The purpose of this production test is to provide a standard method of obtaining scram transient reactivity information at the eight reactors, under conditions conducive to valid data. These conditions include the bypassing of the Panellit system at a low power level for a short, controlled period of time during May 1959.

In 1958, planned large scale use of the new I & E slug geometry at more severe operating conditions than had been generally experienced suggested a possible compromise in reactor life and safety if a reasonable degree of rupture control with the new type of element was not maintained. The formalized slug corrosion limit (Top-of-Annulus limit) was issued as a Process Standard at the time of the full-scale loading of I & E geometry fuel elements to provide this limit for reactor operation. The loading of I & E slugs at all reactors has been accomplished and initial power level increases have been made. To date, 67 I & E ruptures have been sustained including both `hole` and `annulus` failures. The type and behavior of ruptures to be expected with I & E geometry are now characterized. Recent studies have indicated that the I & E failure experience is consistent with the general mathematical rupture model formulated from analysis of solid slug experience. Increased confidence in the use of this model in combination with Optimization Studies permits greater emphasis to be placed on the rupture model as a guide for reactor operation. It is the purpose of this report to …

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The technique of high-frequency titrimetry was applied to the determination of thorium, uranium, sulfate, and free acid. In Part I, the reproducibility of the method for the titration of standard solutions that contained 50 rag of thorium in the absence of interferences is established. Under these conditions, the coefficient of variation of the method was <1%. In Part II, the effect of uranium on the highfrequency titration of thorium, as well as the application of the method to actual samples, is discussed. Uranium in a ratio of 5 to 1 to thorium can be tolerated. When the method is applied to the analysis of representative samples, the coefficient of variation is 1%. Attempts to determine uranium by high-frequency titration with 8-quinolinol were unsuccessful. Tests on this titration and possible reasons for its failure are discussed in Part III. The application of the high-frequency titration method to the determination of sulfate in solutions of uranyl sulfate is described in Part IV. The coefficient of variation, on titrating 40 to 70 mg of sulfate with barium chloride after the uranium is masked with citrate or fluoride, is 2%. In Part V, the high-frequency titration of free acid in solutions of uranyl sulfate …

After two batches ( approximately 340 kg) of fluoride salt from the ARE were reprocessed, a pilot plant operations were terminated because of a leak through which an estimated 780 g of uranium (as UF/sub 6/ escaped. Of the 21 kg of highly enriched uranium in the feed, 93.12% was collected as UF/sub 6/ product, 0.13% represented measured losses, and 3.72% was unaccounted for (leak). An additional 3.03% was reclaimed from NaF beds and equipment washes. The produce met both chemical purity and activity specifications for product level UF/ sub 6/. Decontamination from fission products was essentially complete. A gross gamma decontamination factor was apparently limited by the low activity of the feed salt. (auth)

Volatility Pilot Plant Mark III Fluorinator is a doublechamber type vessel, each chamber 2 1/2 ft by 16 in. outside diameter separated by a 5-in. pipe 15 in. long. ASME flanged and dished heads are used for the chamber tops and conical sections with a 60 deg apex angle for the chamber bottoms. A new furnace designed to maintain the complete lower chamber (molten salt+ freeboard) above melt temperature is to eliminate past experiences of salt solidification on the wall, heads, and in or on the internal process lines. External pipe runs are autoresistance heated to allow melting and drain back of salt plugs. The upper chamber serves as a gas de-entrainment and solids precipitation device to retain most of the entrained salt and condensable fluorides in the 100 to 400 deg C range. (auth)

BS>Results of a study of thermodynamic properties of aqueous hydrochloric acid solutions are presented. A hydrogen electrode was used against a silver-silver chloride electrode at 25 to 275 deg C using hydrogen pressure of about 1 atm. and hydrochloric acid concentrations of 0.005 to 1.0 M. Electromotive measurement techniques are described and resulting data are tabulated. (J.R.D.)

The thickness of an oxide film on phosphor bronze helices was determined by first establishing the oxygen content of the helix "as received" and after cleansing with nitric acid. Based on the assumption that the difference between the two values was the oxygen in the film, and that the film consisted entirely of cupric oxide, the thickness of the film was calculated from the density of cupric oxide, weight of film, and surface area of film. A value of 1080 A was calculated as the thickness by this method. (auth)

The results of small exploding-wire studies were found to be capable of direct extrapolation to larger wires (an increase in cross-sectional area of 1500 to 1500 from the small wires). Copper wires up to 40 mils in diameter and iron wires to 62 mils in diameter were studied for use as fuses. in lengths up to 18 in. A dependency between pause time (the time between system current cut-off and current restrike) and wire length is described for several sizes of copper wires exploded with 16.5- and 49.5-kilojoule sources. The role of wire confinement is discussed in connection with establishment of the pause. (auth)

Available knowledge of precision limits in S.S. accountability measurements and/or calculations by reactor and chemical processing groups is surveyed and summarized. Experienee in comparisons of reactor (production and research) calculations vs. chemical plant accountability measurements is also reported. A general tentative conclusion is that available precisions ( plus or minus 0.54 to plus or minus 0.78%) in chemical plant measurements (bulk and analytical) for fissionable material accountability is superior to the variable precision ( plus or minus 1.0 to 1l.0%) possible by calculations (nuclear and/or engineering) of power reactor systems; however, with operation and empirical experience (e.g., after two or three core loadings), it is believed that calculations for given reactors can attain acceptable precisions, e,g., less than plus or minus 1.0%. It may be proposed that fuel payments be made as follows: 90% of fuel value based on reactor calculations, an additional 5% based on dissolver analyses, and final settlement based on chemical plant material balance (product plus loss analyses). (auth)

