Progress is reported in six areas of research: air quality, water quality, ecosystem quality, subsidence and seismicity, socioeconomic effects, and integrated assessment. A major goal of the air quality element is to evaluate the rate of emission of H/sub 2/S, CO/sub 2/, H/sub 2/, N/sub 2/, CH/sub 4/, and C/sub 2/H/sub 6/ from the operation of the geothermal loop experimental facility at Niland. Concentrations of H/sub 2/S were found to vary between 1500 to 4900 ppM by volume at the Niland facility. To distinguish between geothermal fluids and other waters, extensive sampling networks were established. A major accomplishment was the installation of a high-resolution subsidence-detection network in the Salton Sea geothermal field area, centered on the test facility at Niland. A major effort went into establishing a background of data needed for subsequent impact assessments related to socioeconomic issues raised by geothermal developments. Underway are a set of geothermal energy scenarios that include power development schedules, technology characterizations, and considerations of power-plant-siting criteria. A Gaussian air-pollution model was modified for use in preliminary air-quality assessments. A crop-growth model was developed to evaluate impacts of gases released from geothermal operations on various agricultural crops. Work is also reported on the legal …

Low-resolution field ionization and high-resolution 70-eV electron-impact mass spectra data were obtained for 28 GPC fractions acquired from Bartlett, Kansas, heavy petroleum by members of the Separation and Characterization group at the Bartlesville Energy Research Center. This group was supplied with most-probable empirical formulas deduced from the high resolution electron-impact data. Analysis of the qualitative and quantitative analytical data previously obtained for GPC fractions from a Synthoil sample by high- and low-resolution field-ionization and high-resolution 70-eV electron-impact mass spectrometry is essentially complete. A study of field-ionization sensitivities for saturates and mixtures of saturates and aromatics is in progress. Components required to modify the combined FI/EI ion source to permit operation in the field desorption mode have been ordered.

We report on the raw disk i/o performance of a set of Compaq StorageWorks RAID arrays connected to our cluster of Compaq ES40 computers via Fibre Channel. The best cumulative peak sustained data rate is l17MB/s per node for reads and 77MB/s per node for writes. This value occurs for a configuration in which a node has two Fibre Channel interfaces to a switch, which in turn has two connections to each of two Compaq StorageWorks RAID arrays. Each RAID array has two HSG80 RAID controllers controlling (together) two 5+p RAID chains. A 10% more space efficient arrangement using a single 1l+p RAID chain in place of the two 5+P chains is 25% slower for reads and 40% slower for writes.

Efforts were concentrated on numerically modeling the time-dependent particle coarsening (Ostwald ripening) process. Four models were included: Lifshsitz-Slyozov-Wagner, Brailsford and Wynblatt, Marqusee and Ross, and Marder. The simulations monitored the particle size distribution (PSD) as a function of time; initial PSDs were derived from classical nucleation theory. The ripening kinetics can be represented as a plot of the second moment of normalized PSD vs time. A geometric correction factor is discussed. Future research is planned on Al-Li.

A series of laser welds have been made on several materials using a Rofin-Sinar DY-033, 3.3 kW, Diode-Pumped Continuous Wave (CW) Nd:YAG laser system, located at Los Alamos National Laboratory. Materials welded in these experiments include 21-6-9 stainless steel, 304L stainless steel, vanadium, and tantalum. The effects of changes in the power input at a constant travel speed on the depth, width, aspect ratio, and total melted area of the welds have been analyzed. Increases in the measured weld pool dimensions as a function of power input are compared for each of the base metals investigated. These results provide a basis for further examining the characteristics of diode pumped CW Nd:YAG laser systems in welding applications.

In keeping with the Open Source tradition, we want our Babel 1.0 release to indicate a certain level of capability, maturity, and stability. From our first release (version 0.5.0) in July of 2001 to our current (18th) release (version 0.9.6) we have continued to add capabilities in response to customer feedback, our observations in the field, and a consistent vision for interoperability. The key to our maturity is without a doubt the ever-increasing demands of our growing user base... both in terms of sheer size and sophistication with the underlying technology. Stability is a special challenge for any research project. With our 1.0 release, we will branch and maintain a stable Babel 1.0 code line for at least a full year. This means no new features and no backward incompatible changes, only bug fixes. All continuing R&D will be performed on a separate development tree. Currently, Babel has a quarterly release cycle with no guarantee for backward compatibility from one release to the next (though we certainly try to make migration as painless as possible). Now is the time where we can see a good point for a Babel 1.0 release. But, seeing that point is different from being there. …

This document provides the structural analysis (static and thermal loads) of the 241SY101 tank to determine the maximum allowable temperature and rate of heating that could be applied to tank 241SY101 through annulus air heating without detrimental effects to the structural integrity of the concrete and steel liner of the tank.

