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This report, from the 300 area of the Hanford Plant, May 31, 1956, describes problems and operation of a vacuum system and associated equipment.

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Many rivers are burdened with tributary streams of warm water and/or liquid wastes containing dissolved or suspended matter. The warm water and waste matter mix thoroughly with the river water some distance downstream from the point of entry of the tributary, but near the point of entry there may be high local temperatures or concentrations of waste. It is often necessary to know the local temperatures or concentrations of waste. The authors have used a formula for computing the turbulent mixing that takes place in such a situation; this formula fits quite well in the case of one Southern river.

Object of this paper is to present preliminary results of experiments in Hanford in-reactor loops to determine if exposure to neutrons will increase corrosion rates of Al alloys, Zy-2, and 304 stainless steel. Results were negligible or no corrosion.

During April 1962, equipment in both the main Redox Building (202-S) and the Plutonium Concentration Building (233-S) vas rearranged to allow the accumulation and recovery of neptunium without interference with the production of uranium and plutonium. In order to do this, the former rework column (1S) was put into continuous service as a neptunium recovery column, the Third Plutonium Cycle was converted to a neptunium decontamination cycle, and ion-exchange equipment was installed in the 233-S Building to replace the Third Plutonium Cycle. The neptunium, once decontaminated, will be concentrated and loaded out via its own system in the 233-S Building. To check the critical mass safety of the new arrangement, a formal hazards review was made, the results of which are reported in this document.

Two models of a liquid-hydrogen (?-illegible) Cherenkov counter (illegible) been constructed (illegible). The first served as a prototype (?-illegible) and was (illegible) to demonstrate the feasibility (?-illegible) of the (illegible) concept (?-illegible) (illegible) liquid hydrogen does not give scintillation (?-illegible) (illegible) that of Cherenkov light. The second, final version (?-illegible), (illegible) in an experiment (?-illegible) in which particles brought to rest (?-illegible) (illegible) (illegible) electrons. In this second counter, the efficiency (?-illegible) (illegible) relativistic (?-illegible) particles (?-illegible) by their Cherenkov radiation in liquid hydrogen (?-illegible) was measured by stopping (illegible) mesons in the hydrogen and detecting their decay electrons outside (?-illegible) of the flask (?-illegible) after a suitable time delay. An average detection (?-illegible) efficiency (?-illegible) of 75% (?-illegible) was (illegible) taken over the volume of the hydrogen (?-illegible).

This report itemizes the irradiations performed by Testing and Irradiation Services for Battelle-Northwest. It lists the material being irradiated, awaiting disposition and material shipped during the report period during May 1968.

This document provides the general instructions for performing acceptance Test Number Four as indicated in the Acceptance Test Index (TI-022-130-003). Also indicated are the plant conditions and special equipment required to conduct the test. The acceptance criteria for each portion of the test are specified.

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A computerized mathematical model for anion exchange processing of plutonium(IV) was adopted from a previously written code. The model was verified to predict, within +-30 percent, a profile of plutonium breakthrough for the sorption process on Dowex 1-X4 anion exchange resin. The program was modified to incorporate column washing and elution logic. Experimental washing and elution data were in satisfactory agreement with predicted data. Provisions for changing the flow rate during the course of a run and for plotting capabilities to aid in better presentation of column breakthrough curves also were incorporated into the model.

The work included in this Interim Summary Report is part of the Electric Car Program, the goal of which is to develop by 1979 a totally new electric car with substantially improved performance over those electric cars available in 1976. The rationale used in designing a four-passenger electric car for use in an urban environment is presented. The approach taken was to design an electric car utilizing current technology. On the basis of tradeoff analyses, upgrading improvements were identified which would permit the electric car to more nearly meet all of the ERDA near-term goals. The electric car design, including the chassis, drive train, major components, and the control are summarized. The Phase I electric car design will meet many of the ERDA near-term goals. Upgrading development programs are identified which, when incorporated in Phase II vehicle development, will result in upgraded performance, which essentially meets ERDA's near-term goals.

An overall summary is presented giving the radioactive liquid wastes discharged to ground during 1976 and since startup (for both total and decayed depositions) within the Production and Waste Management Division control zone (200 Area plateau). Overall summaries are also presented for 200 East Area and for 200 West Area. The data contain an estimate of the radioactivity discharged to individual ponds, cribs and specific retention sites within the Production and Waste Management Division during 1976 and from startup through December 31, 1976; an estimate of the decayed activities from startup through 1976; the location and reference drawings of each disposal site; and the usage dates of each disposal site. The estimates for the radioactivity discharged and for decayed activities dicharged from startup through December 31, 1976 are based upon Item 4 of the Bibliography. The volume of liquid discharged to the ponds also includes major nonradioactive streams. The wastes discharged during 1976 to each active disposal site are detailed on a month-to-month basis, along with the monthly maximum concentration and average concentration data. An estimate of the radioactivity discharged to each active site along with the remaining decayed activities is given.

