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Results for “LIQUID RADIOACTIVE WASTE”

Search indexed NASA NTRS and DOE OSTI research on propulsion, heat transfer, battery materials and energy systems. Follow report and document links to the original sources.

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At least 19 records
All sourcesNASA NTRSDOE OSTI
DOE OSTI2018

The Use of Macrophytes as Biosorbents in Radioactive Liquid Waste Treatment - 18039

An important stage of the management of radioactive liquid waste is the chemical treatment. In the last few years, bio-sorption has attracted attention as one alternative method to remove radionuclides in liquid LL/ILW due to its efficiency and low costs. There are many biomasses that can be applied for this purpose, as agricultural residues and Macrophytes. This study aims at studying Macrophytes (Pistia Stratiotes, Limnobium Laevigatum, Lemna sp and Azolla sp) ability to absorb uranium in liquid solutions. The bio-sorption capacity of uranium by the Macrophytes was experimentally determined. The experiments determine the metal uptake after the solution was in contact with each bio-sorbents by inductively coupled plasma optical emission spectrometry (ICP-OES). The results show that these materials are potentially applicable in the treatment of liquid radioactive waste. (authors)

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DOE OSTI2018

Immobilization of organic radioactive and non-radioactive liquid waste in a composite matrix

A method for immobilizing liquid radioactive waste is provided, the method having the steps of mixing waste with polymer to form a non-liquid waste; contacting the non-liquid waste with a solidifying agent to create a mixture, heating the mixture to cause the polymer, waste, and filler to irreversibly bind in a solid phase, and compressing the solid phase into a monolith. The invention also provides a method for immobilizing liquid radioactive waste containing tritium, the method having the steps of mixing liquid waste with polymer to convert the liquid waste to a non-liquid waste, contacting the non-liquid waste with a solidifying agent to create a mixture, heating the mixture to form homogeneous, chemically stable solid phase, and compressing the chemically stable solid phase into a final waste form, wherein the polymer comprises approximately a 9:1 weight ratio mixture of styrene block co-polymers and cross linked co-polymers of acrylamides.

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DOE OSTI2016

WOW Technology's Innovative Radioactive Liquid Waste Treatment - 16128

WOW presents its revolutionary technology and equipment for liquid radioactive waste treatment: outperforming ultimate water decontamination and purification process, enhanced sludge concentration, no secondary waste nor consumables, fully automated, remote controlled and self-decontaminating device. The WOW's technology is based upon a never before observed discovery of fluid dynamics science: the possibility of performing a molecular separation between solute and suspended elements and the solvent. The combination of such a molecular separation process with a standard vacuum evaporation improves the abatement performances by thousands of times, with respect to those of the state of the art vacuum evaporators. In addition to this, no secondary waste is produced during the process, as no filters, membranes, resins or additives are used. WOW equipment, automated and remote controlled, self decontaminates after use and can be designed and constructed either tailored to the application needs or with a modular approach for enhanced transportability and application flexibility. After the preliminary verification by CNR, the Italian National Research Center, WOW Technology's decontamination device was tested c/o LENA, the Laboratory of Applied Nuclear Energy of the University of Pavia, Italy with a simulated solution 6000 times more contaminated than the nuclear reactor's cooling water of Fukushima-Daiichi NPP. In addition to that, WOW's technology was also used in a real case at the Radiochemistry laboratory of the Pavia's University Chemistry department. Both the above mentioned contaminated fluids have been successfully decontaminated without production of additional or secondary waste. WOW's technology has already performed on industrial scale c/o the Nuclear Repository of S.S.M. in Saluggia, Italy: 45000 liters of acid radioactive solution have been successfully decontaminated to a Decontamination Factor (DF) of 335000 for Cs-137 by one single evaporation step and without using any additional tool to control steam. [Performances independently certified by: National Physics Laboratory (UK) and Pavia University Radiochemistry Laboratory, Chemistry Department (Italy)]. The high decontamination factors and the high volume reduction of the sludge make this technology suitable for the ultimate treatment of highly contaminated liquid waste such as the Fukushima-Daiichi nuclear reactor's cooling water. The WOW's technology addresses as well to interventions in both, operating and decommissioning nuclear power plants and any other nuclear and radioactive facility whose produced and/or stored radioactive liquid solutions, including acid liquid solutions, can be successfully treated, the waste volume reduced and no secondary waste produced. (authors)

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DOE OSTI2017

Immobilization in Cement of Rice Husk used as Bio-sorbent of Radionuclides Present in Radioactive Liquid Waste - 17225

