This report includes shop acceptance test results. The test was performed prior to installation at tank AZ-101. Both the camera system and camera purge system were originally sought and procured as a part of initial waste retrieval project W-151.

The project undertaken by the Salix Consortium is a multi-phased, multi-partner endeavor. Phase 1 focused on initial development and testing of the technology and forging the necessary agreements to demonstrate commercial willow production. The Phase 1 objectives have been successfully completed: preparing design plans for 2 utility pulverized coal boilers for 20 MW of biopower capacity; developing fuel supply plans for the project with a goal of establishing 365 ha (900 ac) of willow; obtaining power production commitments from the power companies for Phase 2; obtaining construction and environmental permits; and developing an experimental strategy for crop production and power generation improvements needed to assure commercial success. The R and D effort also addresses environmental issues pertaining to introduction of the willow energy system.

This document provided the detailed accident analysis to support HNF-3553, Spent Nuclear Fuel Project Final Safety Analysis Report, Annex A, ''Canister Storage Building Final Safety Analysis Report''. All assumptions, parameters, and models used to provide the analysis of the design basis accidents are documented to support the conclusions in the Canister Storage Building Final Safety Analysis Report.

Fueled clads for radioisotope power systems are produced by encapsulating {sup 238}PuO{sub 2} in iridium alloy cups, which are joined at their equators by gas tungsten arc welding. Cracking problems at the girth weld tie-in area during production of the Galileo/Ulysses GPHS capsules led to the development of a first-generation ultrasonic test for girth weld inspection at the Savannah River Plant. A second-generation test and equipment with significantly improved sensitivity and accuracy were jointly developed by the Oak Ridge Y-12 Plant and Westinghouse Savannah River Company for use during the production of Cassini GPHS capsules by the Los Alamos National Laboratory. The test consisted of Lamb wave ultrasonic scanning of the entire girth weld from each end of the capsule combined with a time-of-flight evaluation to aid in characterizing nonrelevant indications. Tangential radiography was also used as a supplementary test for further evaluation of reflector geometry. Each of the 317 fueled GPHS capsules, which were girth welded for the Cassini Program, was subjected to a series of nondestructive tests that included visual, dimensional, helium leak rate, and ultrasonic testing. Thirty-three capsules were rejected prior to ultrasonic testing. Of the 44 capsules rejected by the standard ultrasonic test, 22 were upgraded …

The Pacific Northwest National Laboratory (PNNL) is developing and implementing a customer satisfaction assessment program (CSAP) to assess the quality of research and development provided by the laboratory. This report presents the customer survey component of the PNNL CSAP. The customer survey questionnaire is composed of two major sections: Strategic Value and Project Performance. Both sections contain a set of questions that can be answered with a 5-point Likert scale response. The strategic value section consists of five questions that are designed to determine if a project directly contributes to critical future national needs. The project Performance section consists of nine questions designed to determine PNNL performance in meeting customer expectations. A statistical model for customer survey data is developed and this report discusses how to analyze the data with this model. The properties of the statistical model can be used to establish a gold standard or performance expectation for the laboratory, and then to assess progress. The gold standard is defined using laboratory management input--answers to four questions, in terms of the information obtained from the customer survey: (1) What should the average Strategic Value be for the laboratory project portfolio? (2) What Strategic Value interval should include most …

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A letter report issued by the General Accounting Office with an abstract that begins "Pursuant to a congressional request, GAO reviewed the Health Care Financing Administration's (HCFA) recent efforts to address weaknesses in how the central office and regional offices work together to oversee Medicare contractors, and the continuing management challenges HCFA faces."

This document contains descriptions of Federal Manufacturing and Technologies (FM and T) Metrology capabilities, traceability flow charts, and the measurement uncertainty of each measurement capability. Metrology provides NIST traceable precision measurements or equipment calibration for a wide variety of parameters, ranges, and state-of-the-art uncertainties in laboratories that conform to the requirements of the Department of Energy Development and Production Manual Chapter 8.4, and ANSI/NCSL Z540-1 (equivalent to ISO Guide 25). FM and T Metrology laboratories are accredited by NVLAP for the parameters, ranges, and uncertainties listed in the specific scope of accreditation under NVLAP Lab code 200108-0. These parameters are summarized.

This document identifies the means to determine NPSHa for Hanford waste tanks. It presents the values of vapor pressure and density of Hanford double-shell tank waste as they relate to temperature.

Geophysical methods have been used for characterization of hydrogeologic conditions and/or contaminant distributions at the Hanford site since at least the mid- to late-1940s. A review of these geophysical methods is presented in two parts: 1) shallow surface-based geophysical methods and 2) borehole geophysical-logging methods.

Geophysical methods have been used for characterization of hydrogeologic conditions and/or contaminant distributions at the Hanford site since at least the mid- to late-1940s. A review of these geophysical methods is presented in two parts: (1) shallow surface-based geophysical methods and (2) borehole geophysical-logging methods.

This paper presents a review of geophysical methods used at Hanford in two parts: (1) shallow surface-based geophysical methods and (2) borehole geophysical methods. This review was not intended to be ``all encompassing'' but should represent the vast majority (>90% complete) of geophysical work conducted onsite and aimed at hazardous waste investigations in the vadose zone and/or uppermost groundwater aquifers. This review did not cover geophysical methods aimed at large-scale geologic structures or seismicity and, in particular, did not include those efforts conducted in support of the Basalt Waste Isolation Program. This review focused primarily on the more recent efforts.

This is a summary of the results of my calculations compared to Elisabeth Wolfrum's data on the Vulcan imprint experiments. The material strength makes essentially no difference to the growth of perturbations seeded by the laser imprint. For the low-intensity case (30 J laser energy, beam intensity of 0.5 x 10{sup 12} W/cm{sup 2}) the thin (2 microns) Al foil melts quickly from the front (driven) surface and decompresses quickly from the back surface, so there is actually only a fraction of the foil that is solid and compressed, and then for only a short time. And this solid fraction is not accelerating much during this short time. In particular, the shock (which is at about 250 kbar when it is about half way through the foil) travels entirely through the foil in about 0.25 ns. At 0.3 ns the ablation front is 0.6 {micro}m in from the original position of the front surface, the next 0.6 {micro}m is melted, so only the back 0.8 {micro}m is solid and compressed. This solid portion, though, is not moving much; the place where the imprinted perturbations are growing is back at the ablation front, where the perturbations are clearly growing fluid-like. By …

This report interprets information about the tank answering a series of six questions covering areas such as information drivers, tank history, tank comparisons, disposal implications, data quality and quantity, and unique aspects of the tank.

The thermal analysis examined transient thermal and chemical behavior of the Multi-Canister Overpack (MCO) container for a broad range of cases that represent the Cold Vacuum Drying (CVD) processes. The cases were defined to consider both normal and off-normal operations at the CVD Facility for an MCO with N Reactor spent fuel. This analysis provides the basis for the MCO thermal behavior at the CVD Facility in support of the safety basis documentation.