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Full-Scale Test of a Non-Plugging Bubbler Used in Large Tanks Containing High Yield Stress Slurries

Description: As a follow-up to a bench-top experiment (1), the Savannah River Technology Center (SRTC) at the Savannah River Site (SRS) carried out a full-scale test of a "large-diameter" bubbler (LDB) to measure liquid-level and density in high yield stress slurries. The test was the final step in a process to find an instrument that could effectively and economically operate in the existing mixing tank environments. Positive results would lead to implementation of the LDB. This new bubbler replaced two inadequate instruments: an expensive technology, a Holledge probe, which needed replacing twice a year and "standard bubblers," which plugged in as little as four hours of operation. Three LDBs, at different depths, were tested under highly prototypic conditions from November 27, 1996, to January 23, 1997, using the full-scale test facilities at SRS. The instruments were subjected to 58 days of slurry operation; 14 days of which the slurry was brought to boiling temperatures. The results showed that the LDBs (6.7 cm inside diameter) operated successfully by not plugging with the glass-frit ladened slurry, which was maintained at a minimum temperature of 50 degrees C and at approximatley 102 degrees C during days of boiling. A recommendation was made to implement the LDB because none of the three bubblers plugged during the test period to the point of compromising liquid-level measurement. However, after a week's operation at boiling temperatures, several inches of a soft sludge built up within the bubbler tubes. This sludge was easily removed in place with high-pressure water. Since completion of this study, four LDBs have been installed in different tanks throughout the Defense Waste Processing Facility at SRS. Their operation has been satisfactory to date.
Date: January 5, 1999
Creator: Duignan, M.R.
Partner: UNT Libraries Government Documents Department

Hanford facility RCRA permit condition II.U.1 report: mapping of underground piping

Description: The purpose of this report is to fulfill Condition Il.U.1. of the Hanford Facility (HF) Resource Conservation and Recovery Act (RCRA) Permit. The HF RCRA Permit, Number WA7890008967, became effective on September 28, 1994 (Ecology 1994). Permit Conditions Il.U. (mapping) and II.V. (marking) of the HF RCRA Permit, Dangerous Waste (OW) Portion, require the mapping and marking of dangerous waste underground pipelines subject to the provisions of the Washington Administrative Code (WAC) Chapter 173-303. Permit Condition Il.U.I. requires the submittal of a report describing the methodology used to generate pipeline maps and to assure their quality. Though not required by the Permit, this report also documents the approach used for the field marking of dangerous waste underground pipelines.
Date: September 27, 1996
Creator: Hays, C.B.
Partner: UNT Libraries Government Documents Department

Corrective Action Investigation Plan: Roller Coaster Lagoons and North Disposal Trench, Tonopah Test Range, Revision 1

Description: 1.1 Purpose The purpose of this investigation is to collect data to confirm the presence or absence of contamination, evaluate the potential for contaminant migration, and select appropriate closure methods for these sites. The potential closure methods for these sites involve either clean closure, closure in place, or no further action. 1.2 Scope The scope of this investigation includes collecting surface and subsurface soil samples at the Roller Coaster Lagoons; and collecting surface soil samples at the North Disposal Trench and the small spill area associated with the Voluntary Cotiective Action (VCA) that was conducted in 1995.
Date: June 27, 1996
Creator: IT Corporation, Las Vegas, NV
Partner: UNT Libraries Government Documents Department

Functional design criteria for project W-252, phase II liquid effluent treatment and disposal. Revision 2

Description: This document is the Functional Design Criteria for Project W-252. Project W-252 provides the scope to provide BAT/AKART (best available technology...) to 200 Liquid Effluent Phase II streams (B-Plant). This revision (Rev. 2) incorporates a major descoping of the project. The descoping was done to reflect a combination of budget cutting measures allowed by a less stringent regulatory posture toward the Phase II streams
Date: May 1, 1995
Creator: Hatch, C.E.
Partner: UNT Libraries Government Documents Department

TWRS privatization phase I liquid effluent transfer systems engineering study

Description: The DOE-RL is pursuing a new business strategy of hiring private contractors for treatment of Hanford tank waste. This `privatization` initiative includes design, permitting, construction, operations, deactivation and decommissioning of tank waste treatment facilities. The TWRS Privatization Infrastructure Project is part of the first phase of the initiative. It consists of several sub-projects which will provide key physical interfaces and services needed to support the phase I mission. One sub-project is to provide transfer systems integrated with 200 Area liquid effluent facilities to service the private contractors. This study deals with transfer systems requirements, alternatives and identifies a preferred alternative.
Date: September 30, 1996
Creator: Parazin, R.J.
Partner: UNT Libraries Government Documents Department

