Engineering Papers⌕ Search

SEARCH · Engineering Papers

Results for “DECONTAMINATION”

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.

Quote a phrase for an exact phrase match. Source license links do not imply unrestricted reuse.

At least 577 records · Page 32

Deactivation of the K-27 building at the east Tennessee Technology Park - 15554

In 1942, nearly 24,280 hectares (60,000 acres) of east Tennessee landscape became part of the most significant defense strategy in the history of the United States - the Manhattan Project. Three methods of uranium separation were pursued at the site in the effort to end World War II. What became the K-25 site, now known as the East Tennessee Technology Park, focused on the gaseous diffusion method of uranium enrichment. This paper focuses on the deactivation of the second of five gaseous diffusion plants built on the site. The four-level, rectangular-shaped K-27 came online in 1945 and was tied to the site's original gaseous diffusion plant, K-25. K-27 extended K-25's enriching stages to increase production. The plant supported weapons production and other security strategies until 1964. K-27 spans 35,582 square meters (383,000 square feet) and contains approximately 92,903 square meters (one million square feet) of floor space. During deactivation, workers will use an assembly line process to tackle the 540 process stages housed in 90 cells. While often the less publicized, less visible aspect of building decontamination and decommissioning, deactivation takes more than three times longer than demolition. Crews work in high-risk, high-hazard environments - exposed to extreme temperatures, radiological and chemical contaminants, and deteriorating infrastructure. Therefore, worker safety becomes the most rigorous task performed. K-27 is the fifth and final gaseous diffusion building in the Department of Energy's Oak Ridge Environmental Management program to be demolished. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

Hanford building 324 REC hot cell decommissioning approach - 15484

The 324 Building is a facility located at the Hanford Site and is undergoing decontamination and demolition (D and D) activities by Washington Closure Hanford (WCH). In October 1986, an in-cell leak of approximately 1.3 million curies occurred with a substantial fraction being lost into the subsurface soil beneath the floor of a large hot cell complex. Sampling under the hot cell floor revealed hot spots in the soil and cobble reading in excess of 10,000 R. In January of 2014, WCH contracted an AREVA lead team with Kurion as primary design agent to remove the B-Cell floor and highly contaminated underlying soils. The objective of this project is to remove the contaminated debris and soil and repackage them into the existing adjacent hot cells for final disposition as monoliths. The approach to this project uses an innovate combination of existing cell equipment, commercial equipment, and special tools to perform a series of completely remote operations. Also, a novel waste handling approach allows all the highly radioactive waste to remain within the existing cells. The remote handling approach to this project is to use customized off-the-shelf excavators which are mounted and operated remotely inside the cell. These can be moved and replaced remotely with a -Plug-and-Play- connection method. All the cables and utilities for the excavator and tools are managed through this cell connection with connections in a worker-accessible gallery space. The remote excavators are wall-mounted, which frees up the floor for the excavator work. The design also includes a transfer barrier which allows the B-Cell door to remain open during waste transfers while preventing spread of contamination between cells. The project balances the use of existing cell equipment such as cranes and shield doors, with the use of new remote equipment Existing equipment will be removed from the floor of the hot cell to adjacent cells. The concrete floor and stainless steel liner will then be remotely cut and removed, revealing the contaminated soil beneath the cell. The contaminated soil will be mixed with grout in the cell using the excavators and then placed in rigid bins. These bins will then be placed in the adjacent cells using existing overhead cranes. The waste containers allow optimal utilization of the limited adjacent hot cell space and improve the characteristics of the final waste monolith package. The system will use each bin once which significantly decreases the risk of contamination spread. The project includes a full-scale mockup facility in which all installation and operational activities will be tested and proven prior to hot cell construction activities. The mockup facility will also be used for operator training before actual hot work starts. This facility will remain available for use during operations with a full set of spares for redundancy and to support operations modeling during construction and remediation activities. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

Removing of Core Constructions of the MR and RFT Reactors in NRC 'Kurchatov Institute' - 16054

