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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.

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 model-based flotation control scheme is being implemented to achieve optimal performance in the handling and treatment of fine coal. The control scheme monitors flotation performance through on-line analysis of ash content. Then, based on the economic and metallurgical performance of the circuit, variables such as reagent dosage, air addition rate, pulp density and pulp level are adjusted using model-based control algorithms to compensate for feed variations and other process disturbances. Recent developments in video-based sensor technology are being applied for on-line determination of slurry ash content. During the third quarter of this project, work continued on the testing and calibration of the video-based ash analyzer, and a plant sampling campaign was conducted to provide data for the development of a mathematical process model and the model-based control algorithms.

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 note describes my analysis of the measurement of the electron energy distribution function in a DC glow discharge reported by T. Kimura, K. Akatsuka, and K. Ohe, in `Experimental and theoretical investigations of DC glow discharges in argon-nitrogen mixtures,`J. Phys. D: Appl. Phys. 27 (1994) 1664-1671. T. Kimura of the Department of Systems Engineering at the Nagoya Institute of Technology sent me this paper in 1994, as well as `Electron Energy Distribution Function in Neon-Nitrogen Mixture Positive Column,` T. Kimura, and K. Ohe, Jpn. J. Appl. Phys. Vol. 3 1, Part 1, No. 12A, December 1992, pp. 4051- 4052. I base my analysis on the data for a pure N{sub 2} discharge at p=1 torr in the 1994 paper. Figures 2 and 3 in that paper show a discrepancy between f({epsilon}) as measured by Langmuir probing and f({epsilon}) as calculated from E/N based on the measured axial field. Kimura et. al. explain their observation of hotter than expected electrons on superelastic collisions with vibrationally excited nitrogen. My fundamental point is that the radial field generated by ambipolar diffusion significantly augments E/N above the contribution from the axial field in this experiment, and creates a higher than expected radially averaged …

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 results of a study of the acoustic emission (AE) behavior of impact-damaged, spherical, composite test specimens subjected to thermal cycling and biaxial mechanical loading are presented. Seven Kevlar{reg_sign}-epoxy, filament-wound, spherical composite test specimens were subjected to different levels of impact damage. The seven specimens were a subset of a group of 77 specimens made with simulated fabrication-induced flaws. The specimens were subjected to two or three cycles of elevated temperature and then hydraulically pressurized to failure. The pressurization regime consisted of two cycles to different intermediate levels with a hold at each peak pressure level; a final pressurization to failure followed. The thermal and pressurization cycles were carefully designed to stimulate AE production under defined conditions. Both impacted and nonimpacted specimens produced thermo-AE (the term given to emission stimulated by thermal loading), but impacted specimens produced significantly more. Thermo-AE was produced primarily by damaged composite material. Damaged material produced emission as a function of both rising and falling temperature, but the effect was not repeatable. More seriously damaged specimens produced very large quantities of emission. Emission recorded during the static portion of the hydraulic loading cycles varied with load, time, and degree of damage. Static load AE behavior was …

A double-shell tank (DST) inspection (DSTI) system was performance tested over three months until August 1995 at Pittsburgh, Pennsylvania, completing a contract initiated in February 1993 to design, fabricate, and test an ultrasonic inspection system intended to provide ultrasonic test (UT) and visual data to determine the integrity of 28 DSTs at Hanford. The DSTs are approximately one-million-gallon underground radioactive-waste storage tanks. The test was performed in accordance with a procedure (Jensen 1995) that included requirements described in the contract specification (Pfluger 1995). This report documents the results of tests conducted to evaluate the performance of the DSTI system against the requirements of the contract specification. The test of the DSTI system also reflects the performance of qualified personnel and operating procedures.

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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.

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.

This document presents the current strategy and path forward for removal of the Shippingport Pressurized Water Reactor Core 2 blanket fuel assemblies from their existing storage configuration (wet storage within the T Plant canyon) and transport to the Canister Storage Building (designed and managed by the Spent Nuclear Fuel. Division). The removal plan identifies all processes, equipment, facility interfaces, and documentation (safety, permitting, procedures, etc.) required to facilitate the PWR Core 2 assembly removal (from T Plant), transport (to the Canister storage Building), and storage to the Canister Storage Building. The plan also provides schedules, associated milestones, and cost estimates for all handling activities.

