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12,691
Congressional Research Service Reports
3,663
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2,104
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1,074
Government Accountability Office Reports
653
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398
Texas State Publications
380
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93
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19,723 Matching Results
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100-F unit purge May 20, 1945
None
Date:
May 29, 1945
Creator:
Dahlen, P. A.
System:
The UNT Digital Library
The 100 largest industrial corporations in the U.S ranked by sales in 1970
This report ranks the 100 largest industrial corporations in the U.S by sales in 1970.
Date:
May 24, 1971
Creator:
Kline, Linda S.
System:
The UNT Digital Library
100-NR-2 Apatite Treatability Test: An update on Barrier Performance
This report updates a previous report covering the performance of a permeable reactive barrier installed at 100N. In this report we re-evaluate the results after having an additional year of performance monitoring data to incorporate.
Date:
May 1, 2011
Creator:
Fritz, Brad G.; Vermeul, Vincent R.; Fruchter, Jonathan S.; Szecsody, James E. & Williams, Mark D.
System:
The UNT Digital Library
100-Watt Curium-242 Fueled Thermoelectric Generator--Conceptual Design. SNAP Subtask 5.7 Final Report
A thermoelectric generator which produces 100 watts of electrical power continuously over a six-month operational life in a space environment was designed. It employs the heat produced by the decay of Cm/sup 24/ as the source of power. Uniform output over the operational life of the generator is accomplished by means of a thermally actuated shutter which maintains the hot junction temperature of the thermoelectric conventer at a constunt figure by varying the amount of surplus heat which is radiated directly to space from the heat source. The isotopic heat source is designed to safely contain the Cm/sup 242/ under conditions of launch pad abont and rocket failure, but to burn up upon re-entry to the earth's atmosphere from orbital velocity. (W.L.H.)
Date:
May 1, 1960
Creator:
Weddell, J. B. & Bloom, J.
System:
The UNT Digital Library
105-DR Large Sodium Fire Facility Closure Plan. Revision 1
The Hanford Site, located northwest of the city of Richland, Washington, houses reactors, chemical-separation systems, and related facilities used for the production of special nuclear materials, and activities associated with nuclear energy development. The 105-DR Large Sodium Fire Facility (LSFF), which was in operation from about 1972 to 1986, was a research laboratory that occupied the former ventilation supply room on the southwest side of the 105-DR Reactor facility. The LSFF was established to provide a means of investigating fire and safety aspects associated with large sodium or other metal alkali fires in the liquid metal fast breeder reactor (LMFBR) facilities. The 105-DR Reactor facility was designed and built in the 1950`s and is located in the 100-D Area of the Hanford Site. The building housed the 105-DR defense reactor, which was shut down in 1964. The LSFF was initially used only for engineering-scale alkali metal reaction studies. In addition, the Fusion Safety Support Studies program sponsored intermediate-size safety reaction tests in the LSFF with lithium and lithium lead compounds. The facility has also been used to store and treat alkali metal waste, therefore the LSFF is subject to the regulatory requirements for the storage and treatment of dangerous waste. …
Date:
May 1, 1993
Creator:
unknown
System:
The UNT Digital Library
105-K Basin 1999 Debris Report
The purpose of this report is to describe the quantities, character, and management (e.g., segregation and management after removal) of 105-K Basins debris managed in calendar year 1999.
Date:
May 1, 2000
Creator:
WATSON, D.J.
System:
The UNT Digital Library
105 K East isolation barrier acceptance analysis report
The objective of this document is to report and interpret the findings of the isolation barrier acceptance tests performed in 105KE/100K. The tests were performed in accordance with the test plan (McCracken 1995c) and acceptance test procedure (McCracken 1995a). The test report (McCracken 1995b) contains the test data. This document compares the test data (McCracken 1995b) against the criteria (McCracken 1995a, c). A discussion of the leak rate analytical characterization (Irwin 1995) describes how the flow characteristics and the flow rate will be determined using the test data from the test report (McCracken 1995b). The barriers must adequately control the leakage from the main basin to the discharge chute to less than the 1,500 gph (5,680 lph) Safety Analysis Report (SAR 1994) limit.
Date:
May 31, 1995
Creator:
McCracken, K. J. & Irwin, J. J.
System:
The UNT Digital Library
105 K West Cask Transportation Facility Modification Acceptance for Beneficial Use Checklist Project A.5 and A.6
The CTFM Subproject of the SNF Project has prepared an ABU checklist per SNF Administrative Procedure (AP) CS-6-019. This checklist identifies the essential documentation needed to operate and maintain the 105 KW CTFM/CLS Structures, Systems, and Components (SSCs) when ownership is transferred from the CTFM Subproject to K Basins Operations. Approval of this supporting document demonstrates an agreement by the approvers as to the documentation required at turnover.
Date:
May 5, 2000
Creator:
HARRIS, D.L.
