At the Hanford Site organic compounds were measured in tank supernate simulant solutions during FY 1995. This solubility information will be used to determine if these organic salts could exist in solid phases (saltcake or sludges) in the waste where they might react violently with the nitrate or nitrite salts present in the tanks. Solubilities of sodium glycolate, succinate, and caproate salts; iron and aluminum and butylphosphate salts; and aluminum oxalate were measured in simulated waste supernate solutions at 25 {degree}C, 30 {degree}C, 40 {degree}C, and 50 {degree}C. The organic compounds were selected because they are expected to exist in relatively high concentrations in the tanks. The solubilities of sodium glycolate, succinate, caproate, and butylphosphate in HLW tank supernate solutions were high over the temperature and sodium hydroxide concentration ranges expected in the tanks. High solubilities will prevent solid sodium salts of these organic acids from precipitating from tank supernate solutions. The total organic carbon concentrations (YOC) of actual tank supernates are generally much lower than the TOC ranges for simulated supernate solutions saturated (at the solubility limit) with the organic salts. This is so even if all the dissolved carbon in a given tank and supernate is due to …

This inspection plan is written to meet the requirements of WAC 173-303 for operations of a TSD facility. Owners/operators of TSD facilities are required to inspection their facility and active waste management units to prevent and/or detect malfunctions, discharges and other conditions potentially hazardous to human health and the environment. A written plan detailing these inspection efforts must be maintained at the facility in accordance with Washington Administrative Code (WAC), Chapter 173-303, ``Dangerous Waste Regulations`` (WAC 173-303), a written inspection plan is required for the operation of a treatment, storage and disposal (TSD) facility and individual TSD units. B Plant is a permitted TSD facility currently operating under interim status with an approved Part A Permit. Various operational systems and locations within or under the control of B Plant have been permitted for waste management activities. Included are the following TSD units: Cell 4 Container Storage Area; B Plant Containment Building; Low Level Waste Tank System; Organic Waste Tank System; Neutralized Current Acid Waste (NCAW) Tank System; Low Level Waste Concentrator Tank System. This inspection plan complies with the requirements of WAC 173-303. It addresses both general TSD facility and TSD unit-specific inspection requirements. Sections on each of the TSD …

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This analysis is prepared by the Mined Geologic Disposal System (MGDS) Waste Package Development Department (WPDD) to determine the dose rates from the MPC waste packages to be used by the EBS and other repository systems to incorporate ALARA practices in the overall repository design in compliance with the goals of the Waste Package Implementation Plan for conceptual design. These design calculations are performed in sufficient detail to provide a comprehensive comparison base with other design alternatives. The objectives of this evaluation are (1) to show the dose rate as a function of distance from the waste package surface and (2) to provide the shielding thicknesses required for the waste package transporter to meet a 10 mrem/hr target dose rate at 2 meters from the transporter surface.

The purpose and objective of this analysis are to expand the level of detail and confirm member sizes for steel sets included in the Ground Support Design Analysis, Reference 5.20. This analysis also provides bounding values and details and defines critical design attributes for alternative configurations of the steel set. One possible configuration for the steel set is presented. This analysis covers the steel set design for the Exploratory Studies Facility (ESF) entire Main Loop 25-foot diameter tunnel.

This document summarizes the final results of push mode core samples 131, 133, and 136 for tank 241-U-105.

This document summarizes the information on the historical uses, present status, and the sampling and analysis results of waste stored in Tank 241 BY-106. This report supports the requirements of the Tri Party Agreement Milestone M-44-09.

Shown in Figure 1 is a side view of the D0 F-disk assembly. SVX II chips are mounted to a flex copper/kapton Circuit, which is glued to a beryllium substrate. Figure 1 shows the top and bottom disk assemblies mounted on the cooling channel. However the disks are not mounted directly opposite one another as shown, but alternately rotate through 30{sup o} wedges mounted on either side of the cooling channel. The assumed channel temperature for these calculations is 0 C, as in the cases of the ladder cooling calculations, ref. [1] and [2]. The assumed SVX II chip power is 0.400 W. The finite difference method is used to calculate the temperature profiles of the various components. It is described in Ref. [1]. Each disk is read out using SVX II chips on both sides of the silicon. The silicon is 59.2 mm wide at its widest location. The SVX II chip location opposite the cooling channel has 8 chips mounted on the hybrid. and there are 6 SVX II chips mounted outboard of the cooling channel on the same side as the cooling channel. The SVX II chips mounted on the same side as the cooling channel read …

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The European Atomic Energy Community (EURATOM) is a regional organization established in 1958 to "create conditions necessary for the establishment and growth of nuclear industries." The United States promoted its establishment to benefit sales of U.S. nuclear power reactors and related equipment. fuels and technology in Europe. The agreement for nuclear cooperation between the United States and EURATOM expired at the end of 1995. On November 29 President Clinton submitted to Congress a new agreement. reached after several years of difficult negotiation.

In a sense the term "budget process" is a misnomer when applied to the federal government. Budgeting for the federal government is not a single process; rather it consists of a number of processes that have evolved separately and which occur with varying degrees of coordination. This report, and the accompanying flow chart, attempt to clarify the role played by each of the component parts of the budget process as well as how they operate together.

The Line Item Veto Act of 1996 (Public Law 104-130, 110 Stat. 1200), gives the President expanded rescission authority by changing the burden of action and coverage. Under the Impoundment Control Act of 1974 (88 Stat. 332), the President must obtain the support of both Houses within a specified time period for a rescission to become permanent, while the new law puts the burden on Congress to disapprove presidential rescission proposals within a 30-day period. Along with rescission of discretionary appropriations, the new law subjects any new item of direct spending (entitlement) and certain limited tax benefits to cancellation as well.

