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45-Day safety screen results for tank 241-U-202, push mode, cores 75 and 78 (open access)

45-Day safety screen results for tank 241-U-202, push mode, cores 75 and 78

This document is a report of the analytical results for samples collected from the radioactive wastes in Tank 241-U-202 at the Hanford Reservation. Core samples were collected from the solid wastes in the tank and underwent safety screening analyses including differential scanning calorimetry, thermogravimetric analysis, and total alpha analysis. Results indicate that no safety screening notification limits were exceeded.
Date: May 5, 1995
Creator: Jo, J.
Object Type: Report
System: The UNT Digital Library
45-Day safety screen results for tank 241-U-203, push mode, cores 79 and 80 (open access)

45-Day safety screen results for tank 241-U-203, push mode, cores 79 and 80

Two one-segment core samples from tank 241-U-203 (U-203) were received by the 222-S Laboratories and underwent safety screening analysis, consisting of differential scanning calorimetry (DSC), thermogravimetric analysis (TGA), and total alpha activity. In addition to the safety screening requirements, inductively coupled plasma (ICP) spectrographic analysis for lithium was performed to determine the extent of hydrostatic head fluid contamination during the sampling event. No notification limits were exceeded for these analyses.
Date: May 5, 1995
Creator: Schreiber, R. D.
Object Type: Report
System: The UNT Digital Library
45-day safety screen results for tank 241-U-204, push mode, cores 81 and 82 (open access)

45-day safety screen results for tank 241-U-204, push mode, cores 81 and 82

This is the 45-Day report for the fiscal year 1995 tank 241-U-204 (U-204) push-mode characterization effort. Included are a summary of analytical results and copies of the differential scanning calorimetry (DSC) and thermogravimetric analysis (TGA) scans. Core samples 81 and 82 from tank U-204, obtained by the push-mode core sampling method, were received by the 222-S Laboratories. Each core consisted of only one segment. Both core samples and the field blank were extruded, subsampled, and analyzed in accordance with Reference 1. Drainable liquids and the field blank were analyzed at the segment level for energetics by DSC, percent water by TGA, and total organic carbon (TOC) by furnace oxidation. In addition, the presence or absence of any separable, presumably organic, layer in drainable liquid samples was noted and none was observed. The solids were analyzed directly at the half segment level for energetics by DSC, percent water by TGA, and TOC by persulfate oxidation. Total alpha activity was determined on fusion digestions of the sludge subsamples. No immediate notifications were necessary on samples from cores 81 or 82.
Date: May 17, 1995
Creator: Bell, Kevin E.
Object Type: Report
System: The UNT Digital Library
The 50 MeV Beam Test Facility at LBL (open access)

The 50 MeV Beam Test Facility at LBL

A new beam line, expected to be built by September 1993, will transport the 50 MeV electron beam from the ALS LINAC into an experimental area to support various R&D activities in the Center for Beam Physics at LBL. A variety of experiments are planned involving the interaction of such a relativistic electron beam with plasmas (plasma focusing), laser beams (generation of femtosecond X-ray pulses) and electromagnetic cavities (Crab cavities etc....). The beam line is designed using the measured emittance and Twiss parameters of the ALS linac. It accommodates the different requirements of the various experiments on the electron beam properties (charge, energy, pulse length) and on the handling of the beam before and after the interaction point. Special attention has also been given to incorporate diagnostics for measuring the beam properties (such as the electron energy, bunch length and charge) needed in the interpretation of the experiments.
Date: May 1, 1993
Creator: Leemans, W.; Behrsing, G.; Kim, K. J.; Krupnick, J.; Matuk, C.; Selph, F. et al.
Object Type: Article
System: The UNT Digital Library
50 Watt Recooler ASME Boiler Code Calculations (open access)

50 Watt Recooler ASME Boiler Code Calculations

This Report contains ASME Boiler and Pressure Vessel code Calculations for the RHIC 50 watt recooler.
Date: May 1995
Creator: DeLalio, J.
Object Type: Report
System: The UNT Digital Library
53 MHz beam loading compensation for slip stacking in the Fermilab Main Injector (open access)