In frame of the FTP 'Providing nuclear and radiation safety of Russia in 2008 and for the period till 2015' works of a decommissioning of the MR and RFT research reactors are carried out in National Research Center 'Kurchatov Institute'. Within these works, the equipment of 9 loop-back facilities of the MR reactor was dismantled. In the conditions, which are most approached to natural, one researched a heat, hydrodynamic and strength characteristics of elements of cores and the capital equipment of the majority of power reactors at these facilities. In 2014-2015 dismantle of core constructions of the MR reactor was carried out and dismantle of a graphite laying of the RFT reactor is begun. The beryllium blocks, which were constructional elements of the core, and the graphite blocks playing a reactor reflector role were also taken, packed into cases or containers and removed: part on an accumulative platform, and part are placed in storage of high level radioactive waste of the Center for decay and further sending for long storage. Works were performed by remote controlled mechanisms, control of their performance was exercised by means of remote diagnostics: Gammavizor, the scanning spectrometer systems. The following methods and the organizational principles were applied to providing of radiation safety of these works: - the constant radiation control including individual control of a dose of external radiation, control of volume activity of radionuclides in air, annual control of internal radiation doses of the personnel; - dust suppression and fixing of radioactive contamination by dispersion of polymeric structures; - carrying out decontamination on a shift basis rooms with use of detergents; - use of the remote controlled mechanisms equipped with hydraulic scissors, nippers, application of the diamond are sharp that allowed to perform the majority of technological operations remotely, using 'cold' methods of fragmentation; - development on each type of works of the operation project and schedules. As a result, of works of 2011-2014 of the decommissioning of the MR and RFT research reactors more than 630 t of the equipment were dismantled. From them more than 455 t of radioactive waste was. The total activity of radwaste exceeded 300.0 GBq. From the pool of the reactor, about 160 channels of loop-back installations and near 230 beryllium and graphite are taken, fragmented and packed. The total activity on radionuclides {sup 60}Co and {sup 137}Cs of them was near 55 TBq. From the territory of the center about 2550 m{sup 3} of firm and 4600 m{sup 3} of liquid radwaste are removed. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

Radioactive Waste Water Treatment for Fukushima Daiichi Nuclear Power Plant - 16081

The Great East Japan Earthquake of 11 March 2011 caused serious damage to the Fukushima Daiichi Nuclear Power Station (NPS) of the Tokyo Electric Power Company, Inc.. Toshiba and Shaw/AVANTech installed a Simplified Active Water Retrieve and Recovery System (SARRY{sup TM}) to remove radioactive cesium (Cs) from the contaminated water. Toshiba, in partnership with EnergySolutions, also developed and installed the Multi Radionuclide Removal System (MRRSTM), which can remove radioactive nuclides being treated, except tritium, to a level less than the concentration limit in water. As contaminated water treatment has progressed, the composition of the contaminated water has changed. Both salinity and radioactive Cs concentration in the contaminated water have been decreasing. Thus, a new adsorbent that is suitable for the present water chemistry conditions is required. In order to provide an appropriate contaminated-water treatment system, Toshiba has been examining the removal of not only radioactive Cs but also radioactive strontium (Sr) by SARRY{sup TM}. SARRY{sup TM} has been operated for removing Cs by using a Cs adsorbent. Instead of a Cs adsorbent, a new media that has high selectivity for both Cs and Sr should be installed. This paper describes the results obtained when using the newly developed adsorbent for removing Cs and Sr at once. As the Cs and Sr adsorbent, we have selected crystalline silico-titanate (CST). The distribution coefficient (K{sub d}) of CST was determined by the batch method. The lifetime of the adsorbent was evaluated by a column examination. The selected CST had a K{sub d} value of over 10{sup 4} ml/g for both Cs and Sr. The highest-selectivity CST had a lifetime (defined as the period for the outlet concentration to decrease to one tenth of the inlet level) of more than 125000 BV (bed volume) for Cs and more than 18000 BV for Sr, when the test was conducted at 10 BV/h. Calculation code was also developed for estimating the relation between the BV and the decontamination factor (DF) using an adsorption rate model for diffusion and adsorption. The calculation results of the Cs and Sr adsorption behavior agreed well with the experimental results. To evaluate the replacement cycle of adsorption tower in actual equipment, the radiation exposure during the replacement operation and the required Cs and Sr removal performance were used as limiting conditions for the estimation. The results of the evaluation showed that the selected CST has sufficient performance for practical usage. Based on this finding, Toshiba proposed loading the CST in SARRY{sup TM}, and SARRY{sup TM} loaded with this CST started removing Cs and Sr in December 2014 resulting in decreased contaminated water. It has been continuously working since then. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

