The energy conservation program undertaken by ARHCO to reduce energy consumption in the operation of the fuels reprocessing and waste management facilities on the Hanford reservation is described. This program includes fuel conservation for transportation equipment at the facilities, minimizing power requirements for lighting and air conditioning buildings, and reducing the energy demands of the processes used. (LCL)

Progress was reported on adsorption work in experimental, theoretical and field projects. The reinjection task is now nearing completion of the work on optimizing injection into the Palinpinon geothermal field in the Philippines. Well test analysis research has been expanded with the initiation of a new project on multiwell interference test interpretation.

The formation of negative ions by hydrogen collisions on cesium-coated surfaces is discussed in the limiting cases where the resident cesium is either in the purely ionic state or in the purely atomic state. The survival fraction for negative ions moving away from a metal surface is calculated using a method employing complex eigenvalues. The fraction of surviving ions is found to be larger than calculated by previous workers. The secondary emission coefficient for negative ion production by incident atoms with energies of ten to one hundred electron volts is estimated to be in the range thirty to forty percent.

Design data, safety features, and site characteristics are summarized for 12 nuclear power units in 6 power stations in the United States. Six pages of data are presented for each station, consisting of thermal-hydraulic and nuclear factors, containment features, emergency-core-cooling systems, site features, circulating water system data, and miscellaneous factors. In addition, an aerial perspective is presented for each plant. This volume covers plants with docket numbers 50-553 through 50-569 (Phipps Bend, Black Fox, Yellow Creek, and NEP) and two earlier plants not previously reported--Hope Creek (50-354, 50-355) and WPPSS 1 and 4 (50-460, 50-513). Indexes for this volume and the five earlier volumes are presented in three forms--by docket number, by plant name, and by participating utility.

A sample of titanium metal powder QC 1779 was subjected to five different treatments of dyring and moisture exposure to estimate the effectiveness of normal drying and handling procedures used in the pyrotechnics processing. The treatments were drying in air, drying in two different vacuum furnaces, exposure to normal humidity, and exposure to 100 percent humidity. Statistical evaluation of the NMR results indicates that there is a significant difference between the moisture content of each treatment. Although the combined effects of temperature, pressure, humidity, and treatment time were not studied in a designed manner to determine their significance on the effectiveness of the drying techniques and moisture uptake by sample QC 1779, the experimental evidence does indicate that all four variables do affect the results of the treatments. 2 figures, 6 tables.

A computer program entitled ''WELLFLOW'' is presented for calculating wellhead flow and fluid conditions for a self-flowing geothermal well of constant diameter. The calculational model was developed by Elliott and has been modified to incorporate a more accurate analytical procedure for calculating brine thermophysical properties. An additional modification establishes the mass flow rate needed to just produce sonic liquid velocity at the wellhead (if the specified flow rate exceeds this value) in order to characterize the entire range of flow conditions for the well geometry and reservoir characteristics. Reservoir values of temperature, depth, salinity, mass flow rate and drawdown pressure factor must be specified. Wellbore parameters of casing inside diameter, Moody friction factor, gas/liquid velocity ratio and the overall heat transfer coefficient between the casing and ground must also be supplied. The calculated wellhead conditions consist of temperature, pressure, vapor mass fraction, enthalpy and entropy of the two-phase mixture, liquid velocity and vapor and liquid mass flow rates for either pure water or brine.

In experiments like the spheromak, it becomes interesting to investigate the quality o f the magnetic flux surfaces in the device. One method of doing so is to impose an external perturbation. If the magnetic field without perturbation is tangled and no flux surfaces exist, then the perturbation will have little effect. However, if the field has well defined flux surfaces, the field should react strongly to a perturbation. Magnetic islands should form and potentially cause a degradation of the plasma This paper will assume the second case of good behavior and closed surfaces and will attempt to describe the effects of an external perturbation. Geometry-wise, we begin with the infinite cylinder approximation to a toroidally confined plasma. In the unperturbed state of this cylinder there are a toroidal field (axial field in the cylindrical geometry), a poloidal field and no radial field.

Lawrence Livermore National Laboratory (LLNL) was tasked under project number D103401 to acquire computed tomographic (CT) images of selected components supplied by Y-12 National Security Complex personnel. A total of four components were imaged utilizing CT. In addition, LLNL personnel provided a basic review of the CT data acquisition and CT capabilities at LLNL to four Y-12 personnel. This report identifies the equipment used to acquire the CT images on each of the four components. It also provides representative sample CT images from each of the four components. Additional imaging data along with image display software will be forwarded under separate cover.