System:
The UNT Digital Library
105-KE Basin isolation barrier leak rate test analytical development. Revision 1
This document provides an analytical development in support of the proposed leak rate test of the 105-KE Basin. The analytical basis upon which the K-basin leak test results will be used to determine the basin leakage rates is developed in this report. The leakage of the K-Basin isolation barriers under postulated accident conditions will be determined from the test results. There are two fundamental flow regimes that may exist in the postulated K-Basin leakage: viscous laminar and turbulent flow. An analytical development is presented for each flow regime. The basic geometry and nomenclature of the postulated leak paths are denoted.
Date:
May 9, 1995
Creator:
Irwin, J. J.
System:
The UNT Digital Library
106-AN grout pilot-scale test HGTP-93-0501-02
The Grout Treatment Facility (GTF) at Hanford, Washington will process the low-level fraction of selected double-shell tank (DST) wastes into a cementitious waste form. This facility, which is operated by Westinghouse Hanford Company (WHC), mixes liquid waste with cementitious materials to produce a waste form that immobilizes hazardous constituents through chemical reactions and/or microencapsulation. Over 1,000,000 gal of Phosphate/Sulfate Waste were solidified in the first production campaign with this facility. The next tank scheduled for treatment is 106-AN. After conducting laboratory studies to select the grout formulation, part of the normal formulation verification process is to conduct tests using the 1/4-scale pilot facilities at the Pacific Northwest Laboratory (PNL). The major objectives of these pilot-scale tests were to determine if the proposed grout formulation could be processed in the pilot-scale equipment and to collect thermal information to help determine the best way to manage the grout hydration heat.
Date:
May 1, 1993
Creator:
Bagaasen, L. M.
System:
The UNT Digital Library
AN-107 (C) Simulant Bench-Scale LAW Evaporation with Organic Regulatory Analysis
The overall objective of this work is to develop preliminary operating data including expected concentration endpoints using a C waste envelope simulant. The data is to be used for the preliminary Hanford RPP flow sheet development and LAW Melter Feed Evaporator design.
Date:
May 15, 2001
Creator:
Saito, H.H.
System:
The UNT Digital Library
200 Area monthly report No. 4, April 1966
This monthly report details activities of the 200 Area for the month of April 1966.
Date:
May 10, 1966
Creator:
Christy, J. T.
System:
The UNT Digital Library
200 Area Treated Effluent Disposal Facility (TEDF) Effluent Sampling and Analysis Plan
This Sampling and Analysis Plan (SAP) has been developed to comply with effluent monitoring requirements at the 200 Area Treated Effluent Disposal Facility (TEDF), as stated in Washington State Waste Discharge Permit No. ST 4502 (Ecology 2000). This permit, issued by the Washington State Department of Ecology (Ecology) under the authority of Chapter 90.48 Revised Code of Washington (RCW) and Washington Administrative Code (WAC) Chapter 173-216, is an April 2000 renewal of the original permit issued on April 1995.
Date:
May 18, 2000
Creator:
Brown, M. J.
System:
The UNT Digital Library
T-200 series tank concentration predictions
Of the 177 tanks containing nuclear waste at the Hanford site, 68 have not been characterized based on sampling information. It may be possible to characterize 34 of the 68 unsampled tanks by using information from other sources, such as the Tank Characterization Database (TCD) and the Historical Tank Content Estimates (HTCE). This report lists predicted concentrations of 17 analytes along with the associated estimates of uncertainty for the T-200 series tanks (T-201, T-202, T-203, T-204), based on historical data and sample results from tanks other than the T-200 tanks. The main benefits of reduced sampling are reduced cost, reduced time to achieve acceptable characterization, and reduced exposure of sampling personnel. However, in order to characterize a tank on the basis of reducing sampling, the predicted tank averages and the associated uncertainties must be technically credible and useful. The objective of this report is to describe the approach to predict (without a sample) or estimate (from a single sample) the concentrations of the 17 analytes for the T-200 tanks. Sampling of these tanks and laboratory analysis of the samples is currently under way (sampling is scheduled for 03/27/97 through 04/21/97). This report briefly describes the statistical prediction techniques.
Date:
May 1, 1997
Creator:
Engel, D. W.; Remund, K. M.; Chen, G.; Ferryman, T. A.; Daly, D. S.; Hartley, S. A. et al.
System:
The UNT Digital Library
215 MWD/Ton batch size limits and control in the Bismuth Phosphate Plant
None
Date:
May 24, 1954
Creator:
Browne, W. G.
System:
The UNT Digital Library
221-U Facility concrete and reinforcing steel evaluations specification for the canyon disposition initiative (CDI)
This describes a test program to establish the in-situ material properties of the reinforced concrete in Building 221-U for comparison to the original design specifications. Field sampling and laboratory testing of concrete and reinforcing steel structural materials in Building 221-U for design verification will be undertaken. Forty seven samples are to be taken from radiologically clean exterior walls of the canyon. Laboratory testing program includes unconfined compressive strength of concrete cores, tensile strength of reinforcing steel, and petrographic examinations of concrete cores taken from walls below existing grade.