Observation Technology for Remote Operation in Contaminated Turbid Water - 16113

Remote underwater work in contaminated tanks and pools is one of major decontamination and decommissioning works under high-dose radiation environment. Generally, in this kind of work, visual information obtained by a camera (an optical camera) is limited due to turbid water caused by suspended sludge particles in the water and it makes remote underwater work difficult to be performed safely and efficiently. Therefore, some alternative observation methods to optical cameras have been required. In order to satisfy this requirement, the alternative observation technology which can obtain visual information in contaminated turbid water has been developed since 2014. It is a technology using an acoustic imaging system in a designated airtight container. It provides the visual information in real time regardless of turbidity without significant contamination of any parts of the system. Also, it is able to provide the location information of underwater objects with contactless. This paper will present development details of this innovative observation technology and its effectiveness to various remote works in contaminated turbid water. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

Synthesis of Bismuth Functionalized Grapheme Oxide for Radioactive Iodine Gas Removal - 16114

Released radioactive iodine from nuclear reactors and nuclear severe accidents, such as those experienced at Chernobyl and Fukushima, is one of the most hazardous materials and can affect human health. Uptake of radioactive iodine from gaseous and aqueous waste, consisting of mainly organic forms such as methyl iodide and elemental iodine after reacting with organic matter in scrubber process, is a recent concern during nuclear power plant operation. In general, Triethylenediamine (TEDA) or KI-impregnated activated carbons, silver-loaded silica aerogels, and silver-loaded zeolite are used to remove radioactive iodine compounds. However, previous research has shown TEDA and KI-impregnated activated carbons to have some limitations for use in responding to severe accidents or in pressurized-water reactors, because they are easily burned up and the iodine removal efficiency of silver-loaded sorbents is greatly decreased at high temperatures. To improve the capability of synthesized sorbent material used in iodine gas removal, highly efficient sorbents for methyl and elemental iodine removal were prepared through the functionalization of graphene oxide (GO) with bismuth. GO was synthesized from natural graphite powder (99.95%) by the modified Hummers method, and then mixed with Bi(NO{sub 3}){sub 3}.5H{sub 2}O. After developing a sorbent for the removal of iodine, the synthesized sorbent was characterized using x-ray diffraction, a scanning electron microscope/energy dispersive spectrometer, and thermogravimetric analysis/differential scanning calorimetry, and the surface area of sorbents was determined using the BET-N{sub 2} adsorption method. Methyl iodine batch experiments were conducted for 7 days and elemental iodine gas adsorption experiments were conducted at high temperature (190 deg. C) using a carrier gas (air). The final concentration of iodine in batch and off-gas scrubber solutions (0.1 M NaOH) was analyzed using inductively coupled plasma mass spectrometry. The breakthrough curve and decontamination factor values were also investigated using bismuth-functionalized GO and the results were compared with Ag-zeolite, Sn-apatite, and activated carbon. (authors)