CH2M HILL Hanford Group, Inc. is identifying and developing supplemental process technologies to accelerate the Hanford tank waste cleanup mission. Bulk vitrification, containerized grout, and steam reforming are three technologies under consideration for treatment of the radioactive saltcake wastes in 68 single-shell tanks. To support development and testing of these technologies, Pacific Northwest National Laboratory (PNNL) was tasked with developing a cold dissolved saltcake simulant formulation to be representative of an actual saltcake waste stream, preparing 25- and 100-L batches of the simulant, and analyzing the composition of the batches to ensure conformance to formulation targets. Lacking a defined composition for dissolved actual saltcake waste, PNNL used available tank waste composition information and an equilibrium chemistry model (Environmental Simulation Program [ESP{trademark}]) to predict the concentrations of analytes in solution. Observations of insoluble solids in initial laboratory preparations for the model-predicted formulation prompted reductions in the concentration of phosphate and silicon in the final simulant formulation. The analytical results for the 25- and 100-L simulant batches, prepared by an outside vendor to PNNL specifications, agree within the expected measurement accuracy ({approx}10%) of the target concentrations and are highly consistent for replicate measurements, with a few minor exceptions. In parallel with the …

The high-level radioactive wastes in many single-shell tanks (SSTs) at the Hanford Site are to be retrieved by a modified sluicing method. Retrieval operations will hydraulically erode and dissolve the saltcake waste, and the resulting brine will then be pumped to a double-shell tank (DST). Waste gases residing in the solid waste matrix will be released into the tank headspace when the matrix is eroded or dissolved. These retained waste gases include the flammable species hydrogen, methane, and ammonia, and there is a concern that these flammable gases could produce a flammable mixture in the tank headspaces during the retrieval operations. This report combines conservative retained gas inventory estimates and tank data with anticipated waste retrieval rates to estimate the potential headspace flammability of selected SSTs during waste retrieval operations. The SSTs considered here are ten of the twelve 241-S farm tanks (tanks 241-S-107 and 241-S-111 are excluded from consideration here) and tank 241-U-107 (U-107).

Various reducing agents were used and their additions were varied to (1) increase glass quality through eliminating defects from silica scum, (2) decrease SOx emissions through changing the kind and quantity of reducing agents, and (3) improve production efficiency through increased flexibility of glass redox control during continuous processing. The work included measuring silica sand dissolution and sulfate decomposition in melts from glass batches. Glass batches were heated at a temperature-increase rate deemed similar to that experienced in the melting furnace. The sulfate decomposition kinetics was investigated with thermogravimetric analysis-differential thermal analysis and evolved gas analysis. Sulfur concentrations in glasses quenched at different temperatures were determined using X-ray fluorescence spectroscopy. The distribution of residual sand (that which was not dissolved during the initial batch reactions) in the glass was obtained as a function of temperature with optical microscopy in thin-sections of melts. The fraction of undissolved sand was measured with X-ray diffraction. The results of the present study helped Visteon Inc. reduce the energy consumption and establish the batch containing 0.118 mass% of graphite as the best candidate for Visteon glass production. The improved glass batch has a lower potential for silica scum formation and for brown fault occurrence in …

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This report addresses the AEC symposium on particle-fluid mechanics

Heat loading analysis of the Solid Waste Disposal Facility (SWDF) waste storage configurations show the containers may exceed 90{degrees}C without any radioactive decay heat contribution. Contamination containment is primarily controlled in TRU waste packaging by using multiple bag layers of polyvinyl chloride and polyethylene. Since literature values indicate that these thermoplastic materials can begin mechanical degradation at 66{degrees}C, there was concern that the containment layers could be breached by heating. To better define the mechanical degradation temperature limits for the materials, a series of heating tests were conducted over a fifteen and thirty minute time interval. Samples of a low-density polyethylene (LDPE) bag, a high-density polyethylene (HDPE) high efficiency particulate air filter (HEPA) container, PVC bag and sealing tape were heated in a convection oven to temperatures ranging from 90 to 185{degrees}C. The following temperature limits are recommended for each of the tested materials: (1) low-density polyethylene -- 110{degrees}C; (2) polyvinyl chloride -- 130{degrees}C; (3) high-density polyethylene -- 140{degrees}C; (4) sealing tape -- 140{degrees}C. Testing with LDPE and PVC at temperatures ranging from 110 to 130{degrees}C for 60 and 120 minutes also showed no observable differences between the samples exposed at 15 and 30 minute intervals. Although these observed temperature …

This report details events of importance reported by the Hanford Operations Office for the week ending May 11, 1949.

Timely disposal of the weapons plutonium is of paramount importance to permanently safeguarding this material. GE`s 1300 MWe Advanced Boiling Water Reactor (ABWR) has been designed to utilize fill] core loading of mixed uranium-plutonium oxide fuel. Because of its large core size, a single ABWR reactor is capable of disposing 100 metric tons of plutonium within 15 years of project inception in the spiking mode. The same amount of material could be disposed of in 25 years after the start of the project as spent fuel, again using a single reactor, while operating at 75 percent capacity factor. In either case, the design permits reuse of the stored spent fuel assemblies for electrical energy generation for the remaining life of the plant for another 40 years. Up to 40 percent of the initial plutonium can also be completely destroyed using ABWRS, without reprocessing, either by utilizing six ABWRs over 25 years or by expanding the disposition time to 60 years, the design life of the plants and using two ABWRS. More complete destruction would require the development and testing of a plutonium-base fuel with a non-fertile matrix for an ABWR or use of an Advanced Liquid Metal Reactor (ALMR). The …

Progress was reported on adsorption work in experimental, theoretical and field projects. The reinjection task is now nearing completion of the work on optimizing injection into the Palinpinon geothermal field in the Philippines. Well test analysis research has been expanded with the initiation of a new project on multiwell interference test interpretation.

