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A Nondestructive Assay System for use in Decommissioning a Plutonium-Handling Facility

Description: Argonne National Laboratory is decommissioning a facility used to fabricate reactor fuel elements. The equipment is contaminated with alpha emitters. The objective of decontamination is to reduce the TRU concentrations below 10 nCi/g of waste. A portable NDA procedure using Na I (TI ) gamma-spectrometric techniques was selected to measure the residual Pu and 2i 1 Am in the glove boxes. Assays were performed at different stages in the decontamination process to estimate the detection system sensitivity and the effectiveness of the cleaning efforts.
Date: July 1979
Creator: Argonne National Laboratory. Special Materials Division. Nondestructive Assay Section.
Partner: UNT Libraries Government Documents Department

Action Memorandum for Decommissioning of TAN-607 Hot Shop Area

Description: The Department of Energy is documenting the selection of an alternative for the TAN-607 Hot Shop Area using a Comprehensive Environmental Response, Compensation, and Liability Act non-time-critical removal action (NTCRA). The scope of the removal action is limited to TAN-607 Hot Shop Area. An engineering evaluation/cost analysis (EE/CA) has assisted the Department of Energy Idaho Operations Office in identifuomg the most effective method for performing the decommissioning of this structure whose mission has ended. TAN-607 Hot Shop Area is located at Test Area North Technical Support Facility within the Idaho National Laboratory Site. The selected alternative consists of demolishing the TAN-607 aboveground structures and components, removing belowground noninert components (e.g. wood products), and removing the radiologically contaminated debris that does not meet remedial action objectives (RAOs), as defined in the Record of Decision Amendment for the V-Tanks and Explanation of Significant Differences for the PM-2A Tanks at Test Area North, Operable Unit 1-10.
Date: May 1, 2007
Creator: Pinzel, M. A.
Partner: UNT Libraries Government Documents Department

Action Memorandum for General Decommissioning Activities under the Idaho Cleanup Project

Description: This Action Memorandum documents the selected alternative to perform general decommissioning activities at the Idaho National Laboratory (INL) under the Idaho Cleanup Project (ICP). Preparation of this Action Memorandum has been performed in accordance with the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA), as amended by the "Superfund Amendments and Reauthorization Act of 1986", and in accordance with the "National Oil and Hazardous Substances Pollution Contingency Plan". An engineering evaluation/cost analysis (EE/CA) was prepared and released for public comment and evaluated alternatives to accomplish the decommissioning of excess buildings and structures whose missions havve been completed.
Date: October 26, 2006
Creator: Reno, S. L.
Partner: UNT Libraries Government Documents Department

Keys to Successful D&D Technology Deployments at the INEEL

Description: Seven improved decontamination and decommissioning (D&D) technologies were successfully deployed at the Idaho National Engineering and Environmental Laboratory (INEEL) during the Accelerated Site Technology Deployment (ASTD) Integrated Decontamination and Decommissioning (ID&D) project. The use of these improved technologies saved the INEEL $462K in fiscal year 1999, and is projected to save about $14M over the next ten years. Since deploying new technologies on D&D projects shows great potential for cost-savings, factors that led to successful deployment have been documented. These factors are described here as they apply to the seven deployments at the INEEL to assist with deployments at other DOE sites.
Date: April 1, 2000
Creator: Smith, Agatha Marie; Meservey, Richard Harlan & Tripp, Julia Lynn
Partner: UNT Libraries Government Documents Department

A NEW APPROACH TO DEVELOPMENT OF VOLUNTARY DECOMISSIONING STANDARDS

Description: The purpose of the Decontamination, Decommissioning, and Reutilization (DDR) Division of the American Nuclear Society (ANS) is to advance the technology of decontamination, decommissioning, and reutilization of nuclear and former nuclear installations, materials, facilities, and sites [1]. This includes sharing collective decommissioning experiences and lessons learned with others in the industry. An integral part of the work of the DDR Division is the preparation of voluntary decommissioning standards through its recently re-established DDR Standards Committee. This Committee intends to support development of various standards with other divisions of the ANS. The Committee also intends to participate with external organizations to disseminate information and lessons learned regarding decontamination activities, and participate in the development of voluntary decommissioning standards. External organizations, such as ASTM International, are involved in the development of consensus standards for nuclear decommissioning work. This paper describes the work of the DDR Standards Committee on a new co-operative initiative with ASTM International to develop voluntary consensus standards for nuclear decommissioning work.
Date: September 1, 2007
Creator: Zull, Lawrence M.; Meservey, Richard H. & Boing, Lawrence E.
Partner: UNT Libraries Government Documents Department