Date:
May 28, 1998
Creator:
Baxter, J. T.
System:
The UNT Digital Library
236-Z and 291-Z Vacuum Pump System Flow Determination
None
Date:
May 16, 2000
Creator:
ELLINGSON, S.D.
System:
The UNT Digital Library
236-Z and 291-Z Vacuum Pump System Pressure Drop Analysis for Line Size Selection
None
Date:
May 16, 2000
Creator:
ELLINGSON, S.D.
System:
The UNT Digital Library
241-AZ Farm Annulus Extent of Condition Baseline Inspection
This report provides the results of the comprehensive annulus visual inspection for tanks 241- AZ-101 and 241-AZ-102 performed in fiscal year 2013. The inspection established a baseline covering about 95 percent of the annulus floor for comparison with future inspections. Any changes in the condition are also included in this document.
Date:
May 15, 2013
Creator:
Engeman, Jason K.; Girardot, Crystal L. & Vazquez, Brandon J.
System:
The UNT Digital Library
241-SY-101 data acquisition and control system (DACS) operator interface upgrade operational test report
This procedure provides instructions for readiness of the first portion of the upgraded 241-SY-101 Data Acquisition and Control System (DACS) computer system to provide proper control and monitoring of the mitigation mixer pump and instrumentation installed in the 241-SY-101 underground storage tank will be systematically evaluated by the performance of this procedure.
Date:
May 11, 1999
Creator:
Ermi, A. M.
System:
The UNT Digital Library
242-A Control System device logic software documentation. Revision 2
A Distributive Process Control system was purchased by Project B-534. This computer-based control system, called the Monitor and Control System (MCS), was installed in the 242-A Evaporator located in the 200 East Area. The purpose of the MCS is to monitor and control the Evaporator and Monitor a number of alarms and other signals from various Tank Farm facilities. Applications software for the MCS was developed by the Waste Treatment System Engineering Group of Westinghouse. This document describes the Device Logic for this system.
Date:
May 19, 1995
Creator:
Berger, J. F.
System:
The UNT Digital Library
242-A Evaporator/plutonium uranium extraction (PUREX) effluent treatment facility (ETF) nonradioactive air emission test report
This report shows the methods used to test the stack gas outlet concentration and emission rate of Volatile Organic Compounds as Total Non-Methane Hydrocarbons in parts per million by volume,grams per dry standard cubic meter, and grams per minute from the PUREX ETF stream number G6 on the Hanford Site. Test results are shown in Appendix B.1.
Date:
May 10, 1996
Creator:
Hill, J. S.
System:
The UNT Digital Library
242-A Evaporator quality assurance plan. Revision 2
The purpose of this quality assurance project plan (Plan) is to provide requirements for activities pertaining to sampling, shipping, and analyses associated with candidate feed tank samples for the 242-A Evaporator project. The purpose of the 242-A Evaporator project is to reduce the volume of aqueous waste in the Double Shell Tank (DST) System and will result in considerable savings to the disposal of mixed waste. The 242-A Evaporator feed stream originates from DSTs identified as candidate feed tanks. The 242-A Evaporator reduces the volume of aqueous waste contained in DSTs by boiling off water and sending the condensate (called process condensate) to the Liquid Effluent Retention Facility (LEPF) storage basin where it is stored prior to treatment in the Effluent Treatment Facility (ETF). The objective of this quality assurance project plan is to provide the planning, implementation, and assessment of sample collection and analysis, data issuance, and validation activities for the candidate feed tanks.
Date:
May 4, 1995
Creator:
Basra, T. S.
System:
The UNT Digital Library
242-A evaporator safety analysis report
This report provides a revised safety analysis for the upgraded 242-A Evaporator (the Evaporator). This safety analysis report (SAR) supports the operation of the Evaporator following life extension upgrades and other facility and operations upgrades (e.g., Project B-534) that were undertaken to enhance the capabilities of the Evaporator. The Evaporator has been classified as a moderate-hazard facility (Johnson 1990). The information contained in this SAR is based on information provided by 242-A Evaporator Operations, Westinghouse Hanford Company, site maintenance and operations contractor from June 1987 to October 1996, and the existing operating contractor, Waste Management Hanford (WMH) policies. Where appropriate, a discussion address the US Department of Energy (DOE) Orders applicable to a topic is provided. Operation of the facility will be compared to the operating contractor procedures using appropriate audits and appraisals. The following subsections provide introductory and background information, including a general description of the Evaporator facility and process, a description of the scope of this SAR revision,a nd a description of the basic changes made to the original SAR.
Date:
May 17, 1999
Creator:
CAMPBELL, T.A.
System:
The UNT Digital Library