The purpose of this Acceptance Test Report is to provide documentation for the acceptance testing of the rotary mode core sample trucks 3 and 4, designated as HO-68K-4600 and HO-68K-4647, respectively. This report conforms to the guidelines established in WHC-IP-1026, ``Engineering Practice Guidelines,`` Appendix M, ``Acceptance Test Procedures and Reports.`` Rotary mode core sample trucks 3 and 4 were based upon the design of the second core sample truck (HO-68K-4345) which was constructed to implement rotary mode sampling of the waste tanks at Hanford. Successful completion of acceptance testing on June 30, 1995 verified that all design requirements were met. This report is divided into four sections, beginning with general information. Acceptance testing was performed on trucks 3 and 4 during the months of March through June, 1995. All testing was performed at the ``Rock Slinger`` test site in the 200 West area. The sequence of testing was determined by equipment availability, and the initial revision of the Acceptance Test Procedure (ATP) was used for both trucks. Testing was directed by ICF-KH, with the support of WHC Characterization Equipment Engineering and Characterization Project Operations. Testing was completed per the ATP without discrepancies or deviations, except as noted.

We consider unusual events in the CDF and D0 dilepton+jets sample with very high ET(lepton) and ET(missing). It is possible, but very unlikely, that these events originate from top quark pair production; however, they have characteristics that are better accounted for by decays of supersymmetric quarks with mass in the region of 300 GeV.

This analysis is prepared by the Mined Geologic Disposal System (MGDS) Waste Package Development Department (WPDD) as specified in the Waste Package Implementation Plan (pp. 4-8, 4-11, 4-24, 5-1, and 5-13, Ref. 5.10) and the Waste Package Plan (pp.3-15, 3-17, and 3-24, Ref. 5.9). The design data request addressed herein is: Characterize the preliminary 21 pressurized water reactor (PWR) advanced (A) uncanistered fuel (UCF) waste package (WP) to show that the design is feasible for use in the MGDS environment. The purpose of this analysis is to respond to a concern that the long-term disposal thermal issues for the UCF WP do not preclude UCF WP compatibility with the MGDS. The objective of this analysis is to provide thermal parameter information for the preliminary UCF WP design under nominal MGDS repository conditions. The results are intended to show that the design has a reasonable chance to meet the MGDS design requirements for normal MGDS operation and to provide the required guidance to determining the major design issues for future design efforts. Future design efforts will focus on UCF design changes as further design and operations information becomes available.

This report addresses the ATR power supplies.

During the assembly of major components into the D0 Detector, a transfer bridge was required to move the North-End Calorimeter from the clean room,over the cable bridge and onto the north sidewalk of the assembly hall. This experiment is now at the beginning stages of the next phase, namely the upgrade of this Detector for future physics research. A major piece of this upgrade is the installation of a solenoid magnet into the Central Calorimeter. In order to accomplish this, the South End Calorimeter has to be removed from the detector and the North End Calorimeter must be moved an additional 20-inch from its nominal open position (total 60-inch movement). The South End Calorimeter will be removed from the detector using the equipment designed for its installation. The calorimeter will be staged on the south sidewalk during the installation of the solenoid magnet and the central tracking systems. The North End Calorimeter is moved 60-inch to give more space between calorimeters during magnet, tracker and cable installation work. This movement will allow the calorimeter to remain coupled to the cryo system. However, this movement requires an extension be added to the center beam. This extension will support the rear wheels …

This report revises an August 1995 CRS Report on Women in Congress and identifies the committee assignments, dates of service, and districts of the 176 women Members of Congress.

This report discusses the history of the use of the phrase "In God We Trust" on the national currency, and the constitutional legality of the practice.

Compilation of monthly reports from departments in the city of San Antonio, Texas providing statistics, project updates, and other information about services and activities. This set of reports includes information about permits for March 1996.

This Acceptance Test Report presents the results of the acceptance test performed at the vendor shop on the monitors and control functions of the A-101 Saltwell Pumping PICS skid. This work supports the interim stabilization of tank 241-A-101.

This Acceptance Test Report presents the results of the acceptance test performed at the shop on the monitor and control functions of the AX-101 Saltwell Pumping PICS skid. This work supports the interim stabilization of tank 241-AX-101.

The hydroforming process involves hydraulically forming components by conforming them to the inner contours of a die. These contours can be complex and can often cause the material being formed to be stressed to rupture. Considerable process knowledge and materials modeling expertise is required to design hydroform dies and hydroformed parts that are readily formed without being overly stressed. For this CRADA, materials properties for steel tubes subjected to hydraulic stresses were collected; algorithms were developed which combined the materials properties data with process knowledge; and a user friendly graphical interface was utilized to make the system usable by a design engineer. A prototype hydroforming advisor was completed and delivered to GM. The technical objectives of the CRADA were met allowing for the development of an intelligent design systems, prediction of forming properties related to hydroforming, simulation and modeling of process execution, and design optimization. The design advisor allows a rapid and seamless approach to integration an otherwise enormous and onerous task of analysis and evaluation.