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This report discusses current plans of the Irradiation Processing Department which call for the inauguration of an E-metal (0.94% U-235) replacement program for the C-metal columns now in reactor use. Other reactor planning is considering the use of E-metal for E-N (lithium) nd E-Co (cobalt) loadings, compensation for reactor biological shields, and for the improved production reactor (IPR). Activation of any of these plans will be dependent on results of the test programs and A.E.C. policy decisions. The quantity of E-metal that might require separation processing is estimated and an economic analysis is provided

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The Automated Transportation Management System (ATMS) Software User Guide (SUG) constitutes the user procedures for the ATMS System. Information in this document will be used by the user to operate the automated system. It is intended to be used as a reference manual to guide and direct the user(s) through the ATMS software product and its environment. The objectives of ATMS are as follows: to better support the Procurement function with freight rate information; to free Transportation Logistics personnel from routine activities such as the auditing and input of freight billing information; to comply with Headquarters Department of Energy-Inspector General (DOE-IG) audit findings to automate transportation management functions; to reduce the keying of data into the Shipment Mobility Accountability Collection (SMAC) database; and to provide automation for the preparing of Bill of Lading, Declaration of Dangerous Goods, Emergency Response Guide and shipping Labels using HM181 Retrieval of hazardous material table text information.

The use of self-supported fuel elements in ribless Zircaloy-2 tubes at C-Reactor requires some inlet nozzle modification to allow charging of the larger overall diameter fuel pieces. A new nozzle assembly has been developed (by Equipment Development Operation -- IPD) which will allow use of the new fuel pieces and at the same time increase the reliability of the header-to-tube piping and reduce pumping power losses. Flow test data were requested for the new assembly and the results of these tests are presented herein. This report also presents a comparison of the header to tube energy losses for the various reactor inlet nozzle assemblies which are currently used on the Hanford production reactors.

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Two coextruded, Zr-2 clad, natural uranium, seven rod cluster fuel elements were irradiated to a calculated exposure of 1250 MWD/T in the KER Facility and discharged 1-16-59. The fuel elements were NPR candidate fuel and examination was requested to determine the behavior of coextruded, Zr-2 clad, natural uranium irradiated at core temperatures of approximtely 425{degree}C. The elements were transferred to the Radiometallurgy Laboratory 2-25-59. The elements demonstrated excellent in reactor performance with no significant changes in either the fuel or the hardware. Detailed examination of the central rod and two peripheral rods from one of the clusters showed no microcracks in the uranium. Moderate growth was observed in the fuel at the unrestricted rod ends.

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The objective of this Supplement described in this report to Pt-IP-250-A is to d enriched tube-and-tube elements will develop pitting corrosion on the Zircaloy-2 jackets when irradiated in pH 10 water. The measurement of dimensional changes in the fuel elements and the observation of the effect of irradiation on the uranium and bond area are also objectives of the test, but secondary in importance to identifying a pitting corrosion problem in NPR quality water, if one exists.

This is the monthly report for the Hanford Laboratories Operation. Metallurgy, reactor fuels, physics and instrumentation, reactor technology, chemistry, separation processes, biology, financial activities, employee relations, laboratories auxiliaries, radiation protection, operation research, inventions, visits, and personnel status are discussed. This report is for September 1956.

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The criteria contained in this report have been established to provide the technical bases for the design modifications involved in the K-Reactor tube replacement. The ultimate intent of these criteria is to provide the basic technical data and concepts to assure: technical feasibility and operability of the reactor system as modified; operation of the reactor and its services to minimize nuclear and radiation hazards; and appropriate lifetime of the reactor and its service facilities as modified. The criteria are appropriately broad and may not contain all the data necessary to accomplish detail design. The information contained herein shall serve as a basis for evaluation and approval of all portions of the modification relating to the process as indicated in the above three points.

The objective of this production test is to evaluate the behavior during irradiation of nominally 1.739 inch OD., 1.074 inch ID., Zircaloy-2 jacketed single tube fuel elements with brazed end closures at operating conditions somewhat more severe than those expected for N Reactor fuel element outer tubes. Enriched single tube elements with brazed end closures and modified fuel element supports are authorized for irradiation in the KEG loops to an exposure no higher than 4000 MWD/T. A typical loading and set of operating conditions are given; these may be modified, however, by obtaining appropriate approvals.

This document is designed to present as complete a review of the hazards associated with the operation of the N Reactor as is feasible at this time. Where completeness is not possible the problems are indicated and probable paths of solution are suggested. Background material is provided to put the hazards in context. Supplements to this report will be issued when the additional data and information required for completeness are obtained. This review is organized into two parts. The first part issued as Volume I is in the nature of an expanded summary. The second part of the review will be issued in a succeeding volume or volumes and will consist of results of evaluations obtained following the publishing of this volume plus more detailed supporting information.

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Tantalum experiences severe intergranular attack (IGA) when in contact with molten plutonium. This IGA of tantalum has produced part failures in crucibles used during Trident and molten salt extraction (MSE) runs and in two stirring rods used in MSE runs. These parts were used at temperatures ranging from 750{degrees}C to 900{degrees}C for a minimum time of 12 hours to a maximum time of 20 hours. 5 refs., 22 figs.

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