The Line Item Veto Act of 1996 (P.L. 104-130) authorizes the President to cancel discretionary budget authority, new entitlements, and limited tax benefits. When this authority becomes available on January 1, 1997, it will change the dynamics among all three branches of government. In response to presidential decisions to cancel certain provisions, Congress may change the way it drafts bills and committee reports. Lawsuits will bring these presidential and congressional actions before federal courts, raising a number of constitutional and statutory questions.

The incompressible Navier-Stokes flow code HYDRA has been modified to produce pressure time history databases for both two-dimensional (2D) and three-dimensional (3D) simulations. This report describes the control parameters needed to activate this option in HYDRA. A detailed description of the actual code modifications are included. The generated pressure time history data is formatted for postprocessing with the code THUG. A brief description of how to produce pressure time history plots is included here for completeness.

Fracture mechanics analyses were done on 3 critical locations on the lower flange of the load beam of the Ederer 5 ton and 4 ton cranes in the D.A.F. Facility. This was done to determine appropriate flaw sizes for NDE detection during periodic inspection, and appropriate inspection intervals.

A reliable, consistent scheme to study phase equilibria in ternary substitutional alloys based on the tight-binding approximation is presented. With electronic parameters from linear muffin-tin orbital calculations, the computed density of states and band structures compare well with those from more accurate {ital ab}{ital initio} calculations. Disordered alloys are studied within the tight-binding coherent-potential approximation extended to alloys; energetics of ordered systems are obtained through effective pair interactions computed with the general perturbation method; and partially ordered alloys are studied with a novel simplification of the molecular coherent-potential approximation combined with the general perturbation method. The formalism is applied to bcc-based Zr-Ru-Pd alloys which are promising candidates for medical implant devices. Using energetics obtained from the above scheme, we apply the cluster- variation method to study phase equilibria for particular pseudo- binary alloys and show that results are consistent with observed behavior of electronic specific heat coefficient with composition for Zr{sub 0.5}(Ru, Pd){sub 0.5}.

This document serves as a modification to Notice of Construction. (NOC) (DOE-RL 1992) pursuant to the requirements of WAC 173-400-110 and 173-460-040 0837 for the expansion of approved influent streams to the ETF.

The overall objective of the project is to demonstrate that a partial oxidation system, which utilizes a transport reactor, is a viable means of converting refinery wastes, byproducts, and other low value materials into valuable products. The primary product would be a high quality fuel gas, which could also be used as a source of hydrogen. The concept involves subjecting the hydrocarbon feed to pyrolysis and steam gasification in a circulating bed of solids. Carbon residue formed during pyrolysis, as well as metals in the feed, are captured by the circulating solids which are returned to the bottom of the transport reactor. Air or oxygen is introduced in this lower zone and sufficient carbon is burned, sub-stoichiometrically, to provide the necessary heat for the endothermic pyrolysis and gasification reactions. The hot solids and gases leaving this zone pass upward to contact the feed material and continue the gasification process. The Transport Reactor Test Unit (TRTU) was commissioned to conduct studies on pyrolysis of Rose Bottoms using spent FCC (Fluid Catalytic Cracker) catalyst as the circulating medium and gasification of this carbon over a temperature range of 1,600 to 1,700 F. The Rose Bottoms (Residuum Oil Supercritical Extraction) was produced in …

Acceptance Test Report for construction functional testing of Project W-030 Backup Power System. Project W-030 provides a ventilation upgrade for the four Aging Waste Facility tanks. Backup power includes a single 125 KW diesel generator, three 10-kva uninterruptible power supply units, and all necessary control.

This report documents radionuclide air emissions from the Hanford Site in 1995, and the resulting effective dose equivalent (FDE) to the maximally exposed member of the public, referred to as the `MEI.` The report has been prepared and will be submitted in accordance with reporting requirements in the Code of Federal Regulations, Title 40, Protection of the Environment, Part 61, `National Emissions Standards for Hazardous Air Pollutants,` Subpart H, `National Emission Standards for Emissions of Radionuclides Other than Radon from Department of Energy Facilities.` This report has also been prepared for and will be submitted in accordance with the reporting requirements of the Washington Administrative Code Chapter 246-247, `Radiation Protection-Air Emissions.`

This report from the Amarillo National Resource Center for Plutonium describes progress in the following areas: electronic resource library; the senior technical review group; environment, health, and safety and remedial action activities; communications, education, and training; and plutonium and other materials.

This supporting document contains a database of waste transactions and waste status reports for all the waste tanks in the southwest quadrant of the 200 Area of the Hanford Site.

This Final Technical Report presents the accomplishments on Phase 2 of the Advanced Turbine Systems (ATS). The ATS is an advanced, natural gas fired gas turbine system that will represent a major advance on currently available industrial gas turbines in the size range of 1--20 MW. This report covers a market-driven development. The Market Survey reported in Section 5 identified the customer`s performance needs. This market survey used analyses performed by Solar turbine Incorporated backed up by the analyses done by two consultants, Research Decision Consultants (RDC) and Onsite Energy Corporation (Onsite). This back-up was important because it is the belief of all parties that growth of the ATS will depend both on continued participation in Solar`s traditional oil and gas market but to a major extent on a new market. This new market is distributed electrical power generation. Difficult decisions have had to be made to meet the different demands of the two markets. Available resources, reasonable development schedules, avoidance of schedule or technology failures, probable acceptance by the marketplace, plus product cost, performance and environmental friendliness are a few of the complex factors influencing the selection of the Gas Fired Advanced Turbine System described in Section 3. Section …