77 NANOSCIENCE AND NANOTECHNOLOGY↗

Decommissioning of NPP in Europe? Strategies, Risks and Opportunities - 16124

This paper offers a strategic perspective on the rapidly developing European nuclear decommissioning scene, with a particular focus on the German market. We will identify a number of strategic themes that might be interesting to international companies practicing in decommissioning. The market size and valuation has received attention in several studies published in the last three years due to political concerns surrounding the funding of decommissioning. This paper will focus mainly on the decommissioning and decontamination (D and D) of Nuclear Power Plants (NPPs), commercially operated reactors generating electricity for power grids. There is also a substantial developing market also in D and D of fuel cycle facilities, research reactors and military production sites. However, they represent a rather different technical and financial challenge so will not be explored here. Further, we also restrict our geographic scope to European Union members and Germany in particular, to ensure our observations offer specific value. Our principal contention is that the German national industry holds too little capacity to fully undertake its own decommissioning program; leading to a conclusion that the European program as a whole will require significant support from international companies. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

LaserSnake2: Remote High Powered Laser Cutting in Confined Hazardous Spaces - 16161

LaserSnake2, a UK collaborative project, seeks to deliver remotely operated cutting techniques into high hazard nuclear environments. This paper describes the developments and results of combining proven robotic manipulators with high-powered laser cutting tools, to allow for selective dismantling within complex nuclear process cells. Decommissioning old and poorly catalogued nuclear plant is a problem faced the world over. Designed with little consideration for decommissioning, or adapted significantly from the original drawings, legacy plant and infrastructure is full of spaces where it is undesirable or impossible to send people. Typically, a process cell or cave will require modification to ensure suitability for human entry or deployment of heavy duty equipment to complete the decontamination processes. The process of widening access routes, or selectively moving sections of highly contaminated material, is ideally suited to remote handling technology. The results of TWI's research into fibre-delivered laser cutting techniques, and integration with a dexterous snake-arm robot, are presented. Coupled with novel laser process head design and diffractive optical elements, the result is an integrated system capable of cutting up to 100 mm thick C-Mn steel plate at significant stand-off distances, encompassing the range of infrastructure found in a typical nuclear plant. Two options have been considered for deployment of the laser cutting tool. The first is focused on a fixed installation using a standard industrial robot. The second is a large, highly flexible snake-arm robot capable of entering cluttered cells through existing penetrations. Designed to operate through a standard 11'' MSM port, the 4.5 m snake-arm robot has the capacity to carry grippers, sensors or the laser cutting tool at the tip. The snake-arm is sealed and housed within a glove box for contamination control, allowing operation within a radioactive environment. Significant technical developments and material research are presented which have led to improved operational life, payload and bend. This paper describes the series of inactive trials which have been conducted to demonstrate the LaserSnake2 system's capabilities. These include: horizontal and vertical deployment, underwater operation, object manipulation and laser cutting. With global nuclear decommissioning costs running in to the $trillions, safe and cost efficient tools such as the LaserSnake2 system are essential as part of the decommissioning toolbox. Remote handling can account for up to 20% of a decommissioning project's costs, however significant time and financial savings can be made by utilising this new technology to reduce operator exposure and reach previously inaccessible areas. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

Waste Management 2016 300-296 Soil Remediation Project. Developing Innovative Solutions to Overcome Design Challenges - 16229