An elementary discussion is given of the reactor parameters which determine the signal-to-noise ratio obtainable with a pile oscillator. (auth)

Results are presented of an evaluation of nuclear safety and raaiation control related to the shipment, mechanical processing, and storage of SRE-1 fuel elements. (auth)

An experimental study was made to determine the effective shielding provided by a modern reinforced-concrete office building (AEC Headquarters building) from nuclear fall-out. Pocket ionization chambers were used for measurement of the radiation-field strength. Fall-out was simulated with distributed and point-source configurations of Co/sup 60/ and Ir/sup 192/ sources. Four typical sections were selected for study, and experiments were performed on each. These included an external wing with exposed basement walls and an external wing with a buried basement. Roof studies were made on an internal wing with a full basement and on the east end of wing A, which has a thin-roof construction. The thick-roof construction of 8 in. of concrete and 2 in. of rigid insulation covers all the building except the east end of wing A, which has 4 in. of concrete and 2 in. of insulation. (auth)

The construction and operation of the plasma injector, Toy Top, used ia the magnetic high compression experements in progess at the Lawrence Radiation Jab. at Livemore are described The essential part of the injector consists of a stack of deuterated titanium washers 3/4 in. O.D. and/2 in. I.D. Details of the construction are sbown (W.D.M.)

A general numerical procedure, called the discrete S/sub n/ method, for solving the neutron transport equation is described. The main topics relate to the derivation of suitable difference equations, and to the problem of solving these, while maintaining generality, accuracy, and reasonable computing speed. A few comparisons with other methods are made. (auth)

The burns to the skin of anesthetized rats were determined for the thermal radiation pulses of a carbon arc on a hot-wet uniform when spaced 5 mm from the skin. The radiant exposures to cause burns resulting in eschar were tion pulses corresponding to 250, 1000, 2900, and 10,000 kiloton detonations, respectively. The threshold lesions were caused by volatile products not associated with ignition. The associated temperatures were recorded. (auth)

Measurements were made of the product of surface tension (ϒ) and the contact angle (θ) of liquid plutonium vs solid tantalum and of the density of liquid plutonium (p) as functions of temperature between 655 and 960°C. The following values were obtained: ϒ cos θ = 1030 - (0.967)T d/cm and p = [17.56$sub 7$ - (1.45$sub 1$ x 10$sup -3$)T] ± 0.021 g/cm$sup 3$. A single determination was also made of the liquid density of a plutonium-7.93 atomic percent iron alloy and he following value obtained: p = [16.88 - (1.36$sub 9$)T] ± 0.012 g/cm$sup 3$.

The basic theory of operation of the triggered spark gap is established, and qualitative and quantitative engineering design data are given. From the basic twoelectrode gap, a three-electrode or triggered gap model is established with its static and dynamic triggering characteristics shown. Several geometry conditions such as gap spacings trigger electrode hole sizes and insulator effects are discussed, showing their influence upon the triggering mechanism. A suggested trigger mechanism is given based on that proposed by Sletten and Lewis for the trigatron and modified to fit the present analysis. (auth)

A method is presented for numerically determining local minima of differentiable functions of several variables. In the proeess of locating each minimum, a matrix is determined which characterizes the behavior of the function about the minimum. For a region in which thc function depends quadratically on the variables, no more than N iterations are required, where N is the number of variables. By suitable choice of starting values and without modification of the procedure, linear constraints can be imposed upon the variables. (auth)

The total K/sup +/-p cross section was measured at the three K/sup +/- meson energies 175 er inch per 25, 225 er inch per 25, and 275 er inch per 25 Mev and the differential scattering cross section was measured at 225 Mev. The K/sup +/-p nuclear force was shown to be repulsive from the observed constructive interference with Coulomb scattering. The differential c=oss section was otherwise isotropic and could arise from either pure S-wave or pure P- wave scattering. Subtracted dispersion relations were applied to these data and the rest of the available K proton scattering data. The statistical errors on the data were found to be too large to determine the K-hyperon relative parity. However, if the K DELTA and K SIGMA relative parities are assumed to be the same, then if the coupling were scalar, the coupling constant g/sup 2/4 pi would be less than 0.6; if pseudoscalar, less than 10. (auth)

The status of the Eurochemic Plant, Mol, Belgium, is summarized, and the Eurochemic organization is given. The anticipated United States assistance through June 1959 is listed. (auth)

At the present time, plants in the 100 to 500 Mw size range are more numerous and carry the greatest portion (over 50%) of the total steam-electric plant load in the US utillties industry. The contribution of plants of over 1,000-Mw capacity is increasing more rapidly than any other size classification and at present represents about 10% of the total capacity. By 1962 the TVA will have six plants with capacities of over 1,000-Mw. The largest steam-electric plant in the US is the TVA plant at Kingston, Tenn., with a nameplate capacity of 1,440Mw. Turbine-generator wits are also following a trend of ever-increasing size. In present construction, the 150 to 200 Mw size range for units ls the most common and represents the greatest contribution to capacity. Two units of 500-Mw nameplate rating each, the largest in the US, are on order by the TVA, and an 80 Mw unit is contemplated. (auth)

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Chemical control of the SM-2 was evaluated both as a partial substitute for burnable poison in the fuel element meat and as a means of improving plant performance. Based on a review of existing information, boric acid was chosen as the reference soluble poison. It was shown that 60% of the burnable B/sup 10/ in the fuel element matrix could be replaced by soluble B/sup 10/ in the coolant without impairing plant stability during load transients. The feasibility of improving power distribution and reducing the number of control rods by supplementing the burnable poison with chemical control was also demonstrated. A preliminary design of an injection and removal system was prepared for the SM-2. (auth)