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Washing of Cloth Contaminated with Radionuclides Using A Detergent-Free Laundry System

Description: In this study, we describe a new laundry system to wash clothes, including those contaminated with radionuclides, without using detergent. The main part of this system is electrolytic cell that consists of a cathode with a special coating of nickel, an anode of nickel, and a cation exchange membrane between the two electrodes. The electrolyte is supplied to the anode and the tap-water to the cathode. When an electricity of 5 volts and 25 amperes is applied to the electrodes, the processed water is produced from the cathode. This processed water containing no detergent was investigated experimentally with regard to its decontamination efficiency of radionuclides and detergency of soil as compared to the conventional washing using detergent. It was found that the processed water from this system has an ability to simultaneously remove radionuclides and soil from the cloth with good efficiency.
Date: February 25, 2003
Creator: Yim, S. P.; Ahn, B. G.; Lee, H. J.; Shon, J. S.; Chung, H.; Kim, K. J. et al.
Partner: UNT Libraries Government Documents Department

Operating Range for High Temperature Borosilicate Waste Glasses: (Simulated Hanford Enveloped)

Description: The following results are a part of an independent thesis study conducted at Diagnostic Instrumentation and Analysis Laboratory-Mississippi State University. A series of small-scale borosilicate glass melts from high-level waste simulant were produced with waste loadings ranging from 20% to 55% (by mass). Crushed glass was allowed to react in an aqueous environment under static conditions for 7 days. The data obtained from the chemical analysis of the leachate solutions were used to test the durability of the resulting glasses. Studies were performed to determine the qualitative effects of increasing the B2O3 content on the overall waste glass leaching behavior. Structural changes in a glass arising due to B2O3 were detected indirectly by its chemical durability, which is a strong function of composition and structure. Modeling was performed to predict glass durability quantitatively in an aqueous environment as a direct function of oxide composition.
Date: February 24, 2003
Creator: Mohammad, J.; Ramsey, W. G. & Toghiani, R. K.
Partner: UNT Libraries Government Documents Department

Integrating Volume Reduction and Packaging Alternatives to Achieve Cost Savings for Low Level Waste Disposal at the Rocky Flats Environmental Technology Site

Description: In order to reduce costs and achieve schedules for Closure of the Rocky Flats Environmental Technology Site (RFETS), the Waste Requirements Group has implemented a number of cost saving initiatives aimed at integrating waste volume reduction with the selection of compliant waste packaging methods for the disposal of RFETS low level radioactive waste (LLW). Waste Guidance Inventory and Shipping Forecasts indicate that over 200,000 m3 of low level waste will be shipped offsite between FY2002 and FY2006. Current projections indicate that the majority of this waste will be shipped offsite in an estimated 40,000 55-gallon drums, 10,000 metal and plywood boxes, and 5000 cargo containers. Currently, the projected cost for packaging, shipment, and disposal adds up to $80 million. With these waste volume and cost projections, the need for more efficient and cost effective packaging and transportation options were apparent in order to reduce costs and achieve future Site packaging a nd transportation needs. This paper presents some of the cost saving initiatives being implemented for waste packaging at the Rocky Flats Environmental Technology Site (the Site). There are many options for either volume reduction or alternative packaging. Each building and/or project may indicate different preferences and/or combinations of options.
Date: February 26, 2002
Creator: Church, A.; Gordon, J. & Montrose, J. K.
Partner: UNT Libraries Government Documents Department


Description: The Environmental Management Science Program (EMSP) funds basic science research that will lead to reduced remediation cost, schedule, technical uncertainties, and risk for DOE’s environmental clean up. The Tanks Focus Area (TFA) has partnered with EMSP to accomplish those same objectives for DOE’s largest and most expensive remediation effort – to retrieve and immobilize the highly radioactive wastes that are our nation's chief nuclear defense program legacy. TFA has been tasked to facilitate success of the EMSP investment. The key for EMSP projects to contribute to this remediation effort is communication. First, the scientist needs to understand much more about how his scientific results would be used than he could ever learn from the original EMSP solicitation or by reading the referenced DOE needs statements. Second, the scientist’s results must be communicated to the site problem holders in a usable form and in a timely manner such that important information gaps can still be filled by the EMSP project. Research results can be used in a variety of ways besides deployment of new hardware or a new process. When results are USED the site problem holders become “users”. The important aspect that research results are to be used is captured in the TFA lexicon for their clients, the DOE sites--“USERS”. The best method observed, so far, to accomplish the indispensable communication necessary for success is through direct contact between EMSP researchers and TFA/site problem holders, person to person. The observation that direct contact is the best medium for exchange of complex information may seem inanely obvious. However, it is not the normal procedure in the more academic world of the fundamental scientists, where publishing of results in a peer-reviewed journal completes the transmittal of scientific results. Direct communication between EMSP researchers and site users doesn’t occur naturally. TFA actively bridges ...
Date: July 31, 2003
Creator: Josephson, Gary B. & Hale, Donna
Partner: UNT Libraries Government Documents Department

Utilization of a Technical Peer Review to Support the Mission of the Nevada Test Site Community Advisory Board