The 324 Building is a non-reactor, Hazard Category 2, Nuclear Facility located in the 300 Area of the U.S. Department of Energy (DOE) Hanford Site, located near Richland, Washington. The building is undergoing deactivation, decommissioning, decontamination, and demolition by Washington Closure Hanford (WCH) under the River Corridor Closure Contract. During the Cold War Era, the facility was used for chemical and radionuclide processing associated with nuclear weapons production. Historical records indicate that in October 1986, approximately 516 L of a concentrated liquid waste stream containing cesium-137 and strontium-90 was spilled onto the floor of B-Cell. B-Cell is located in the Radiochemical Engineering Complex (REC) of the 324 Building. It is estimated that this spill contained approximately 1.3 million curies of radioactivity. Some fraction of the spill was recovered; however, an unknown quantity was released into the soil beneath the 324 Building through an undetected breach in the B-Cell floor sump. Unknown quantities of water were used after the spill to wash items contained in B-Cell. When B-Cell was taken out of service, wastes being removed from B-Cell were placed in Grout Containers (GCs) and stabilized using a particulate grout. In the course of grouting activities, grout was spilled on the floor of B-Cell, eventually filling the sump. The primary scope of this project is to design, test, and implement a process capable of removing and isolating contaminated soil below B-Cell. This remediation effort has been divided into two removal zones identified as the primary and secondary removal zones. Based on current assumptions and estimates, the primary phase of this cleanup effort will remove roughly 156.45 m{sup 3} of highly contaminated materials. B-Cell debris, particulate grout, and the floor slab and liner comprise about 21.24 m{sup 3} of the total. The remaining 135.21 m3 will be contaminated soil. All of this material must be disposed of within the existing 324 Facility or packaged for disposal at the Hanford site. The objective of this project is to remove the B-Cell floor and highly contaminated underlying soils from beneath B-Cell using remote equipment to reduce the radiation levels and allow open-air excavation for the remaining contaminated soil. The challenges and subsequent technological solutions encountered from the Conceptual Design phase to the 100% Design Issued For Fabrication/Issued For Construction (IFF/IFC) consisted in part of the following: Design an efficient remote cleanup strategy for highly contaminated Low Level Waste (LLW) given the unknowns. Maintain contamination control down to 18 feet below B-Cell in a highly radioactive environment (12,870 R/Hr Cs-137 and Sr-90). Perform facility upgrades to enable remediation process implementation while maintaining integrity of pre-existing facility structure and license. Designing first-of-a-kind remote equipment for use in high radiation areas. Developing first-of-a-kind operations sequences for remote equipment while minimizing usage of original facility equipment (i.e. cranes, manipulators, etc.). Conducting time-motion studies of operations sequences to maximize efficiency while keeping dose As Low As Reasonably Achievable (ALARA) in a high dose environment. Construction of a full scale mockup to conduct performance testing in a clean environment and train the work force to operate the equipment. Overcoming scope, budget and schedule constraints associated with a fast-track DOE project. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

Demonstration of SuperLig{sup R} 605 and SuperLig{sup R} 644 in a Regeneration Flow Sheet to Remove Radioactive Strontium and Cesium from Seawater - 16236

Remediation techniques are needed for efficient removal of radioactive strontium and cesium from seawater. Molecular Recognition Technology, using selective SuperLig{sup R} resins, demonstrates a clean chemistry approach to solving this problem. Molecular Recognition Technology offers high levels of separation of chemically pure metal contaminants, whose subsequent disposal is compatible with simple waste forms (grout and glass). SuperLig{sup R} resins can be regenerated with common reagents and used many times, limited by a dose of 1 E+9 Rad, which assures low volumes of secondary solid waste. The metal selectivity of the SuperLig{sup R} resin ensures that the solid waste is of low residual activity. These properties of sustainability are illustrated in a project that demonstrated the ability of two SuperLig{sup R} resins to selectively remove Cs and Sr from a seawater mimic representative of the contaminated seawater in Fukushima, Dai'ichi, Japan harbor. Removal of radioactive Sr-90 and Cs-134/Cs-137 from seawater using conventional ion exchange or a complexing agent is complicated by the presence of large excesses of competing ions such as Na, K, Ca, and Mg, which can be co-extracted. These competing ions, if co-extracted, reduce the capacity of a single pass resin with the consequent increase in volume of spent resin or decrease in capacity of a regenerable resin. The successful demonstration reported in this study has shown the ability of two proprietary resins, SuperLig{sup R} 605 and SuperLig{sup R} 644, to remove Sr and Cs, respectively, with high selectivity from simulated solutions containing these metal ions together with major constituents of seawater at their normal concentrations. This effort was part of a demonstration project to investigate methods for removal of Sr-90 and Cs-134/Cs-137 from 160,000 cubic meters of seawater impounded at Fukushima, Dai'ichi, Japan harbor. SuperLig{sup R} resins can be regenerated by elution with small volumes of simple acid solutions. SuperLig{sup R} resins have a high tolerance to radiation, with their performance not being degraded by doses of 1.0 E+9 Rad. Estimates, based on the results obtained, are that Cs and Sr levels in the volume of seawater in the Fukushima, Dai'ichi, Japan harbor could be reduced to desired discharge limits in 200 days with some 30 cubic meters of the two SuperLig{sup R} resins and that decontamination factors of 10 or more could be achieved. Results of the demonstration, together with advantages of the Molecular Recognition Technology process over conventional procedures for these separations are presented and discussed. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