340 Waste handling facility deactivation plan

Description: This document provides an overview of both the present status of the 340 Complex (within Hanford`s 300 Area), and of tasks associated with the deactivation of segments associated with radioactive, mixed liquid waste receipt, storage, and shipping. The plan also describes activities that will allow portions of the 340 Complex to remain in service.
Date: December 27, 1996
Creator: Stordeur, R.T., Westinghouse Hanford
Partner: UNT Libraries Government Documents Department

Apparatus and method for two-stage oxidation of wastes

Description: An apparatus and method for oxidizing wastes in a two-stage process. The apparatus includes an oxidation device, a gas-liquid contacting column and an electrocell. In the first stage of the process, wastes are heated in the presence of air to partially oxidize the wastes. The heated wastes produce an off-gas stream containing oxidizable materials. In the second stage, the off-gas stream is cooled and flowed through the contacting column, where the off-gas stream is contacted with an aqueous acid stream containing an oxidizing agent having at least two positive valence states. At least a portion of the oxidizable materials are transferred to the acid stream and destroyed by the oxidizing agent. During oxidation, the valence of the oxidizing agent is decreased from its higher state to its lower state. The acid stream is flowed to the electrocell, where an electric current is applied to the stream to restore the oxidizing agent to its higher valence state. The regenerated acid stream is recycled to the contacting column.
Date: September 28, 1993
Creator: Fleischman, S. D.
Partner: UNT Libraries Government Documents Department

INEEL Radioactive Liquid Waste Reduction Program

Description: Reduction of radioactive liquid waste, much of which is Resource Conservation and Recovery Act (RCRA) listed, is a high priority at the Idaho National Technology and Engineering Center (INTEC). Major strides in the past five years have lead to significant decreases in generation and subsequent reduction in the overall cost of treatment of these wastes. In 1992, the INTEC, which is part of the Idaho National Environmental and Engineering Laboratory (INEEL), began a program to reduce the generation of radioactive liquid waste (both hazardous and non-hazardous). As part of this program, a Waste Minimization Plan was developed that detailed the various contributing waste streams, and identified methods to eliminate or reduce these waste streams. Reduction goals, which will reduce expected waste generation by 43%, were set for five years as part of this plan. The approval of the plan led to a Waste Minimization Incentive being put in place between the Department of Energy � Idaho Office (DOE-ID) and the INEEL operating contractor, Lockheed Martin Idaho Technologies Company (LMITCO). This incentive is worth $5 million dollars from FY-98 through FY-02 if the waste reduction goals are met. In addition, a second plan was prepared to show a path forward to either totally eliminate all radioactive liquid waste generation at INTEC by 2005 or find alternative waste treatment paths. Historically, this waste has been sent to an evaporator system with the bottoms sent to the INTEC Tank Farm. However, this Tank Farm is not RCRA permitted for mixed wastes and a Notice of Non-compliance Consent Order gives dates of 2003 and 2012 for removal of this waste from these tanks. Therefore, alternative treatments are needed for the waste streams. This plan investigated waste elimination opportunities as well as treatment alternatives. The alternatives, and the criteria for ranking these alternatives, were identified ...
Date: February 1, 1999
Creator: Millet, C. B.; Tripp, J. L.; Archibald, K. E.; Lauerhauss, L.; Argyle, M. D. & Demmer, R. L.
Partner: UNT Libraries Government Documents Department

Medical and Biohazardous Waste Generator's Guide (Revision2)

Description: These guidelines describe procedures to comply with all Federal and State laws and regulations and Lawrence Berkeley National Laboratory (LBNL) policy applicable to State-regulated medical and unregulated, but biohazardous, waste (medical/biohazardous waste). These guidelines apply to all LBNL personnel who: (1) generate and/or store medical/biohazardous waste, (2) supervise personnel who generate medical/biohazardous waste, or (3) manage a medical/biohazardous waste pickup location. Personnel generating biohazardous waste at the Joint Genome Institute/Production Genomics Facility (JGI/PGF) are referred to the guidelines contained in Section 9. Section 9 is the only part of these guidelines that apply to JGI/PGF. Medical/biohazardous waste referred to in this Web site includes biohazardous, sharps, pathological and liquid waste. Procedures for proper storage and disposal are summarized in the Solid Medical/Biohazardous Waste Disposal Procedures Chart. Contact the Waste Management Group at 486-7663 if you have any questions regarding medical/biohazardous waste management.
Date: November 29, 2006
Creator: Group, Waste Management
Partner: UNT Libraries Government Documents Department