Constructing Predictive Estimates for Worker Exposure to Radioactivity During Decommissioning: Analysis of Completed Decommissioning Projects - Master Thesis

Description: An analysis of completed decommissioning projects is used to construct predictive estimates for worker exposure to radioactivity during decommissioning activities. The preferred organizational method for the completed decommissioning project data is to divide the data by type of facility, whether decommissioning was performed on part of the facility or the complete facility, and the level of radiation within the facility prior to decommissioning (low, medium, or high). Additional data analysis shows that there is not a downward trend in worker exposure data over time. Also, the use of a standard estimate for worker exposure to radioactivity may be a best estimate for low complete storage, high partial storage, and medium reactor facilities; a conservative estimate for some low level of facility radiation facilities (reactor complete, research complete, pits/ponds, other), medium partial process facilities, and high complete research facilities; and an underestimate for the remaining facilities. Limited data are available to compare different decommissioning alternatives, so the available data are reported and no conclusions can been drawn. It is recommended that all DOE sites and the NRC use a similar method to document worker hours, worker exposure to radiation (person-rem), and standard industrial accidents, injuries, and deaths for all completed decommissioning activities.
Date: October 1, 2002
Creator: Dettmers, Dana Lee & Eide, Steven Arvid
Partner: UNT Libraries Government Documents Department

Waste In-Situ Stabilization/Entombment Research and Development Project

Description: The technical basis and stakeholder acceptance of entombment technology is necessary before entombment becomes a decontamination and decommissioning (D&D) option for nuclear reactors. The authors present a research and development (R&D) approach addressing technical basis and stakeholder acceptance of entombment technology. The approach includes a consortium and the conceptual R&D program.
Date: September 1, 2000
Creator: Birk, Sandra Margaret; Hanson, Robert Gail & Vernon, Donald Keith
Partner: UNT Libraries Government Documents Department

PUREX Plant deactivation function analysis report

Description: The document contains the functions, function definitions, function interfaces, function interface definitions, Input Computer Automated Manufacturing Definition (IDEFO) diagrams, and a function hierarchy chart that describe what needs to be performed to deactivate PUREX.
Date: September 1, 1995
Creator: Lund, D.P. & Group, PUREX Working
Partner: UNT Libraries Government Documents Department

308 Building deactivation function analysis report

Description: The document contains the functions, function definitions, function interfaces, function interface definitions, Input Computer Automated Manufacturing Definition (IDEFO) diagrams, and a function hierarchy chart that describes what needs to be performed to deactivate the 308 Building.
Date: September 1, 1995
Creator: Lund, D.P. & Group, 308 Building Working
Partner: UNT Libraries Government Documents Department

The restoration of an Argonne National Laboratory foundry

Description: The Environmental Management Operations` Waste Management Department (WMD) at Argonne National Laboratory-East (ANL-E) undertook the restoration of an unused foundry with the goal of restoring the area for general use. The foundry was used in the fabrication of reactor components for ANL`s research and development programs; many of the items fabricated in the facility were radioactive, thereby contaminating the foundry equipment. This paper very briefly describes the dismantling and decontamination of the facility. The major challenges associated with the safe removal of the foundry equipment included the sheer size of the equipment, a limited overhead crane capability (4.5 tonne), the minimization of radioactive and hazardous wastes, and the cost-effective completion of the project, the hazardous and radioactive wastes present, and limited process knowledge (the facility was unused for many years).
Date: September 1, 1997
Creator: Shearer, T.; Pancake, D. & Shelton, B.
Partner: UNT Libraries Government Documents Department

Annual report Rockwell International Hot Laboratory decommissioning GFY 1994

Description: OAK-B135 This document presents a summary of the activities conducted during GFY 1994 on decontamination and decommissioning of the Rockwell International Hot Laboratory. This is a multi-year program to decontaminate the RIHL facility to levels that allow release for unrestricted use.
Date: April 26, 1995
Creator: Felten, L. D.
Partner: UNT Libraries Government Documents Department

