation damage theory. Limits of accuracy and a discussion of experimental techniques are presented. (auth)

A radiological safety analysis is presented for the SNAP-III thermoelectric generator. Since the fuel of the device is polonium-210, a toxic radioisotope, certain safety measures have been designed into the device and its shipping container to prevent a release of the contaminant into any environment during normal operation or a catastrophic accident. Once containment is assured, the direct radiation problem is considered. It has been shown that the direct radiation from the thermal source is kept within tolerance limits by surrounding materials and spatial and temporal factors. It must be emphasized that this device should not be deliberately abused or mishandled since this would serve to increase the probability of accident. The device has been evaluated with respect to internal forces such as heat and helium pressure and external forces such as impact and chemical attack. The mechanical thermal and chemical integrity of the thermoelectric generator is shown to be quite reliable. The basic physical, chemical, thermal, atomic and nuclear characteristics of polonium-210 have been presented. Potential internal and external radiation hazards have been set forth. (auth)

BS>Critical concentration calculations were made for several D/sub 2/O-H/ sub 2/O moderated HRT-type reactors with 30- and 28-in. core diameters and pressure vessel diameters of 60 and 54 in. A core temperature of 300 C was assumed for all cases while the blanket temperatures assumed the values 250, 280, and 300 C. The assumed moderator compositions were 80, 90, and 100% D/sub 2/O. (auth)

UO/sub 2/, when heated in air, will transform to U/sub 3/O/sub 8/. The U/sub 3/O/sub 8/ which is formed exhibits appreciable vapor pressure at temperatures in excess of l200 deg C. The need for a stable high-temperature nuclear fuel requires prevention of the U/sub 3/O/sub 8/ transformation as well as a lowering of the vapor pressure. A method by which this may be accomplished involves compensation of the valence change of U, as it undergoes oxidation. This is accomplished by massive addition of other metal oxides. Solid-state studies of the U-La-O system were conducted in the investigation to elicit more detailed understanding of the processes involved The oxidation and vaporization characteristics of UO/sub 2/ were compared directly to solid solutions of U0/sub 2/ containing from 30 to 60 wt. % of La/sub 2/O/sub 3/. These solid solutions. which have the fluorite structure, were formed by reacting U0/sub 2/ and La/sub2/ O/sub3/ in vacuo. When these materials were oxidized the fluorite structure was retained with, however, reduced lattice parameters. These were shown to be equivalent to reacting U/sub 3/O/sub 8/ with La/sub 2/O/sub 3/. The volatility of the resultin g solid solutions was found to vary with the amount of additive. …