The use of new techniques for the treatment of radioactive liquid wastes has been studied in the last few years by many countries. In this context, the bio-sorption has been an attractive process. In Brazil the Radioactive Waste Management Laboratory of Nuclear and Energy Research Institute (IPEN-CNEN/SP), studied some bio-masses to be used as bio-sorbents to remove radionuclides of the radioactive liquid waste stored in this institute. The rice husk is a low cost and wide available byproduct of the agriculture and its bio-sorption capacity has been proved as feasible. Thus, it is necessary to evaluate if its immobilization in a cementitious matrix will result in a waste form that meets the requirements of Brazilian regulations for final disposal of low and intermediate level waste. This work aimed at evaluating the properties of the immobilization of rice husk in a cementitious matrix. Some properties of the waste form with incorporated rice husk were evaluated, as free water, workability, setting time and mechanical strength. The results indicated that cement matrices with 5 and 10% of biomass and water/cement ratio of 0.30 and 0.35 are viable for the production of waste forms that meets the Brazilian regulations. (authors)

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DOE OSTI2020

Proven Technologies for the Solidification of Complex Liquid Radioactive Waste (LRW): Global Case Studies of Applications and Disposal Options - 20424

Legacy radioactive waste streams from the Cold War still exist and newly generated waste streams from nuclear power plants and research institutes go untreated and expose environmental hazards at many nuclear sites. The nature of the waste is diverse, depending upon the source or the process from which it originated. The most problematic waste streams include complex liquids such as organic (tri-butyl-phosphate TBP) solutions contaminated with Pu and U isotopes, mixed sludge types, high acid radioactive waste, H-3 contaminated organic and aqueous streams, etc. Technological, environmental and economic challenges exist for the treatment and disposal of such waste streams. A proven technology that has been applied to LRW on a global basis provides one option as a low-cost solution to legacy streams and small volume, highly complex LRW frequently found during decommissioning at nuclear power plants and weapons sites. The engineered polymer technology from Nochar, USA, is capable of solidifying standard and highly complex LLW and ILW waste streams for interim or final storage, or for incineration. (authors)

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DOE OSTI2018

Meeting the Challenges, Exceeding Expectations in Radioactive Liquid Waste Work - 18657

The Savannah River Site (SRS) is an 803-square kilometer (310-square mile) U.S. Department of Energy (DOE) site located near Aiken, South Carolina, encompassing parts of Aiken, Barnwell, and Allendale counties. SRS is a key industrial complex responsible for environmental stewardship, environmental cleanup, waste management, and disposition of nuclear materials. The Site was constructed in the early 1950's in support of the United States' Cold War efforts. In July 2009, the DOE began a new era by awarding a stand-alone contract to execute the Liquid Waste Mission at SRS. The Liquid Waste Contractor is responsible for all liquid waste operations, including waste management, disposition, and management of all liquid waste facilities at SRS, as well as operationally closing high-level waste tanks. Currently, there are 43 operational underground storage tanks containing approximately 132.5 million liters (35 million gallons) of radioactive waste. Before tanks can be closed, work involves removing, stabilizing, and disposing of high- and low-level radioactive waste from the tanks. (authors)

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DOE OSTI2018

Immobilization of Organic Liquid Radioactive Waste (LWR) in a Sulfur Composite Matrix at the BN-350 Fast Neutron Reactor Site, Kazakhstan - 18031

The immobilization treatment and final disposition of all forms of organic radioactive liquids, such as pump oil, spent solvent, tri-butyl-phosphate (TBP) and scintillation fluids, remain a significant challenge for nuclear waste generators and national regulators. The majority of nuclear nations have instituted regulations that require some form of encapsulation of treated organic liquid, notwithstanding LLW organic liquids that can be safely incinerated. In most cases cement is the designated material for encapsulation; however, cement can pose certain problems with the containment of treated organic liquids. In 2013, with funding from the U.S. Department of Energy - National Nuclear Security Administration through its Global Initiative for Proliferation Prevention Program (GIPP), a proven U.S. technology for the treatment of radioactive organic liquids was introduced at the BN-350 fast neutron reactor facility in Aktau, Kazakhstan. As the facility was undergoing full decommissioning, one hundred and sixty cubic meters of contaminated pump oil (including Cs-137, Sr-90 and U-235/238) contained in large above ground tanks had to be treated for final disposal. As a result of the research conducted over a two-year period, a new 2-step treatment process was invented by combining the U.S. solidification technology with a newly developed inorganic filler and molecular sulfur, referred to as radiation-resistant composite (RRC) to fully encapsulate the waste oil. The outcome of extensive test program indicates that the final form can reach up to 60 wt.% with a compressive strength of about 100 kg/cm{sup 2}. Preliminary conclusions indicate that RRC outperforms cement as an encapsulation form for final waste treatment which meets U.S. Nuclear Regulatory requirements for final disposal. This paper examines the preliminary experimental work that was conducted in Kazakhstan with the U.S. polymer technology and radioactive pump oil, and the subsequent secondary process of combining the solidified material into a homogeneous final form utilizing RRC. Topics covered in the paper include: - Kazakhstan's regulatory requirements for attaining an achievable waste form for acceptance, which led to the RRC invention; - Technical objectives for the application of polymer technology and RRC materials to radioactive liquid waste; - Polymer solidification with radioactive oil and the result; step one of the RRC process; - Description of RRC materials, their origin and chemical characteristics; - Process of combining the solidified polymer mass with RRC materials into a solid, homogeneous matrix; step two of the RRC process; - Experimental results including leaching data, waste loading estimates and heat process calculations to create the matrix; - Cost advantages of the RRC process over cementation; - Limitations of the RRC process; - Next steps to verify conformance of the RRC technology to the U.S. requirements. (authors)

