This report describes batch and ion exchange column laboratory scale studies investigating ex situ methods to remove chromate (chromium [VI]), nitrate (NO{sub 3}{sup -}) and uranium (present as uranium [VI]) from contaminated Hanford site groundwaters. The technologies investigated include: chemical precipitation or coprecipitation to remove chromate and uranium; and anion exchange to remove chromate, uranium and nitrate. The technologies investigated were specified in the 100-HR-3 Groundwater Treatability Test Plan. The method suggested for future study is anion exchange.

This report examines experimental results obtained from three P Tunnel events -- Mission Cyber, Disko Elm, and Distant Zenith. The objective of the study was to determine if there were any differences in the explosive source coupling for the three events. It was felt that Mission Cyber might not have coupled well because the ground motions recorded for that event were much lower than expected based on experience from N Tunnel. Detailed examination of the physical and chemical properties of the tuff in the vicinity of each explosion indicated only minor differences. In general, the core samples are strong and competent out to at least 60 m from each working point. Qualitative measures of core sample strength indicate that the strength of the tuff near Mission Cyber may be greater than indicated by results of static testing. Slight differences in mineralogic content and saturation of the Mission Cyber tuff were noted relative to the other two tests, but probably would not result in large differences in ground motions. Examination of scaled free-field stress and acceleration records collected by Sandia National Laboratory (SNL) indicated that Disko Elm showed the least scatter and Distant Zenith the most scatter. Mission Cyber measurements tend …

The purpose of this document is to describe the radiological and chemical source terms for the major projects of the Solid Waste Operations Complex (SWOC), including Project W-112, Project W-133 and Project W-100 (WRAP 2A). For purposes of this document, the term ``source term`` means the design basis inventory. All of the SWOC source terms involve the estimation of the radiological and chemical contents of various waste packages from different waste streams, and the inventories of these packages within facilities or within a scope of operations. The composition of some of the waste is not known precisely; consequently, conservative assumptions were made to ensure that the source term represents a bounding case (i.e., it is expected that the source term would not be exceeded). As better information is obtained on the radiological and chemical contents of waste packages and more accurate facility specific models are developed, this document should be revised as appropriate. Radiological source terms are needed to perform shielding and external dose calculations, to estimate routine airborne releases, to perform release calculations and dose estimates for safety documentation, to calculate the maximum possible fire loss and specific source terms for individual fire areas, etc. Chemical source terms (i.e., …

The design of the Sign-Selected Quadrupole Train for E-815 (NuTeV) is set forth. The relevant physics requirements are explained. The optics of the beam are presented, along with an explanation of the proton dumping scheme. A discussion of rates and backgrounds follows, with special care given to backgrounds from scraping and obstructions. The relevant tolerances for beam construction are given and justified by simulations of the beamline. This leads to a discussion of the beam monitoring.

The overall goal of this program is to develop a system based on reverse-osmosis (RO) membranes that can treat oily water economically. This system will be based on the use of thin-film-composite (TFC) membranes that consist of a selective coating placed on a solvent-resistant hollow-fiber support. For this program, the authors plan to develop solvent-resistant hollow-fiber supports and coat them with a {open_quotes}loose-RO{close_quotes} coating. They developed the TTM coating used in this program in previous work for the treatment of oily waste waters. During this reporting period, work was focused on operating the demonstration test unit at a test site near Houston, Texas. During the next reporting period, the authors plan to continue long-term testing at the demonstration test site. The completion of the demonstration test, preparation of the final report, and technology transfer are the tasks remaining in this program.

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A method is described to increase the yield of Anti-Protons/cycle by about a factor of five, without building new storage rings. In this method, the full circumference of the Main Injector is filled and accelerated. Existing RF cavities are then used to perform ``snap coalescing`` which clumps the charge in azimuth to produce 28 large RF bunches {approximately}5ns long. These are then extracted and targeted in a single 11{mu}sec turn of the Main Injector. The resulting P-bars are injected into six turns of the Debuncher using a resonant kicker which injects every 21st RF bucket The result is that every 3rd RF bucket in the Debuncher is occupied. After an h=30 rotation in the Debuncher, ESME simulations indicate a final momentum spread of {plus_minus}0.25%. This is comparable to the current momentum spread after debunching. It is superior to the momentum spreads of {plus_minus}1.2% and {plus_minus}2% which would be produced by the Compressor Ring and Linear Debuncher.