The Importance of Experience Based Decommissioning Planning - 16242

Decommissioning of a nuclear facility is an extensive and multidisciplinary task which involves the management and technical actions associated with ceasing operation and thereafter the step by step transfer of the facility from an operating plant to an object under decommissioning. The decommissioning phase includes dismantling of systems and components, decontamination and clearance, demolition of buildings, remediation of any contaminated ground and finally a survey of the site. Several of these activities generate radioactive or potentially radioactive waste which has to be managed properly prior to clearance or disposal. What makes decommissioning of nuclear installations unique is to a large extent the radioactive waste management. No other industries have that complex regulatory frameworks for waste management. If a decommissioning project in the nuclear industry does not consider the waste aspects to the extent required, there is a large risk of failure causing a reduced trust by the regulators and other stakeholders as well as cost and schedule overruns. This paper will give an overview of important aspects and findings gathered during decades of planning and conducting decommissioning and nuclear facility modernization projects. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

Waste Estimation from a Wide-Area Radiological Incident: The Impact of Geography and Urban Footprint - 16256

In the planning and preparedness stages for a response to a radiological incident, it is important to include waste management considerations when developing the decontamination/demolition/cleanup approach because waste management can be a driver for time and cost for return to normalcy. Waste management is also inextricably linked to the geography and urban footprint of the impacted area. The U.S. Environmental Protection Agency's (EPA's) Waste Estimation Support Tool (WEST) is a novel application based on the Federal Emergency Management Agency (FEMA) Hazus-MH software. WEST enables users to estimate the characteristics, amount, and residual radioactivity of waste generated from remediation and cleanup activities after a radiological incident, including incidents caused by radiological dispersal devices and improvised nuclear devices, as well as nuclear power plant accidents. These waste estimates are generated as a function of user-defined decontamination strategies and are specific to a geographic location. This paper will describe the recently released version 3 update to WEST, and how differences in geography and urban footprints can impact the waste that is generated. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

Treatment of LLW Components for Waste Minimization and Recycling - 16258

The Studsvik Melting Facility has been in operation for almost 30 years. Many turbines, heat exchangers and other retired components, pipes, structures have been treated in the facility during those years. The ambition of all projects is to minimize the waste volumes for final disposal and to maximize the amount of material that can be recycled. Another objective, respecting ALARA, is to keep dose exposition to the personnel at very low levels. The overall concept comprises the whole sequence of preparations from road and sea transports, the management of the metallic LLW by segmentation, decontamination and sorting using specially devised tools and shielded treatment cell, to the decision criteria for recycling of the metals, radiological analyses and conditioning of the residual waste into a final form suitable for customer-related disposal. The records show that the amount of material possible for conditional clearance to open market after treatment is between 95 - 97 % on weight for falling metallic scrap. For large components there is a larger span and especially for heat exchangers. This paper describes the Studsvik technical concept and experience related to treatment of metals from the program for modernization and power upgrade of the Swedish nuclear power plants. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