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DOE OSTI2018

Radioactive Liquid Waste Treatment Facility Discharges in 2017

This report documents radioactive discharges from the TA50 Radioactive Liquid Waste Treatment Facility (RLWTF) during calendar year 2017. During 2017, all treated water was fed to the effluent evaporator. The evaporator was operated 3574 hours on 224 days, primarily in one-burner mode (63% of the time). A total of 3.42 million liters of treated water were fed to the evaporator, and 3.36 million liters were discharged to the environment as steam from the evaporator stack. Evaporator operation continued the single-tank feed mode that was begun in 2014. Specifically, when a Frac tank was filled with treated water, contents of the tank were mixed; a representative sample was collected; and the sample was analyzed to assess water quality. A total of 49 tanks of treated water were sampled, analyzed, and then fed to the evaporator during 2017. Tank samples were analyzed for gross alpha, gross beta, tritium, and a few inorganic parameters such as nitrate and dissolved solids. Frac tank samples of evaporator feed were held, then composited at the end of each month. Each monthly composite sample was then analyzed for gross alpha, gross beta, tritium, and 36 radioisotopes (eight alpha-emitting isotopes, 28 beta emitters). Samples were also collected of water drained from the evaporator. These samples, analyzed for alpha, beta, and tritium concentrations, were then used to estimate radioactive quantities present in evaporator drain water. The difference, rad fed less rad drained, yielded quantities of radioactivity discharged through the stack into the environment . Table 1 summarizes this information.

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DOE OSTI2016

DWPF Safely Dispositioning Liquid Waste

The only operating radioactive waste glassification plant in the nation, the Defense Waste Processing Facility (DWPF) converts the liquid radioactive waste currently stored at the Savannah River Site (SRS) into a solid glass form suitable for long-term storage and disposal. Scientists have long considered this glassification process, called “vitrification,” as the preferred option for treating liquid radioactive waste.

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DOE OSTI2016

Transitioning from Construction to Startup at WTP from a Plant Engineering Perspective - 16461

The Hanford Tank Waste Treatment and Immobilization Plant (WTP) is a one-of-a-kind facility being designed, built and commissioned for the U.S. Department of Energy by Bechtel National, Inc. and principal subcontractor URS to solidify liquid radioactive waste stored in underground tanks at the Hanford Site. WTP consists of 20 infrastructure facilities and structures, known as Balance of Facilities, designed to support the Plant's four major facilities - Pretreatment Facility, High-Level Waste Vitrification Facility, Low-Activity Waste Vitrification Facility and the Analytical Laboratory. As construction moves toward startup and commissioning, a turnover process facilitates the transition of facilities and systems between organizations. The transition from Construction is initiated by an approved Design Completion List, which documents that design and construction have been completed, and the facility or system is ready for startup testing. Qualified individuals perform an inspection to ensure the facility or system has been constructed per the design during an eight-week engineering walk-down. During this phase in turnover, Plant Engineering personnel are responsible for updating and maintaining the Master Equipment List, developing spare parts recommendations, developing and issuing instrument calibration data sheets, evaluating temporary modifications, and supporting plant operations and maintenance activities. As of 2015, two electrical switchgear buildings and the non-radioactive liquid waste disposal system have been turned over from Construction to Startup. This paper discusses the turnover process, organizational interfaces, and experiences from a Plant Engineering perspective. (authors)

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