EFFECT OF CHLORIDE AND SULFATE CONCENTRATION ON PROBABLITY BASED CORROSION CONTROL FOR LIQUID WASTE TANKS- PART IV

Description: A series of cyclic potentiodynamic polarization tests was performed on samples of A537 carbon steel in support of a probability-based approach to evaluate the effect of chloride and sulfate on corrosion susceptibility. Testing solutions were chosen to build off previous experimental results from FY07, FY08, FY09 and FY10 to systemically evaluate the influence of the secondary aggressive species, chloride, and sulfate. The FY11 results suggest that evaluating the combined effect of all aggressive species, nitrate, chloride, and sulfate, provides a consistent response for determining corrosion susceptibility. The results of this work emphasize the importance for not only nitrate concentration limits, but also chloride and sulfate concentration limits as well.
Date: August 23, 2012
Creator: Hoffman, E.
Partner: UNT Libraries Government Documents Department

A Comparative Review of Hydrologic Issues Involved in Geologic Storage of CO2 and Injection Disposal of Liquid Waste

Description: The paper presents a comparison of hydrologic issues and technical approaches used in deep-well injection and disposal of liquid wastes, and those issues and approaches associated with injection and storage of CO{sub 2} in deep brine formations. These comparisons have been discussed in nine areas: (1) Injection well integrity; (2) Abandoned well problems; (3) Buoyancy effects; (4) Multiphase flow effects; (5) Heterogeneity and flow channeling; (6) Multilayer isolation effects; (7) Caprock effectiveness and hydrogeomechanics; (8) Site characterization and monitoring; and (9) Effects of CO{sub 2} storage on groundwater resources There are considerable similarities, as well as significant differences. Scientifically and technically, these two fields can learn much from each other. The discussions presented in this paper should help to focus on the key scientific issues facing deep injection of fluids. A substantial but by no means exhaustive reference list has been provided for further studies into the subject.
Date: April 15, 2008
Creator: Tsang, C.-F.; Birkholzer, J. & Rutqvist, J.
Partner: UNT Libraries Government Documents Department

Progress Report on Waste Concentration Studies: Engineering Results on the BNL Semi-Works Vapor Filtration Vapor Compression Evaporator

Description: Report issued by the Brookhaven National Laboratory discussing progress of waste concentration studies. As stated in the introduction, "the present report covers all experimental hot runs up to the time the still was turned over to the Waste Control Section for intermediate handling of laboratory D waste" (p. 1). This report includes tables, illustrations, and photographs.
Date: August 15, 1951
Creator: Horrigan, R. V.; Fried, H. M.; Manowitz, B.; Kuhl, O.; Baranosky, J. A.; Bellanca, S. et al.
Partner: UNT Libraries Government Documents Department

Tank 241-Z-361 process and characterization history

Description: An Unreviewed Safety Question (Wagoner, 1997) was declared based on lack of adequate authorization basis for Tank 241-Z-361 in the 200W Area at Hanford. This document is a summary of the history of Tank 241-Z-361 through December 1997. Documents reviewed include engineering files, laboratory notebooks from characterization efforts, waste facility process procedures, supporting documents and interviews of people`s recollections of over twenty years ago. Records of transfers into the tank, past characterization efforts, and speculation were used to estimate the current condition of Tank 241-Z-361 and its contents. Information about the overall waste system as related to the settling tank was included to help in understanding the numbering system and process relationships. The Plutonium Finishing Plant was built in 1948 and began processing plutonium in mid-1949. The Incinerator (232-Z) operated from December 1961 until May 1973. The Plutonium Reclamation Facility (PRF, 236-Z) began operation in May 1964. The Waste Treatment Facility (242-Z) operated from August 1964 until August 1976. Waste from some processes went through transfer lines to 241-Z sump tanks. High salt and organic waste under normal operation were sent to Z-9 or Z-18 cribs. Water from the retention basin may have also passed through this tank. The transfer lines to 241-Z were numbered D-4 to D-6. The 241-Z sump tanks were numbered D-4 through D-8. The D-4, 5, and 8 drains went to the D-6 sump tank. When D-6 tank was full it was transferred to D-7 tank. Prior to transfer to cribs, the D-7 tank contents was sampled. If the plutonium content was analyzed to be more than 10 g per batch, the material was (generally) reprocessed. Below the discard limit, caustic was added and the material was sent to the cribs via the 241-Z-361 settling tank where solids settled out and the liquid overflowed by gravity ...
Date: August 6, 1998
Creator: Jones, S.A.
Partner: UNT Libraries Government Documents Department