Survey and Remediation Project at the DOE Bannister Site - 16280

The Department of Energy Kansas City office has operated the Bannister site with a variety of contractors since the late 1940's. This facility has had a number of missions, some of which included using natural and depleted uranium. In order to prepare for the demolition of the site, ANTECH was contracted to perform radiometric surveys of the areas where these uranium operations took place. In the process of performing these surveys, areas with low levels of fixed radioactive contamination were identified; ANTECH then remediated these areas using a variety of techniques. In all areas surveyed, the only radioactive contaminant of interest was uranium and members of its decay chain. In no cases were other radionuclides found. The detection equipment used for the surveys included a Ludlum model 239- 1F Floor Monitor, a Ludlum 2360 Alpha Beta Data Logger Scaler/Ratemeter, and an ORTEC IDM-200-V High Purity Germanium Detector. The Ludlum instruments were used for bulk surveys and the ORTEC instrument was used to determine an accurate radioactive background spectra and subsequent spectra for areas where radioactive contamination was identified. Contamination was located on concrete floors and columns, cinder block walls, steel beams, inside ductwork and in floor drain piping. After these areas were identified, a number of methods were used to remove the contamination for disposal including scabbling, core drilling and wholesale removal. Extensive use of Pentek scabbling equipment on the concrete sections proved to be very effective at removing the contaminated layer. Upon completion, the waste materials were consolidated and packaged in a strong tight sea land container and shipped to the Energy Solutions waste facility in Utah. The completed work at the Bannister site serves as an example and demonstration of an effective and comprehensive decommissioning project. It involved the integration of a variety of decommissioning activities all executed and managed by a single contractor. These included radiometric measurement surveying using a variety of detection technologies to identify and locate uranium contamination, decontamination and removal of low level radioactive waste including some deconstruction activities and finally the management of low level radioactive waste including packaging, consignment and shipping of waste to a remediation site. The effective and efficient identification and removal of radioactive contamination at the Bannister site has contributed to the overall goal of returning the site to unrestricted use. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

GrayQb Single-Faced Version 2 Open Environment Test - 16344

The GrayQb{sup TM} Single Faced Version 2 (SF2) is a non-destructive examination device developed to generate radiation contour maps showing source locations and relative radiological levels present in an area under examination. This device allows for characterization of radioactively contaminated areas such as hot cells, gloveboxes, small and large rooms, hallways, and waste tanks. The goal of GrayQb{sup TM} (pronounced 'Gray Cube') is to provide a low cost easily deployable device to aid in the process of decontamination and decommissioning (D and D). The GrayQb{sup TM} SF2 device is approximately a six inch cube weighing seven (7) pounds composed of a tungsten shield with integrated collimator, radiation imaging medium (Phosphor Storage Plate), and digital camera. This paper details the design upgrades incorporated into the new version of the GrayQb{sup TM} SF2 device and the characterization testing of this upgraded device. Device results from controlled testing performed at the Savannah River Site (SRS) Health Physics Instrument Calibration Laboratory (HPICL) are presented, as well as results from the open environment field testing performed in the E-Area Low Level Waste Storage Area. Follow on work performed deploying the GrayQb SF2 device at the Hanford Plutonium Reclamation Facility (PRF) to assist in the radiological characterization of the canyon will also be presented. Testing of the redesigned GrayQb{sup TM} SF2 device demonstrated its ability to detect low energy isotopes, e.g. Am-241 and Pu-238, not only indoors in controlled environments with well-defined source locations, but also in open environment field areas with a significant high energy background. Additionally, it was demonstrated that the device could detect higher energy isotopes (Cs-137 and Co-60) in a controlled setting and with additional testing and/or modifications to device and software, would likely be able to detect these isotopes in the open environment field testing. Follow on 2015 work performed at Hanford proved GrayQb to be a useful tool in the radiological characterization of the PRF canyon. Distribution tendencies of the radiological hot spots were identified that provided insights which will assist in more efficient planning of the continued D and D effort. Hot spots were identified which can be targeted during the future D and D effort and used as markers during the NDA assessment to quantify the radiological environment. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