Building 235-F Goldsim Fate And Transport Model

Description: Savannah River National Laboratory (SRNL) personnel, at the request of Area Completion Projects (ACP), evaluated In-Situ Disposal (ISD) alternatives that are under consideration for deactivation and decommissioning (D&D) of Building 235-F and the Building 294-2F Sand Filter. SRNL personnel developed and used a GoldSim fate and transport model, which is consistent with Musall 2012, to evaluate relative to groundwater protection, ISD alternatives that involve either source removal and/or the grouting of portions or all of 235-F. This evaluation was conducted through the development and use of a Building 235-F GoldSim fate and transport model. The model simulates contaminant release from four 235-F process areas and the 294-2F Sand Filter. In addition, it simulates the fate and transport through the vadose zone, the Upper Three Runs (UTR) aquifer, and the Upper Three Runs (UTR) creek. The model is designed as a stochastic model, and as such it can provide both deterministic and stochastic (probabilistic) results. The results show that the median radium activity concentrations exceed the 5 ?Ci/L radium MCL at the edge of the building for all ISD alternatives after 10,000 years, except those with a sufficient amount of inventory removed. A very interesting result was that grouting was shown to basically have minimal effect on the radium activity concentration. During the first 1,000 years grouting may have some small positive benefit relative to radium, however after that it may have a slightly deleterious effect. The Pb-210 results, relative to its 0.06 ?Ci/L PRG, are essentially identical to the radium results, but the Pb-210 results exhibit a lesser degree of exceedance. In summary, some level of inventory removal will be required to ensure that groundwater standards are met.
Date: September 14, 2012
Creator: Taylor, G. A. & Phifer, M. A.
Partner: UNT Libraries Government Documents Department

In-situ spectroelectrochemical studies of radionuclide contaminated surface films on metals and the mechanism of their formation and dissolution. 1997 annual progress report

Description: 'The incorporation of radioactive contaminants into corrosion product scales on metals is being investigated using in-situ spectroscopic and electrochemical techniques. To facilitate the study, stable isotopes are used initially, while the corrosion films are simulated by electrodeposition of the appropriate oxide (hydroxide) onto a graphite substrate. Synchrotron x-ray absorption spectroscopy (XAS) is used to determine the structure and composition of the host oxide film, as well as the local structure of the impurity ion. Results on the incorporation of Sr and Ce into surface films of Ni(OH){sub 2} and NiOOH are reported. Cathodically deposited Ni(OH){sub 2} was found to be mainly in the {alpha} form while anodically prepared NiOOH consists of Ni{sup +2} and Ni{sup +4} phases. Sr in the films consists mainly of Sr{sup 2+} which appears to be coordinated to oxygen atoms and is likely to exist as small domains of co-precipitated material. Ce in Ni(OH){sub 2} exists mainly as Ce{sup +3} and as a Ce{sup +4} species when co-deposited with NiOOH. The structure of the Ce{sup +4} phase appears similar to a Ce(OH){sub 4} standard. However, x-ray diffraction and laser Raman measurements indicate that the latter chemical formulation is probably incorrect and that the material is more likely to be a disordered hydrous cerium oxide. Ce chemisorbed on Ni(OH){sub 2} and NiOOH films is predominantly in the +3 valency state. Iron oxide films prepared by anodic deposition from borate buffer solution containing Fe{sup +2}, has been found by XAS to consist mainly of {alpha} FeOOH. The latter has been found by others to be the constituent of the corrosion film on iron; this lends credence to the present simulation approach. Future work will involve studies on the incorporation of radioactive Sr, Ce, and Cs, as well as U, into nickel and iron oxide films. Investigations on the ...
Date: September 1, 1997
Creator: Melendres, C.A.; Balasubramanian, M.; Papapanayiotou, D.; Mini, S. & Mansour, A.N.
Partner: UNT Libraries Government Documents Department

Atmospheric-pressure plasma cleaning of contaminated surfaces. 1998 annual progress report

Description: 'The object of this research program is to develop an atmospheric-pressure plasma jet for converting transuranic wastes (TRUs) into low-level radioactive wastes (LLWs). This plasma process will be used to efficiently decontaminate a wide range of structures and equipment. This report summarizes work after 1 year and 9 months of a 3-year project. A picture of the atmospheric-pressure plasma jet is shown in Fig. 1. This new plasma source consists of two concentric electrodes through which a mixture of helium and reactive gases flow. The plasma is ignited by applying 13.56 MHz RF power to the inner electrode. The characteristics of this discharge are different from other atmospheric-pressure plasmas, such as transferred arcs, torches, coronas and silent discharges. Shown in Fig. 2 is the current-voltage curve for the plasma jet. Spark breakdown occurs at 0.01 A, and is proceeded by a normal glow region, in which the voltage remains constant with increasing current, and an abnormal glow region, in which the voltage increases rapidly with current. At about 1.0 A and 225 V, the plasma begins to arc. The normal glow region is rarely observed in atmospheric pressure plasmas. They usually proceed directly from spark breakdown to arcing. The trend shown in the figure indicates that the plasma jet is stable over a wide range of operating conditions. The distribution of reactive species in a plasma jet, containing oxygen and helium, has been characterized by Langmuir probe measurements, optical emission spectroscopy, and ultraviolet absorption spectroscopy. The charged particle density ranges from about 5 x 10{sup 11} cm{sup -3} inside the plasma to 1 x 10{sup 10} cm{sup -3} in the jet exit. The concentration of metastable oxygen molecules (a 1 Dg and b 1 Sg{sup +} ) is estimated to be between 10{sup 12} to 10{sup 13} cm{sup -3} . ...
Date: June 1, 1998
Creator: Hicks, R.F. & Selwyn, G.
Partner: UNT Libraries Government Documents Department