An analysis is presented of the direct radiation exposures and dose rates to personnel from assumed quantities of radioactive grout, and Double Shell Tank (DST) waste feed. This analysis was based on filling four disposal vaults per year. Whole body doses were analyzed for occupational workers assigned to the Grout Treatment Facility (GTF). The study makes assumptions that must be met by the facility. Otherwise, the GTF will meet all DOE and WHC direct radiation exposure criteria. This analysis will be published in the Grout Final Safety Analysis Report (FSAR).

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Phase space matching errors when transfering a beam from one circular accelerator to another.

The effect of thermal aging on tensile properties of cast stainless steels during service in light water reactors has been evaluated. Tensile data for several experimental and commercial heats of cast stainless steels are presented. Thermal aging increases the tensile strength of these steels. The high-C Mo-bearing CF-8M steels are more susceptible to thermal aging than the Mo-free CF-3 or CF-8 steels. A procedure and correlations are presented for predicting the change in tensile flow and yield stresses and engineering stress-vs.-strain curve of cast stainless steel as a function of time and temperature of service. The tensile properties of aged cast stainless steel are estimated from known material information, i.e., chemical composition and the initial tensile strength of the steel. The correlations described in this report may be used for assessing thermal embrittlement of cast stainless steel components.

Error correction coils are planned for the TPX (Tokamak Plasma Experiment) in order to avoid error field induced locked modes and disruption. The FT (Fix Tokamak) code is used to evaluate the ability of these correction coils to remove islands caused by symmetry breaking magnetic field errors. The proposed correction coils are capable of correcting a variety of error fields.

Gated, microchannel-plate-based (MCP) framing cameras are increasingly used worldwide for x-ray imaging of subnanosecond laser-plasma phenomena. Large dynamic range (> 1,000) measurements of gain profiles for gated microchannel plates (MCP) are presented. Temporal profiles are reconstructed for any point on the microstrip transmission line from data acquired over many shots with variable delay. No evidence for significant pulse distortion by voltage reflections at the ends of the microstrip is observed. The measured profiles compare well to predictions by a time-dependent discrete dynode model down to the 1% level. The calculations do overestimate the contrast further into the temporal wings. The role of electron transit time dispersion in limiting the minimum achievable gate duration is then investigated by using variable duration flattop gating pulses. A minimum gate duration of 50 ps is achieved with flattop gating, consistent with a fractional transit time spread of {approx} 15%.

The sampling and analytical needs associated with the 51 Hanford Site underground storage tanks classified on one or more of the four Watch Lists (ferrocyanide, organic, flammable gas, and high heat), and the safety screening of all 177 tanks have been identified through the Data Quality Objective (DQO) process. DQO`s identify information needed by a program group in the Tank Waste Remediation System concerned with safety issues, regulatory requirements, or the transporting and processing of tank waste. This Tank Characterization Plan will identify characterization objectives for Tank BY-111 pertaining to sample collection, sample preparation and analysis, and laboratory analytical evaluation and reporting requirements. In addition, an estimate of the current contents and status of the tank is given.

This document contains the inspection plan for the <90 day dangerous/mixed waste storage areas and satellite accumulation areas at B Plant Complex. This inspection plan is designed to comply with all applicable federal, state and US Department of Energy-Richland Operations Office training requirements. In particular, the requirements of WAC 173-303 ``Dangerous Waste Regulations`` are met by this inspection plan. This inspection plan is designed to provide B Plant Complex with the records and documentation showing that the waste storage and handling program is in compliance with applicable regulations. The plan also includes the requirements for becoming a qualified inspector of waste storage areas and the responsibilities of various individuals and groups at B Plant Complex.

This document shows the general layout, and gives a part description for the weight/balance test equipment. This equipment will aid in the regulation of the leachate loading of tanker trucks. The report contains four drawings with part specifications. The leachate originates from lined trenches.