Deep Borehole Disposal Waste Emplacement Mode Cost-Risk Study - 16346

An engineering study has developed alternative concepts for waste packaging and for emplacing/retrieving packages in deep boreholes. The study compared costs and risks associated with emplacement using wire-line vs. drill-string technologies. Selection of a method is needed to proceed with demonstration as part of the Deep Borehole Field Test being conducted by the U.S. Department of Energy, Office of Used Nuclear Fuel Disposition. Each emplacement method was described as a series of steps, and each step was analyzed for potential to cause any of four off-normal events including drops and getting stuck. Each such event was supported by a fault tree. The hazard analysis identified a number of improvements including: 1) impact limiters; 2) safety systems; 3) instrumentation; and 4) methods to mitigate casing collapse or borehole debris during operations. Off-normal events were related in a top-level event tree with normal and off-normal outcomes. Costs were estimated for each outcome (including recovery and decontamination). A panel of subject matter experts was convened to review the study and provide key inputs. The wire-line method is less costly for normal operations, while the drill-string method has advantages if waste packages become stuck. The wire-line method has a lower aggregate probability of accidents resulting in waste package breach. The integrated probability of off-normal events is on the order of a few percent per borehole, and engineered measures are quite important to prevent and mitigate accidents, limiting radiological consequences. Development of these measures during design will help to further improve system reliability. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

Utilization and Application of Kurion Mobile Processing System in Remediation of Radioactively Contaminated Water - 16370

Kurion{sup R} Mobile Processing Systems (KMPS) were deployed in Fukushima as first-of-a- kind at-tank isotope removal systems to remediate Sr from reverse osmosis concentrated salt water. The systems were successful in their efforts and achieved their decontamination and availability goals. The use of KMPS has been considered for other applications where a modular system is of benefit. The use of different Kurion Ion Specific Media (ISM) allows for precision removal of hazardous ions from a variety of waste streams. This paper describes a range of projects in which KMPS modularity will benefit the nuclear industry. The KMPS is a flexible system that can be deployed quickly and efficiently. One treatment system option being considered is the utilization of a KMPS for the removal of contamination from groundwater. Similar to its use in Japan, the KMPS can be sent to remote locations for the direct treatment of ground water. In particular, there are several sites across the world where uranium contamination is a problem. Uranium treatability testing was performed on collected groundwater samples from a radiologically contaminated site. The tests were used to help provide designs for KMPS modifications. These designs included the addition of chemical treatment module for the control of pH and other chemistry, the addition of an ultraviolet module for the destruction of biological material, among others. The tests determined the loading capacities of uranium capture resins (UCR) and media (UCM) for this specific waste stream. Based on uranium loading capacities of 37.3 mg/L (end of test C/C{sub 0} = 0.5) and 54.6 mg/L (extrapolated to C/C{sub 0} = 0.98), and the longevity of the resin (45,911 BV for C/C{sub 0} = 0.5, and 80,556 BV for C/C{sub 0} = 0.98) UCR-1 was selected as the media/resin to be proposed for a uranium treatment system. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

Characterization and Clearance of m/s Sigyn - 16412

M/s Sigyn was a 2044 ton ship that transported contaminated material between 1982 and 2013. Most of the transports were with spent nuclear fuel between Swedish nuclear power plants and the Swedish fuel repository, Clab. In addition to spent fuel, m/s Sigyn also transported big contaminated components, from nuclear power plants in Europe, to Studsvik for analysis or decontamination and melting. She also transported components from Swedish nuclear power plants to final disposal of short lived waste, SFR. Even though all transported items have been cleaned, checked and wrapped with plastics, some activity ended up as contamination onboard. In December 2013 it was decided that m/s Sigyn was subject for decommissioning due to her age. This Paper describes the method in which the activity onboard m/s Sigyn was characterized and clearance levels were calculated. This method for radiological characterization and clearance has recently been developed in Sweden, the method is efficient in that it does not need a big pre characterization survey. Only the nuclide distribution and history of the object, is needed to start the final survey. In the future there will be further development of the method, making it possible to reduce the number of measurements even more. This will further optimize the method and reduce the cost for final surveys and clearance. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