Atmospheric pressure plasma cleaning of contamination surfaces. 1997 mid-year progress report

Description: 'Goals of the project are to (1) identify the key physics and chemistry underlying the use of high pressure plasmas for etching removal of actinides and actinide surrogates; and (2) identify key surface reactions and plasma physics necessary for optimization of the atmospheric pressure plasma jet. Technical description of the work decommissioning of transuranic waste (TRU) into low-level radioactive waste (LLW) represents the largest cleanup cost associated with the nuclear weapons complex. This work is directed towards developing a low-cost plasma technology capable of converting TRU into LLW, based upon highly selective plasma etching of plutonium and other actinides from contaminated surfaces. In this way, only the actinide material is removed, leaving the surface less contaminated. The plasma etches actinide material by producing a volatile halide compound, which may be efficiently trapped using filters. To achieve practical, low-cost operation of a plasma capable of etching actinide materials, the authors have developed a y-mode, resonant-cavity, atmospheric pressure plasma jet (APPJ). In contrast to conventional, low pressure plasmas, the APPJ produces a purely-chemical effluent free of ions, and so achieves very high selectivity and produces negligible damage to the surface. Since the jet operates outside a chamber, many nuclear wastes may be treated including machinery, duct-work, concrete and other building materials. In some cases, it may be necessary to first remove paint from contaminated surfaces using a plasma selective for that surface, then to switch to the actinide etching chemistry for removal of actinide contamination. The goal of this work is to develop the underlying science required for maturation of this technology and to establish early version engineering prototypes. Accomplishments to Date The authors have made significant progress in this program. The work conducted jointly at Los Alamos and at UCLA. This has been facilitated by exchange of people, equipment and designs ...
Date: June 1, 1997
Creator: Selwyn, G.S. & Hicks, R.
Partner: UNT Libraries Government Documents Department

3-D spectral IP imaging: Non-invasive characterization of contaminant plumes. 1998 annual progress report

Description: 'The overall objective of this project is to develop the scientific basis for characterizing contaminant plumes in the earth''s subsurface using field measurements of induced polarization (IP) effects. Three specific objectives towards this end are: (1) understanding IP at the laboratory level through measurements of complex resistivity as a function of frequency in rock and soil samples with varying pore geometries, pore fluid conductivities and saturations, and contaminant chemistries and concentrations; (2) developing effective data acquisition techniques for measuring the critical IP responses (time domain or frequency domain) in the field; (3) developing modeling and inversion algorithms that permit the interpretation of field IP data in terms of subsurface geology and contaminant plume properties. The authors laboratory experiments to date are described in Appendices A and B, which consist of two papers submitted to the annual SAGEEP conference (Frye et al., 1998; Sturrock et al., 1998). The experiments involved measurements of complex resistivity vs. frequency on a suite of brine saturated sandstone samples. In one set of experiments, the fluid chemistry (pH, ionic strength, and cation type) was varied. In a second set of experiments, the microgeometry of the rock matrix was varied. The experiments showed that spectral IP responses are sensitive to subtle variations in both the solution chemistry and rock microgeometry. The results demonstrate that spectral IP responses have the potential of being sensitive indicators of in-situ chemistry and microgeometry, the latter of which may be related to the hydraulic properties. Data Acquisition The authors have been looking in some detail at the effects of electromagnetic coupling and how to practically deal with it. In this area, the results to date are summarized in Vandiver (1998). The progress in the development of modeling and inversion algorithms for IP is described in Appendix C, a paper submitted to the ...
Date: June 1, 1998
Creator: Morgan, F. D.; Rodi, W. & Lesmes, D.
Partner: UNT Libraries Government Documents Department