The objective of this program is the experimental study of interactions of low energy, highly charged ions with other atomic species. The Cornell superconducting solenoid, cryogenic electron beam ion source CEBIS designed and built in our laboratory is the major piece of apparatus used in these investigations. This progress report describes the work accomplished during the period April 16, 1994 and August 1, 1994. This includes both finished experiments and preparatory work for planned future experiments using the source. During this time, we have completed measurements of the angular distributions and energy gains in Ar{sup q+} (11{le}q{le}14) on Ar collisions at 72 qeV laboratory energy. In particular, energy gain spectra at different laboratory scattering angles were obtained for Ar({sup q-1}){sup +} projectiles, i.e. projectiles whose final charge state had decreased by one unit. The experimental technique used, and the method of analysis are described elsewhere. The raw spectra are similar to those observed for Ar{sup 8+} and Ar{sup l0+} on Ar at comparable energies, as well as those described in the last progress report for Ar{sup l2+} on Ar.

Puncturing of aerosol cans is performed in the Waste Receiving and Processing Facility Module 1 (WRAP 1) process as a requirement of the waste disposal acceptance criteria for both transuranic (TRU) waste and low-level waste (LLW). These cans have contained such things as paints, lubricating oils, paint removers, insecticides, and cleaning supplies which were used in radioactive facilities. Due to Westinghouse Hanford Company (WHC) Fire Protection concerns of the baseline system`s fire/explosion proof characteristics, a study was undertaken to compare the baseline system`s design to commercially available puncturing devices. While the study found no areas which might indicate a risk of fire or explosion, WHC Fire Protection determined that the puncturing system must have a demonstrated record of safe operation. This could be obtained either by testing the baseline design by an independent laboratory, or by substituting a commercially available device. As a result of these efforts, the commercially available Aerosolv can puncturing device was chosen to replace the baseline design. Two concerns were raised with the system. Premature blinding of the coalescing/carbon filter, due to its proximity to the puncture and draining operation; and overpressurization of the collection bottle due to its small volume and by blinding of the …

This document identifies the essential and supporting engineering drawings for the Central Waste Complex (CWC). The purpose of the document is to describe the criteria used to identify and the plan for updating and maintaining their accuracy. This document supports Engineering Practices (EP) 1.3 and 2.2. This revision includes drawings that were not included in the original revision and updates our upgrade plans. Information presented describes the implementation plan of the essential drawing system. Because the accuracy of many of the essential and support drawings is in question, a major effort is required to upgrade them. Solid Waste Engineering Services is providing the design and drawing effort with technical input from the CWC Cognizant Engineer.

The decision whether or not to remove the organic layer from Waste Tank 241-C-103 was deferred until May, 1995. The following restart plan was prepared for removal of the organic if the decision is to remove the organic from the waste tank 241-C-103.

This report documents the chemical compatibility of waste types within tanks 241-C-106, 241-AY-101, and 241-AY-102. This information was compiled to facilitate the transfer of tank C-106 waste to tank AY-102 utilizing supernatant from AY-101 as the sluicing medium. This document justifies that no chemical compatibility safety issues currently understood, or theorized from thermodynamic modeling, will result from the intended sluice transfer operation.

This publication contains the 1993 survey results of the ``Annual Fuel Oil and Kerosene, Sales Report`` (Form EIA-821). This is the fifth year that the survey data have appeared in a separate publication. Prior to the 1989 report, the statistics appeared in the Petroleum Marketing Annual (PMA) for reference year 1988 and the Petroleum Marketing Monthly (PMM) for reference years 1984 through 1987. The 1993 edition marks the 10th annual presentation of the results of the ongoing ``Annual Fuel Oil and Kerosene Sales Report`` survey. Except for the kerosene and on-highway diesel information, data presented in Tables 1 through 12 (Sales of Fuel Oil and Kerosene) present results of the EIA-821 survey. Tables 13 through 24 (Adjusted Sales of Fuel Oil and Kerosene) include volumes that are based on the EIA-821 survey but have been adjusted to equal the products supplied volumes published in the Petroleum Supply Annual (PSA).

This document provides direction for the conduct of business in Building 305 for cold testing tools and equipment. The Cold Test Facility represents a small portion of the overall building, and as such, the work instructions already implemented in the 305 Building will be utilized. Specific to the Cold Test there are three phases for the tools and equipment as follows: 1. Development and feature tests of sludge/fuel characterization equipment, fuel containerization equipment, and sludge containerization equipment to be used in K-Basin. 2. Functional and acceptance tests of all like equipment to be installed and operated in K-Basin. 3. Training and qualification of K-Basin Operators on equipment to be installed and operated in the Basin.