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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

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

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

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

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

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

A portable concentrator for processing plutonium containing solutions

Description: This report describes a horizontal, compact agitated-film concentrator called a Rototherm, manufactured by Artisan Industries, Inc. which can be used to process aqueous solutions of radioactive wastes containing plutonium. The unit is designed to concentrate liquid streams to a high-solid content slurry.
Date: December 1, 1995
Creator: Chamberlain, D.B.; Conner, C. & Chen, L.
Partner: UNT Libraries Government Documents Department

Control of instability in nitric acid evaporators for plutonium processing

Description: Improved control of the nitric acid process evaporators requires the detection of spontaneously unstable operating conditions. This process reduces the volume of contaminated liquid by evaporating nitric acid and concentrating salt residues. If a instability is identified quickly, prompt response can avert distillate contamination. An algorithm applied to the runtime data was evaluated to detect this situation. A snapshot of data from a histogram in the old process control software was captured during the unstable conditions and modeled.
Date: March 1, 1998
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

Detecting leaks in hydrocarbon storage tanks using electrical resistance tomography

Description: Large volumes of hydrocarbons are stored worldwide in surface and underground tanks. It is well documented [1] that all too often these tanks are found to leak, resulting in not only a loss of stored inventory but, more importantly, contamination to soil and groundwater. Two field experiments are reported herein to evaluate the utility of electrical resistance tomography (ERT) for detecting and locating leaks as well as delineating any resulting plumes emanating from steel underground storage tanks (UST). Current leak detection methods for single shell tanks require careful inventory monitoring, usually from liquid level sensors within the tank, or placement of chemical sensors in the soil under and around the tank. Liquid level sensors can signal a leak but are limited in sensitivity and, of course, give no information about the location or the leak or the distribution of the resulting plume. External sensors are expensive to retrofit and must be very densely spaced to assure reliable detection, especially in heterogeneous soils. The rational for using subsurface tomography is that it may have none of these shortcomings.
Date: April 3, 1995
Creator: Daily, W.; Ramirez, A.; LaBrecque, D. & Binley, A.
Partner: UNT Libraries Government Documents Department

Corrective Action Investigation Plan for Corrective Action Unit 151: Septic Systems and Discharge Area, Nevada Test Site, Nevada, Rev. No.: 0

Description: This Corrective Action Investigation Plan (CAIP) contains project-specific information for conducting site investigation activities at Corrective Action Unit (CAU) 151: Septic Systems and Discharge Area, Nevada Test Site, Nevada. Information presented in this CAIP includes facility descriptions, environmental sample collection objectives, and criteria for the selection and evaluation of environmental corrective action alternatives. Corrective Action Unit 151 is located in Areas 2, 12, 18, and 20 of the Nevada Test Site, which is 65 miles northwest of Las Vegas, Nevada. Corrective Action Unit 151 is comprised of the nine Corrective Action Sites (CAS) listed below: (1) 02-05-01, UE-2ce Pond; (2) 12-03-01, Sewage Lagoons (6); (3) 12-04-01, Septic Tanks; (4) 12-04-02, Septic Tanks; (5) 12-04-03, Septic Tank; (6) 12-47-01, Wastewater Pond; (7) 18-03-01, Sewage Lagoon; (8) 18-99-09, Sewer Line (Exposed); and (9) 20-19-02, Photochemical Drain. The CASs within CAU 151 are discharge and collection systems. Corrective Action Site 02-05-01 is located in Area 2 and is a well-water collection pond used as a part of the Nash test. Corrective Action Sites 12-03-01, 12-04-01, 12-04-02, 12-04-03, and 12-47-01 are located in Area 12 and are comprised of sewage lagoons, septic tanks, associated piping, and two sumps. The features are a part of the Area 12 Camp housing and administrative septic systems. Corrective Action Sites 18-03-01 and 18-99-09 are located in the Area 17 Camp in Area 18. These sites are sewage lagoons and associated piping. The origin and terminus of CAS 18-99-09 are unknown; however, the type and configuration of the pipe indicates that it may be a part of the septic systems in Area 18. Corrective Action Site 20-19-02 is located in the Area 20 Camp. This site is comprised of a surface discharge of photoprocessing chemicals.
Date: June 1, 2004
Creator: Strand, David A.
Partner: UNT Libraries Government Documents Department

Heat transfer enhanced microwave process for stabilization of liquid radioactive waste slurry. Final report

Description: The objectve of this CRADA is to combine a polymer process for encapsulation of liquid radioactive waste slurry developed by Monolith Technology, Inc. (MTI), with an in-drum microwave process for drying radioactive wastes developed by Oak Ridge National Laboratory (ORNL), for the purpose of achieving a fast, cost-effectve commercial process for solidification of liquid radioactive waste slurry. Tests performed so far show a four-fold increase in process throughput due to the direct microwave heating of the polymer/slurry mixture, compared to conventional edge-heating of the mixer. We measured a steady-state throughput of 33 ml/min for 1.4 kW of absorbed microwave power. The final waste form is a solid monolith with no free liquids and no free particulates.
Date: March 31, 1995
Creator: White, T.L.
Partner: UNT Libraries Government Documents Department