The elevation of the surficial sediment/basalt contact at the Subsurface Disposal Area (SDA), within the Radioactive Waste Management Complex (RWMC) is presented to provide a data base for future remedial actions at this site. About 1,300 elevation data from published and unpublished reports, maps, and surveyors notes were compiled to generate maps and cross-sections of the surficial sediment/basalt contact. In general, an east to west trending depression exists in the south central portion of the SDA with basalt closer to land surface on the northern and southern boundaries of the SDA. The lowest elevation of the surficial sediment/basalt contact is 4,979 ft and the greatest is land surface at 5,012 ft. The median elevation of the sediment/basalt interface is 4,994 ft. The median depth to basalt in the SDA is 16 ft if land surface elevation is assumed to be 5,010 ft. The depth from land surface to the sediment/basalt interface ranges from 24 ft in the southeast corner of the SDA to less than 3 ft at the north-central boundary of the SDA.

Daily river temperature cycling has existed at reactor area river pumphouses from the beginning of operations. Of small account at first and due only to the daily air and solar radiation cycle, the phenomenon became significant with the initiation of daily river flow cycling at priest Rapids Dam to meet changing power generation requirements. The problem was compounded by the construction of the N reactor, placing a water intake and outfall at approximately half the previous distance between the K and D reactors. The decidedly non-uniform effluent distributions in the river at the shorter distances has caused apparent daily temperature swings at 181-D. This distribution was determined by the use of rhodamine B dye. Estimates of the relative contributions over a range of river flow to the temperature cycling at 181-N were made. A similar evaluation of the relative contributions at low river flow only at 181-D from K and N reactor operations has been requested by Douglas United Nuclear, Inc. This report is made to satisfy that request.

The purpose of this report is to summarize all actual and potential power level limits under which the K Reactors may be forced to operate during the next year. In addition, a summary of the methods being followed to eliminate each is to be discussed along with a graphical presentation of the relationship of the various limits. For the purpose of this report, it was assumed that all power levels will be attainable from a physics aspect since these problems are discussed elsewhere. It is not the intent of this report to recommend that these power levels be attained but only to indicate what production levels are possible through operation on any one limit. Seven outlet temperature limits govern operation at the K Reactors. They are: TBI Limit; Crosstie Limit; Rear Header Saturation Limit; Bulk Outlet Temperature Limit; Tube Corrosion Limit; Temperature Monitor Limit; and Rupture Control Point. Operation during the summer months of 1957 will require cuts in power in order to remain within these limits unless modes of circumventing a few are found. The limits are shown graphically in the appendix at the various flow rates probable. From these curves it is evident that the Low Trip TBI …

About 128 air samplers and CAMs presently in service to detect and document potential radioactive release from `H` and `F` area tank farm ventilation stacks are scheduled for replacement and/or upgrade by Projects S-5764, S-2081, S-3603, and S-4516. The seven CAMs scheduled to be upgraded by Project S-4516 during 1995 are expected to provide valuable experience for the three remaining projects. The attached document provides design guidance for the standardized High Level Waste air sampling system.

During 1992, a series of hydrologic characterization tests were conducted at the well 4A -- 4T test facility complex. Details concerning these tests are described in Swanson (1992). Two of the tests, a constant-rate discharge test conducted on March 30, 1992 and a slug interference test performed on April 15, 1992, are the focus of this report.

We have completed the 5480.11 survey for Wing 1. All area(s)/item(s) requested by the 5480.11 committee have been thoroughly surveyed and documented. Decontamination/disposal of contaminated items has been accomplished. The wing 1 survey was started on 8/13/90 and completed 9/18/90. However, the follow-up surveys were not completed until 2/18/91. We received the final set of smear samples for wing 1 on 1/13/91. A total of 5,495 smears were taken from wing 1 and total of 465 smears were taken during the follow-up surveys. There were a total 122 items found to have fixed contamination and 4 items with smearable contamination in excess of the limits specified in DOE ORDER 5480.11 (AR 3-7). The following area(s)/item(s) were not included in the 5480.11 survey: Hallways, Access panels, Men`s and women`s change rooms, Janitor closets, Wall lockers and item(s) stored in wing 1 hallways and room 1116. If our contract is renewed, we will include those areas in our survey according to your request of April 15, 1991.

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