We have used a two step (low and high temperature) strain-annealing process to evolve the two grain boundary character distribution (GBCD) in fully recrystallized oxygen (OFE) copper bar that was forged and rolled. Orientation imaging microscopy (OIM) has been used to characterize the GBCD after each step in the processing. The fraction of special grain boundaries, special fraction was about 70% in the starting recrystallized material. Three different processing conditions were employed: high, moderate, and low temperature. The high temperature process resulted in a reduction in the fraction of special grain boundaries while both of the lower temperature processes resulted in an increase in special fraction up to 85%. Further, the lower temperature processes resulted in average deviation angles from exact misorientation, for special boundaries, that were significantly smaller than observed from the high temperature process. Results indicate the importance of low temperature part of the two-step strain-annealing process in preparing the microstructure for the higher-temperature anneal and commensurate increase in the special fraction.

This document outlines the technical basis for correcting waste tank core samples for water intrusion based on a LiBr tracer.

In 1990 the U.S. Department of Energy (DOE) Office of Technology Development initiated the Light Duty Utility Arm (LDUA) program to support the Consent Order between the State of Idaho, U.S. Department of Energy, and the Environmental Protection Agency that requires ceasing use of the 11 high-level liquid waste (HLLW) storage tanks at the Idaho Chemical Processing Plant (ICPP).

Updated analysis of frequency of waste tank fires due to vehicle/riser accidents.

A shielding analysis of a potential long length contaminated equipment transportation package was completed. The analysis was performed to support the design of the transportation package and external shielding.

The Spent Nuclear Fuel Project was established to develop engineered solutions for the expedited removal, stabilization, and storage of spent nuclear fuel from the K Basins at the U.S. Department of Energy`s Hanford Site in Richland, Washington. A series of analyses have been completed investigating the thermal-hydraulic performance and feasibility of the proposed Hot Conditioning System and process for the Spent Nuclear Fuel Project. The analyses were performed using a series of thermal-hydraulic models that could respond to all process and safety-related issues that may arise pertaining to the Hot Conditioning System. The subject efforts focus on independently investigating, quantifying, and establishing the governing heat production and removal mechanisms, flow distributions within the multi-canister overpack, and performing process simulations for various purge gases under consideration for the Hot Conditioning System, as well as obtaining preliminary results for comparison with and verification of other analyses, and providing technology- based recommendations for consideration and incorporation into the Hot Conditioning System design bases.

This document includes a cassette tape that contains the Hanford specific files that make up the Hanford Site Technical Baseline Database as of May 10, 1996. The cassette tape also includes the delta files that delineate the differences between this revision and revision 3 (April 10, 1996) of the Hanford Site Technical Baseline Database.

This report documents operational controls to be incorporated into the Process Control Plan for Project W-320, Tank 241-C-106(C-106) Sluicing. The controls are based upon various technical analyses regarding prevention of potential hazards formed by uncontrolled releases of flammable gas or steam from the wastes contained within the Waste Retrieval Sluicing System. The retrieval approach calls for the sequenced removal of waste from tank C-106 in volume increments of 25, 000 gallons. A holding or waste monitoring period is specified upon removal of each 25,000 gallon waste volume increment. The waste behavior which must be observed during the monitoring period is stated. These behavioral specifications must be satisfied to allow the retrieval effort to progress to the removal of the next waste volume increment.

This report documents the resolution of industrial health and safety issues regarding potentially hazardous tank vapors in the Hanford 200 Area Tank Farms. It also summarizes the tasks and controls which have been implemented and demonstrates that with the present work controls in place, an unacceptable inhalation risk to workers from tank farm vapors does not exist.

A `White` paper was written on the High Heat Generation Safety Issue in Tank 241-C-106. The issue is if tank 241-C-106 should start leaking, the lack of alternative cooling methods will require continued addition of water and thereby possibly increase the amount of leakage to the ground. If the current methods of cooling the tank are stopped, the sludge and concrete structure will heat to temperatures greater than established limits and may cause structural damage, leading to dome collapse and possibly an unacceptable radioactive release to the environment. Potential approaches to the resolution of this issue were evaluated, and waste retrieval by sluicing and transfer to a double-shell tank was selected. The paper gives background information on the tank and an assessment of the issue and its resolution, with references to support the paper.

This document is a plan that identifies the information needed to address relevant issues concerning short-term and long-term storage and long-term management of single-shell tank 241-U-103.

This document is a plan that identifies the information needed to address relevant issues concerning short-term and long-term storage and long-term management of single-shell tank 241-A-104.

This document is a plan that identifies the information needed to address relevant issues concerning short-term and long-term storage and long-term management of single-shell tank 241-SX-104.