Description: The U. S. Department of Energy's (DOE) National Nuclear Security Administration Nevada Operations Office (NNSA/NV) Environmental Management (EM) Underground Test Area (UGTA) project addresses the characterization and needs for long-term monitoring of the subsurface contamination resulting from 828 underground nuclear weapon tests at the Nevada Test Site (NTS). EM promotes, and is required, to include stakeholders in its program. However, UGTA is a very complex program not easily understood by members of the public. The NTS Community Advisory Board (CAB), a federally chartered Site Specific Advisory Board (SSAB), has studied the UGTA project since 1996, and has found it a challenge to completely comprehend and provide NNSA/NV meaningful citizen input. The CAB realized the benefit of a technical peer review and in 2000 recommended to NNSA/NV that a peer review of the UGTA strategy would provide valuable feedback to the program to address underground contamination at the NTS. N NSA agreed to the CAB's recommendation, and moved forward with a scope of work to have the American Society of Mechanical Engineers (ASME) perform the peer review of the UGTA strategy. The ASME began the peer review in June 2001, and their final report was published in November 2001. In January 2002, the CAB devoted their monthly meeting in Las Vegas, Nevada to reporting the results of the peer review of the UGTA strategy to the public. Two public workshops were later held in the community of Amargosa, Nevada during the month of January to help educate and build interest in the CAB February 2002 monthly meeting which was also held in Amargosa. The CAB recommendation to NNSA to utilize a technical peer review has provided valuable information to NNSA, the State of Nevada, and the CAB. At other DOE sites SSABs are challenged by a number of complex, technical programs ...
Date: February 27, 2003
Creator: Dixon, Earle C. & Peterson, Kathleen
Partner: UNT Libraries Government Documents Department

Outlooks of HLW Partitioning Technologies Usage for Recovering of Platinum Metals from Spent Fuel

Description: The existing practice of management of high level waste (HLW) generated by NPPs, call for a task of selective separation of the most dangerous long-lived radionuclides with the purpose of their subsequent immobilization and disposal. HLW partitioning allows to reduce substantially the cost of vitrified product storage owing to isolation of the most dangerous radionuclides, such as transplutonium elements (TPE) into separate fractions of small volumes, intended for ultimate storage. By now numerous investigations on partitioning of HLW of various composition have been carried out in many countries and a lot of processes permitting to recover cesium, strontium, TPE and rare earth elements (REE) have been already tested. Apart from enumerated radionuclides, a fair quantity of palladium and rhodium presents in spent fuel, but the problem of these elements recovery has not yet been decided at the operating radiochemical plants. A negative effect of platinum group metals (PGM) occurrence is determined by the formation of separate metal phase, which not only worsens the conditions of glass-melting but also shortens considerably the service life of the equipment. At the same time, the exhaustion of PGMs natural resources may finally lead to such a growth of their costs that the spent nuclear fuel would became a substituting source of these elements industrial production. Allowing above mentioned, it is of interest to develop the technique for ''reactor'' palladium and rhodium recovery process which would be compatible with HLW partitioning and could be realized using the same facilities. In the report the data on platinum metals distribution in spent fuel reprocessing products and the several flowsheets for palladium separation from HLW are presented.
Date: February 24, 2003
Creator: Pokhitonov, Y. A.; Estimantovskiy, V.; Romanovski, v.; Zatsev, B. & Todd, T.
Partner: UNT Libraries Government Documents Department

Overview of Fiscal Year 2002 Research and Development for Savannah River Site's Salt Waste Processing Facility

Description: The Department of Energy's (DOE) Savannah River Site (SRS) high-level waste program is responsible for storage, treatment, and immobilization of high-level waste for disposal. The Salt Processing Program (SPP) is the salt (soluble) waste treatment portion of the SRS high-level waste effort. The overall SPP encompasses the selection, design, construction and operation of treatment technologies to prepare the salt waste feed material for the site's grout facility (Saltstone) and vitrification facility (Defense Waste Processing Facility). Major constituents that must be removed from the salt waste and sent as feed to Defense Waste Processing Facility include actinides, strontium, cesium, and entrained sludge. In fiscal year 2002 (FY02), research and development (R&D) on the actinide and strontium removal and Caustic-Side Solvent Extraction (CSSX) processes transitioned from technology development for baseline process selection to providing input for conceptual design of the Salt Waste Processing Facility. The SPP R&D focused on advancing the technical maturity, risk reduction, engineering development, and design support for DOE's engineering, procurement, and construction (EPC) contractors for the Salt Waste Processing Facility. Thus, R&D in FY02 addressed the areas of actual waste performance, process chemistry, engineering tests of equipment, and chemical and physical properties relevant to safety. All of the testing, studies, and reports were summarized and provided to the DOE to support the Salt Waste Processing Facility, which began conceptual design in September 2002.
Date: February 26, 2003
Creator: Harmon, H. D.; Leugemors, R.; Fink, S.; Thompson, M.; Walker, D.; Suggs, P. et al.
Partner: UNT Libraries Government Documents Department