The warm plasma from a deuterium-loaded titanium washer gun, streaming along magnetic-field lines through the steady-state magnetic well of Baseball II, has been examined for its suitability in this experimental situation as a target plasma for hot-ion buildup experiments and for microinstability control. The gun was positioned near the magnetic axis outside the mirror region. Measurements were made with gridded, end-loss detectors placed outside the opposite mirror, a microwave interferometer, a beam-attenuation detector, and other diagnostics.

The first system proposed for test in the LOFT facility is a pressurized water reactor system, designed to operate continuously for up to 1600 effective full power hours at 50 MWt. Because of the experimental nature of the plant and its relatively short life, utilization of the reactor heat for power generation is not practical. Consequently, it is necessary to provide a secondary heat removal system capable of continuously removing up to 170 x 10/sup 6/ Btu/hr (50 MWt) from the primary coolant system and dissipating this heat to the atmosphere. In the LOFT Conceptual Design, IDO-16833 (Revision I), a heat removal system was proposed in which liquid ''Dowtherm A'' is circulated in a closed secondary loop between the primary heat exchanger and shell-and-tube secondary heat exchangers; in the latter the heat is in turn transferred to a tertiary system in which treated water is circulated between the secondary heat exchangers and an induced draft cooling tower. In response to a KE recommendation that certain alternate heat removal systems might result in cost savings or improved operation, the Idaho Operations Office, USAEC, authorized an engineering and economic study comparing the Dowtherm system described above with a secondary system in which …

This LTR contains the original results of the Railroad Locomotive Tractive Effort Test performed by Kaiser Engineers on July 29, 1965, using an existing 24-wheel 500-ton dolly and the existing shielded locomotive. The test was conducted to confirm calculations of the tractive effort required to move the LOFT dolly (MTA) through the four-rail high bay curve and the curve into the LOFT containment vessel.

The current status of the capability of laser fusion diagnostics is reviewed. Optical and infrared streak cameras provide one time resolution measurement capability of less than 10 ps, while x-ray streak cameras provide 15 ps time resolution in the range of about 1--30 keV presently. Time integrated spatial resolutions of 1 ..mu..m are provided with a variety of optical techniques. Ultraviolet holographic interferometry has measured electron densities above 10/sup 21/ cm/sup -3/ with 1 ..mu..m spatial resolution and 15 ps temporal resolution. X-ray microscopes provide 3 ..mu..m time integrated resolution and the x-ray streak pinhole camera has 6 ..mu..m spatial resolution. Development of the framing camera has thus far provided 50 ..mu..m spatial resolution with 125 ps frame duration and the third order reconstruction of zone plate images has provided 3 ..mu..m resolutions for alpha particles. Time integrated measurements of x-rays span the range shown. Finally, the new Shiva neutron spectrometer increases the energy resolution capability of that technique to 25 keV for 14-MeV neutrons. These combined capabilities provide a unique set of diagnostics for the detailed measurement of the interaction of laser light with targets and a subsequent performance of those targets.

The document discusses the rationale used in selecting the following Secondary Coolant System design parameters: (1) pressure, (2) temperature, (3) heat removal, and (4) system flow rates.

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The STORET/MSP option was used to obtain county aggregated information on ambient water quality for sixty parameters during the period 1950 to 1978. Masks, extended EXTRACT specifications and bounds on allowable values limited inclusion of erroneous data. Remark codes were required to aggregate STORET parameters to obtain increased numbers of observations. Numerous statistical analyses led to the conclusions that medians were more useful than means, that trimming on number of observations was required to eliminate counties with extreme values, and that many parameters required logarithmic transformation to be useful in regional analyses. County aggregated data for nineteen water quality parameters were examined in terms of their ability to describe qualitative chemical characteristics of water. Anion--cation balances as well as expected relationships between conductivity and other parameters were correctly accounted for. Factor analysis indicated the existence of three principal components describing patterns between metal ions, non-metal ions, and alkalinity-bicarbonate, respectively. These factors were used in place of the original complete set of water quality parameters in a structural equation approach describing relationships between variables of mans activites. It was found that counties with high industrial electric consumption, farming and mineral shipments tended to have increased levels of most water quality parameters. …

Measurements of n/sub 2/ for a large class of oxide and fluoride crystals and glasses have been made using 100-ps, 1.06-..mu..m laser pulses and time-resolved interferometry. Values of n/sub 2/ for various glasses are summarized.

Two procedures for the separation of Np are presented; the first involves separation of /sup 239/Np from irradiated /sup 238/U, and the second involves separation of /sup 237/Np from a solution representing that from a dissolved fuel element.

Our survey was limited to ICF programs in the United States. It included researchers in laser and heavy ion fusion, target design, target diagnostics, and conceptual reactor design. We asked each of these people to read the current data needs for magnetic fusion energy and to comment on additional data that they require.

A study was made of the properties of metal hydrides which may be suitable for use in chromatographic separation of hydrogen isotopes. Sixty-five alloys were measured, with the best having a hydrogen-deuterium separation factor of 1.35 at 60/sup 0/C. Chromatographic columns using these alloys produced deuterium enrichments of up to 3.6 in a single pass, using natural abundance hydrogen as starting material. 25 references, 16 figures, 4 tables.