Report on the Biological Monitoring Program at Paducah Gaseous Diffusion Plant, January--December 1995

Description: The BMP for PGDP consists of three major tasks: (1) effluent and ambient toxicity monitoring, (2) bioaccumulation studies, and (3) ecological surveys of stream communities (benthic macroinvertebrates, fish). This report focuses on ESD activities occurring from Jan. 1995 to Dec. 1995, although activities conducted outside this period are included as appropriate.
Date: April 1, 1996
Creator: Kszos, L.A.
Partner: UNT Libraries Government Documents Department

Electrochemical Treatment of Liquid Wastes

Description: Electrochemical treatment processes are being evaluated and developed for the destruction of organic compounds and nitrates/nitrites and the removal of other hazardous species from liquid wastes stored throughout the DOE complex. The development program consists of five major tasks: (1) evaluation of electrochemical reactors for the destruction and removal of hazardous waste components, (2) development and validation of engineering process models, (3) radioactive laboratory-scale tests, (4) demonstration of the technology in an engineering-scale size reactor, and (5) analysis and evaluation of test data.
Date: December 1, 1996
Creator: Hobbs, D.T.
Partner: UNT Libraries Government Documents Department

Calculations of slurry pump jet impingement loads

Description: This paper presents a methodology to calculate the impingement load in the region of a submerged turbulent jet where a potential core exits and the jet is not fully developed. The profile of the jet flow velocities is represented by a piece-wise linear function which satisfies the conservation of momentum flux of the jet flow. The adequacy of the of the predicted jet expansion is further verified by considering the continuity of the jet flow from the region of potential core to the fully developed region. The jet impingement load can be calculated either as a direct impingement force or a drag force using the jet velocity field determined by the methodology presented.
Date: March 4, 1996
Creator: Wu, T.T.
Partner: UNT Libraries Government Documents Department

Waste minimization methods for treating analyticl instrumentation effluents at the source

Description: Recently there has been increasing interest in minimizing analytical laboratory wastes. The driving forces behind this interest are the ever increasing costs and liabilities associated with waste disposal. Thus, many analytical laboratories, like the Defense Waste Processing Technology-Analytical Laboratory (DWPT-AL), located at the Savannah River Site (SRS), are looking into treating their own wastes. The DWPT-AL operates four laboratory modules that produce hazardous liquid effluents from the analytical instrumentation: Spectroscopy, Chromatography I, Chromatography II, and Wet Chemistry. The hazardous waste from these modules is being sent to SRS Waste Management at a cost of approximately $13,000 per drum, which corresponds to approximately $325,000 to $520,000 per year. If the hazardous characteristics of and the hazardous components in the analytical instrument effluents or example preparation wastes can be altered and/or reduced in such a way as to render the stream non-hazardous, the large volume of non-hazardous waste can be disposed of via process drains. Therefore, the primary goal of this project was to reduce the amount of hazardous waste being generated by the DWPT-AL, thereby substantially reducing the costs associated with its disposal. A secondary goal was to develop in-line methods using primarily adsorption/ion exchange columns that can be used to treat the liquid effluent as it emerges from the analytical instrument as a slow, dripping flow. The second goal allows the treatment method to become part of the operating procedure associated with the instrument; thus, the effluent would not be considered a waste until it emerges from the in-line column.
Date: December 1, 1995
Creator: Policke, T.R.; Ritter, J.A. & Barnhart, C.
Partner: UNT Libraries Government Documents Department

Maintenance History of an Oberlin{reg_sign} Pressure Filter System

Description: Two Oberlin 24 sq. ft. pressure filters, operating in parallel for thirteen years at the Savannah River Site, have reliably removed precipitated metals from treated wastewater for direct discharge to surface stream. The maintenance history and modifications of these filters, as well as their flocculation and filter aid addition systems are reviewed. These system modifications have successfully extended service life of individual components and have improved total systems performance.
Date: May 1, 1998
Creator: Burch, J.V.; Norford, S.W. & Martin, H.L.
Partner: UNT Libraries Government Documents Department

Measurement of Thermal Properties of Saltstone

Description: Radioactive liquid effluent from the In Tank Precipitation Process is mixed with Portland cement, flyash and furnace alag to form Saltstone. The Saltstone is poured into vaults at Z Area for long term disposal. A transient heat transfer model of the Saltstone pouring process was previously written to determine whether the Saltstone temperature would exceed the Technical Specification Limit of 95 degrees C. The present work was performed to provide Saltstone density, heat capacity, heat of hydration and thermal conductivity for inclusion in the model.
Date: May 1998
Creator: Steimke, J. L. & Fowley, M. D.
Partner: UNT Libraries Government Documents Department