53 MHz beam loading compensation for slip stacking in the Fermilab Main Injector

Recently In-Phase and Quadrature (I&Q) was added to both the 53 MHz Feedback and Feedforward Beam Loading Compensation for Slip Stacking in the Fermilab Main Injector. With 53 MHz Feedback, we can now turn the 18 Radio Frequency (RF) Stations off down to below 100 V. In using I&Q on Feedforward, beam loading compensation to the beam on both the upper and lower frequencies of Slip Stacking can be applied as we slip the beam. I&Q theory will be discussed.
Date: May 1, 2005
Creator: Dey, J. & Kourbanis, I.
Object Type: Article
System: The UNT Digital Library
53 MHZ Feedforward beam loading compensation in the Fermilab main injector (open access)

53 MHZ Feedforward beam loading compensation in the Fermilab main injector

53 MHz feedforward beam loading compensation is crucial to all operations of the Main Injector. Recently a system using a fundamental frequency down converter mixer, a digital bucket delay module and a fundamental frequency up converter mixer were used to produce a one-turn-delay feedforward signal. This signal was then combined with the low level RF signal to the cavities to cancel the transient beam induced voltage. During operation they have shown consistently over 20 dB reduction in side-band voltage around the fundamental frequency during Proton coalescing and over 14 dB in multi-batch antiproton coalescing.
Date: May 19, 2003
Creator: al., Joseph E Dey et
Object Type: Article
System: The UNT Digital Library
60-day safety screen results and final report for tank 241-C-111, auger samples 95-Aug-002, 95-Aug-003, 95-Aug-016, and 95-Aug-017 (open access)

60-day safety screen results and final report for tank 241-C-111, auger samples 95-Aug-002, 95-Aug-003, 95-Aug-016, and 95-Aug-017

This report presents the details of the auger sampling events for underground waste tank C-111. The samples were shipped to the 222-S laboratories were they underwent safety screening analysis and primary ferricyanide analysis. The samples were analyzed for alpha total, total organic carbon, cyanide, Ni, moisture, and temperature differentials. The results of this analysis are presented in this document.
Date: May 30, 1995
Creator: Rice, A.D.
Object Type: Report
System: The UNT Digital Library
60-day safety screen results for tank 241-BY-106, rotary mode, cores 64 and 65 (open access)

60-day safety screen results for tank 241-BY-106, rotary mode, cores 64 and 65

Core samples 64 and 65 from tank BY-106, obtained by rotary-mode core sampling, were received by the 222-S Laboratories. Differential scanning calorimetry and thermogravimetric analysis were carried out.
Date: May 1, 1995
Creator: Bell, Kevin E.
Object Type: Report
System: The UNT Digital Library
80 and 100 Meter Wind Energy Resource Potential for the United States (Poster) (open access)

80 and 100 Meter Wind Energy Resource Potential for the United States (Poster)

Accurate information about the wind potential in each state is required for federal and state policy initiatives that will expand the use of wind energy in the United States. The National Renewable Energy Laboratory (NREL) and AWS Truewind have collaborated to produce the first comprehensive new state-level assessment of wind resource potential since 1993. The estimates are based on high-resolution maps of predicted mean annual wind speeds for the contiguous 48 states developed by AWS Truewind. These maps, at spatial resolution of 200 meters and heights of 60 to 100 meters, were created with a mesoscale-microscale modeling technique and adjusted to reduce errors through a bias-correction procedure involving data from more than 1,000 measurement masts. NREL used the capacity factor maps to estimate the wind energy potential capacity in megawatts for each state by capacity factor ranges. The purpose of this presentation is to (1) inform state and federal policy makers, regulators, developers, and other stakeholders on the availability of the new wind potential information that may influence development, (2) inform the audience of how the new information was derived, and (3) educate the audience on how the information should be interpreted in developing state and federal policy initiatives.
Date: May 1, 2010
Creator: Elliott, D.; Schwartz, M.; Haymes, S.; Heimiller, D.; Scott, G.; Flowers, L. et al.
Object Type: Article
System: The UNT Digital Library
94-1 Research and Development Project Lead laboratory support. Status report, October 1--December 31, 1995 (open access)