Design assessment for the Melton Valley Storage Tanks capacity increase at Oak Ridge National Laboratory under the Federal Facility Agreement, Oak Ridge, Tennessee

Description: This project was initiated to find ways to increase storage capacity for the liquid low-level waste (LLLW) system at the Oak Ridge National Laboratory and satisfy the Federal Facility Agreement (FFA) requirement for the transfer of LLW from existing tank systems not in full FFA compliance.
Date: November 1, 1995
Partner: UNT Libraries Government Documents Department

Preliminary tank characterization report for single-shell tank 241-SX-105: Best-basis inventory

Description: An effort is underway to provide waste inventory estimates that will serve as standard characterization source terms for the various waste management activities. As part of this effort, an evaluation of available information for single-shell tank 241-SX-105 was performed, and a best-basis inventory was established. This work follows the methodology that was established by the standard inventory task.
Date: August 29, 1997
Creator: Kupfer, M.J.
Partner: UNT Libraries Government Documents Department

Effects of Resin Particle Size and Solution Temperature on SuperLig(R) 644 Resin Performance with AN-105 Simulate

Description: The performance of the SuperLig(R) 644 resin loading and elution was evaluated at 25, 35, and 45 degree C using a single-column containing 2.25 g of oven-dry, hydrogen form of SuperLig(R) 664 resin. A simulated Envelope A solution was used to mimic the composition of low-activity waste solution from Tank 241-AN-105 supernate in the Hanford Site waste tank. The simulant was spiked with small quantities of trace metals (cadmium, chromium, iron, and lead) to evaluate the effects of these metals on cesium sorption. The results from column tests performed at 25, 35, and 45 degree C showed that more than 100 BVs of simulated Envelope A solution could be processed at each temperature before 50 percent breakthrough of the cesium occurred.
Date: July 15, 2003
Creator: Nash, C.A.
Partner: UNT Libraries Government Documents Department

Radioactive liquid waste generation goals at the ICPP

Description: Processes at ICPP generating hazardous radioactive liquid wastes (which are sent to the tank farm) include NWCF, PEW evaporator, LET&D, tank farm, fuel storage operations, etc. In May 1994, the INEL Radioactive Liquid Waste Management Plan was issued but not implemented. Waste generation goals have been reviewed and updated in this report (details are given in appendix). A meeting was held to determine the new waste generation goals and best approach to reaching them. Waste streams were individually analyzed in this meeting and several adjustments made both during the meeting and following the meeting. The information was adjusted and modeling completed to determine the waste reduction achieved (spreadsheets are included in appendix). Results of this update indicate that there has been a significant reduction in the waste generation goals from 2 years ago. If the updated baseline goals are met, a 35% waste reduction will be achieved; this coupled with increased calcination rate, will enable the waste in the tank farm to be processed by 2012; however a program is needed to ensure these waste goals are met. A monitoring and reporting function in conjunction with company level incentives will fill this need; a logic diagram of this monitoring program is given.
Date: July 1, 1996
Creator: Tripp, J.L.
Partner: UNT Libraries Government Documents Department

Glass melter system technologies for vitrification of high-sodium-content low-level, radioactive, liquid wastes: Phase 1, SBS demonstration with simulated low-level waste. Final test report

Description: The attached vendor report was prepared for Westinghouse Hanford Company by Babcock & Wilcox as documentation of the Phase I Final Test Report, Cyclone Combustion Melter Demonstration.
Date: December 31, 1995
Creator: Holmes, M.J.; Scotto, M.V. & Shiao, S.Y.
Partner: UNT Libraries Government Documents Department