This safety evaluation for packaging evaluates and documents the ability of the plywood boxes listed below to meet the packaging requirements of WHC-CM-2-14, Hazardous Material Packaging and Shipping, for the onsite transfer of Type B radioactive material. Onsite transfer is the transport of hazardous materials on controlled routes confined to established limited areas and to portions of federally owned roadways to which public access is prohibited during transfer. The plywood boxes being used for this transport are PIN number PNLD-95-322 and PNLD-95-385. The contents being transported are wood, plastic, piping, rubber, and gloves. The source term was determined by nondestructive analysis and obtained from the solid waste storage/disposal record. Before the nondestructive analysis, the intention was to transport the boxes under WHC-SD-TP-SEP-020, Safety Evaluation for Packaging (Onsite) Plywood Box (WHC 1994), but Type B shipments are not included.

During most of the year, it is assumed that the vapor space in the 177 radioactive waste tanks on the Hanford Project site contain a uniform mixture of gases. Several of these waste tanks (currently twenty-five, 6 Double Shell Tanks and 19 Single Shell Tanks) were identified as having the potential for the buildup of gasses to a flammable level. An active ventilation system in the Double Shell Tanks and a passive ventilation system in the Single Shell Tanks provides a method of expelling gasses from the tanks. A gas release from a tank causes a temporary rise in the tank pressure, and a potential for increased concentration of hydrogen gas in the vapor space. The gas is released via the ventilation systems until a uniform gas mixture in the vapor space is once again achieved. The Standard Hydrogen Monitoring System (SHMS) is designed to monitor and quantify the percent hydrogen concentration during these potential gas releases. This document describes the design of the Standard-D Hydrogen Monitoring System, (SHMS-D) and its components as it differs from the original SHMS.

This characterization report summarizes the available information on the historical uses, current status, and the sampling and analysis results of waste contained in underground storage tank 241-BY-104. This report supports the requirements of the Hanford Federal Facility Agreement and Consent Order, Milestone M-44-09. Tank 241-BY-104 is one of 12 single-shell tanks located in the BY-Tank Farm in the 200 East Area of the Hanford Site. Tank 241-BY-104 entered service in the first quarter of 1950 with a transfer of metal waste from an unknown source. Through cascading, the tank was full of metal waste by the second quarter of 1951. The waste was sluiced in the second quarter of 1954. Uranium recovery (tributyl phosphate) waste was sent from tank 241-BY-107 during the second quarter of 1955 and from tank 241-BY-110 during the third quarter of 1955. Most of this waste was sent to a crib during the fourth quarter of 1955. During the third and fourth quarters of 1956 and the second and third quarters of 1957, the tank received waste from the in-plant ferrocyanide scavenging process (PFeCN2) from tanks 241-BY-106, -107, -108, and -110. This waste type is predicted to compose the bottom layer of waste currently in the …

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.

This document summarizes the information on the historical uses, present status, and the sampling and analysis results of waste stored in Tank 241-T-109. This report supports the requirements of Tri-Party Agreement Milestone M-44-09.

This document provides the technical requirements specification for the retrieval of waste from the underground storage tanks at the Hanford Site. All activities covered by this scope are conducted in support of the Tank Waste Remediation System (TWRS) mission.

This document provides reference to the Acceptance for Beneficial Use (ABU) documentation and effects turnover of the AW tank inlet air control stations from TWRS Equipment Engineering to Evaporator Project.

The authors propose to measure asymmetries in the inclusive reactions, using a transversely polarized beam, a liquid hydrogen target, and a carbon target. The measurements would be made using the 23-GeV/c proton beam in an extracted beam line from the AGS, a spectrometer consisting of an analyzing magnet, scintillation hodoscopes, scintillation trigger counters, and a gas threshold Cerenkov counter. The kinematic range covered by the experiments would be p{sub T} up to 1.0 GeV/c and x{sub F} = p*{sub L}/p*{sub max} {approx} 0.5 to 0.8. The purpose of this proposal is to obtain basic information in order to design a polarimeter for the RHIC polarized beams. The RHIC polarimeter is a crucial item for the success of the RHIC spin program.

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 …

Approximately 100 million gallons ({approx}400,000 m{sup 3}) of existing U.S. Department of Energy (DOE) owned radioactive waste stored in underground tanks can not be disposed of as low-level waste (LLW). The current plan for disposal of UST waste which can not be disposed of as LLW is immobilization as glass and permanent storage in an underground repository. Disposal of LLW generally can be done sub-surface at the point of origin. Consequently, LLW is significantly less expensive to dispose of than that requiring an underground repository. Due to the lower cost for LLW disposal, it is advantageous to separate the 100 million gallons of waste into a small volume of high-level waste (HLW) and a large volume of LLW.