94-1 Research and Development Project Lead laboratory support. Status report, October 1--December 31, 1995

This is a quarterly progress report of the 94-1 Research and Development Lead Laboratory Support Technical Program Plan for the first quarter of FY 1996. The report provides details concerning descriptions, DOE-complex-wide material stabilization technology needs, scientific background and approach, progress, benefits to the DOE complex, and collaborations for selected subprojects. An executive summary and report on end-of-quarter spending is included.
Date: May 1, 1996
Creator: Dinehart, M.
Object Type: Report
System: The UNT Digital Library
100-300 Area program meeting of May 7, 1946 (open access)

100-300 Area program meeting of May 7, 1946

None
Date: May 7, 1946
Creator: Kidder, C. P.
Object Type: Report
System: The UNT Digital Library
100 Area and 300 Area Component of the RCBRA Fall 2005 Data Compilation (open access)

100 Area and 300 Area Component of the RCBRA Fall 2005 Data Compilation

The purpose of this report is to provide a brief description of the sampling approaches, a description of the samples collected, and the results for the Fall 2005 sampling event. This report presents the methods and results of the work to support the 100 Area and 300 Area Component of the River Corridor Baseline Risk Assessment.
Date: May 30, 2006
Creator: Queen, J.M.
Object Type: Report
System: The UNT Digital Library
100 Area excavation treatability study data validation report (open access)

100 Area excavation treatability study data validation report

This report presents the results of sampling and chemical analyses at Hanford Reservation. The samples were analyzed by Thermo-Analytic Laboratories and Roy F. Weston Laboratories using US Environmental Protection Agency CLP protocols. Sample analyses included: volatile organics; semivolatile organics; inorganics; and general chemical parameters. The data from the chemical analyses were reviewed and validated to verify that reported sample results were of sufficient quality to support decisions regarding remedial actions performed at this site.
Date: May 19, 1994
Creator: Frain, J. M.
Object Type: Report
System: The UNT Digital Library
100 Area Excavation Treatability Test Plan (open access)

100 Area Excavation Treatability Test Plan

This test plan documents the requirements for a treatability study on field radionuclide analysis and dust control techniques. These systems will be used during remedial actions involving excavation. The data from this treatability study will be used to support the feasibility study (FS) process. Development and screening of remedial alternatives for the 100 Area, using existing data, have been completed and are documented in the 100 Area Feasibility Study, Phases 1 and 2 (DOE-RL 1992a). Based on the results of the FS, the Treatability Study Program Plan (DOE-RL 1992b) identifies and prioritizes treatability studies for the 100 Area. The data from the treatability study program support future focused FS, interim remedial measures (IRM) selection, operable unit final remedy selection, remedial design, and remedial actions. Excavation is one of the high-priority, near-term, treatability study needs identified in the program plan (DOE-RL 1992b). Excavation of contaminated soils and buried solid wastes is included in several of the alternatives identified in the 100 Area FS. Although a common activity, excavation has only been used occasionally at the Hanford Site for waste removal applications.
Date: May 1, 1993
Creator: unknown
Object Type: Report
System: The UNT Digital Library
100 Area groundwater biodenitrification bench-scale treatability study procedures (open access)

100 Area groundwater biodenitrification bench-scale treatability study procedures

This document describes the methodologies and procedures for conducting the bench-scale biodenitrification treatability tests at Pacific Northwest Laboratory{sup a} (PNL). Biodenitrification is the biological conversion of nitrate and nitrite to gaseous nitrogen. The tests will use statistically designed batch studies to determine if biodenitrification can reduce residual nitrate concentrations to 45 mg/L, the current maximum contaminant level (MCL). These tests will be carried out in anaerobic flasks with a carbon source added to demonstrate nitrate removal. At the pilot scale, an incremental amount of additional carbon will be required to remove the small amount of oxygen present in the incoming groundwater. These tests will be conducted under the guidance of Westinghouse Hanford Company (WHC) and the 100-HR-3 Groundwater Treatability Test Plan (DOE/RL-92-73) and the Treatability Study Program Plan (DOE/RL-92-48) using groundwater from 100-HR-3. In addition to the procedures, requirements for safety, quality assurance, reporting, and schedule are given. Appendices include analytical procedures, a Quality Assurance Project Plan, a Health and Safety Plan, and Applicable Material Data Safety Sheets. The procedures contained herein are designed specifically for the 100-HR-3 Groundwater Treatability Test Plan, and while the author believes that the methods described herein are scientifically valid, the procedures should not be …
Date: May 1, 1993
Creator: Peyton, B. M. & Martin, K. R.
Object Type: Report
System: The UNT Digital Library
100 Areas: (For technical progress letter No. 95), April 23--29 (open access)

100 Areas: (For technical progress letter No. 95), April 23--29

Reported are: physics (B Pile, D Pile, F Pile, general physics); and water, corrosion and engineering (process water control and pressure drop studies, corrosion, graphite expansion).
Date: May 3, 1946
Creator: Jordan, W. E.
Object Type: Report
System: The UNT Digital Library
100 Areas: (For Technical Progress Letter No. 96), April 30--May 6 (open access)

100 Areas: (For Technical Progress Letter No. 96), April 30--May 6

None
Date: May 10, 1946
Creator: Jordan, W. E.
Object Type: Report
System: The UNT Digital Library
100 Areas: (For Technical Progress Letter No. 97), May 7--13 (open access)

100 Areas: (For Technical Progress Letter No. 97), May 7--13

Physics information for the D and F piles is presented. Thermal conductivity, reactivity, and irradiation levels are included. Concerning the cooling systems: process water control, pressure drip studies, purging studies, corrosion, and gun barrel clearance of expanded graphite are discussed. (GHH)
Date: May 17, 1946
Creator: Jordan, W. E.
Object Type: Report
System: The UNT Digital Library
100 Areas: (For technical progress letter No. 98), May 14--May 20 (open access)

100 Areas: (For technical progress letter No. 98), May 14--May 20

This technical progress report details 100 Area activities for the time period of May 14 through May 20, 1946.
Date: May 24, 1946
Creator: Jordan, W. E.
Object Type: Report
System: The UNT Digital Library
100 Areas: (For technical progress letter No. 99), May 21--May 27 (open access)

100 Areas: (For technical progress letter No. 99), May 21--May 27

This report details 100 Area reactor operation for the time period of May 21 through May 27, 1946.
Date: May 31, 1946
Creator: Jordan, W. E.
Object Type: Report
System: The UNT Digital Library
100 Areas Technical Activities Report - Engineering, April 1947 (open access)

100 Areas Technical Activities Report - Engineering, April 1947

This is the first of a series of monthly reports covering details of the work of the Engineering Group of the Pile Technology Section of the Technical Department. The monthly Slug Inspection Report is being discontinued as a separate document and is being incorporated in this group report. Included is work on corrosion and blistering; graphite expansion; and irradiation studies.
Date: May 21, 1947
Creator: Woods, W. K.
Object Type: Report
System: The UNT Digital Library
100 Areas technical activities report: Physics, April 1947 (open access)

100 Areas technical activities report: Physics, April 1947

This monthly report details Physics Department 100 Area technical activities for the month of April 1947.
Date: May 20, 1947
Creator: Gast, P. F.
Object Type: Report
System: The UNT Digital Library
100-B unit purge May 20, 1945 (open access)

100-B unit purge May 20, 1945

None
Date: May 28, 1945
Creator: Dahlen, P. A.
Object Type: Report
System: The UNT Digital Library