Enhancements to and characterization of the very early time electromagnetic (VETEM) prototype instrument and applications to shallow subsurface imaging at sites in the DOE complex. 1998 annual progress report

Description: 'The objective of this project is to enhance the state-of-the-art of electromagnetic imaging of the shallow (0 to 5 m) subsurface in electrically conductive media where ground penetrating radar (GPR) provides insufficient penetration and time domain electromagnetic (TEM) systems provide insufficient resolution. This objective is being pursued by instrumentation enhancements to the existing very early time electromagnetic (VETEM) system coupled with physical and numerical modeling. Success in this endeavor will improve the speed and accuracy of waste pit and trench location and characterization, and could have additional applications to shallow DNAPL and LNAPL spill and cleanup monitoring, clay cap integrity assessment, and landfill stabilization monitoring. This could result in significant savings in time and money during characterization, remediation, and decommissioning of facilities. This report summarizes accomplishments after 8 months of a three-year project. The authors have focused mainly on instrumentation and numerical modeling during this time.'
Date: June 1, 1998
Creator: Wright, D.L. & Chew, W.C.
Partner: UNT Libraries Government Documents Department

In-situ spectro-electrochemical studies of radionuclide contaminated surface films on metals and the mechanism of their formation and dissolution. 1998 annual progress report

Description: 'The objective of this research program is to gain a fundamental understanding of the structure, composition, and mechanism of formation of radionuclide-containing surface films on metals that are relevant to the problem of decontamination of piping systems and waste storage tanks at DOE nuclear processing facilities. As of May 1998, after about a year and a half of work towards implementing this project, considerable progress has been made in understanding the mechanism and structure of heavy metal ions incorporated into simulated corrosion films of nickel. The nature of iron and chromium oxide films, which are used to model the other components of steels used in piping systems and waste storage tanks in nuclear facilities, has also been elucidated. The principal techniques used in these investigations consist of coupled electrochemical and in-situ synchrotron X-ray absorption spectroscopy, as well as vibrational spectroscopy (infrared and laser Raman).'
Date: June 1, 1998
Creator: Melendres, C.A. & Mini, S.M.
Partner: UNT Libraries Government Documents Department

Characterization of a new family of metal transport proteins. 1998 annual progress report

Description: 'Soils at many DOE sites are contaminated with metals and radionuclides. Such soils obviously pose a risk to human and animal health. Unlike organic wastes which can be metabolized, metals are immutable and cannot be degraded into harmless constituents. Phytoremediation, the use of plants to remove toxic materials from soil and water, may prove to be an environmentally friendly and cost effective solution for cleaning up metal-contaminated sites. The success of phytoremediation will rely on the availability of plants that absorb, translocate, and tolerate the contaminating metals. However, before the authors can engineer such plants, they need more basic information on how plants acquire metals. An important long term goal of the research program is to understand how metals such as zinc, cadmium and copper are transported across membranes. The research is focused on a new family of metal transporters which they have identified through combined studies in the yeast Saccharomyces cerevisiae and in the model plant Arabidopsis thaliana. They have identified a family of 19 presumptive metal transport genes in a variety of organisms including yeast, trypanosomes, plants, nematodes, and humans. This family, which the authors have designated the ZIP genes, provides a rich source of material with which to undertake studies on metal transport in eukaryotes. The project has three main objectives: Objective 1: Determine the sub-cellular location of the ZIP proteins in Arabidopsis. Objective 2: Carry out a structure/function analysis of the proteins encoded by the ZIP gene family to identify regions of the protein responsible for substrate specificity and affinity. Objective 3: Engineer plants to overexpress and underexpress members of the ZIP gene family and analyze these transgenic plants for alterations in metal accumulation. They now know that manipulation of transporter levels will also require an understanding of post-transcriptional control of ZIP gene expression. They are ...
Date: June 1, 1998
Creator: Guerinot, M. L.
Partner: UNT Libraries Government Documents Department

Optimization of thermochemical, kinetic, and electrochemical factors governing partitioning of radionuclides during melt decontamination of radioactively contaminated stainless steel. 1998 annual progress report

Description: 'Melt decontamination of radioactive scrap metal could convert a disposal liability into a final product that would reduce the total volume of material necessary for burial and save substantial material costs. The goal of this project is to optimize a melt decontamination process through a basic understanding of the factors which govern the partitioning of various radionuclides between metal, slag, and gas phases. Radionuclides which are captured by a slag phase may be stabilized by promoting the formation of synthetic minerals within a leach resistant matrix. The main focus of this project is the application of electroslag remelting (ESR) toward cleanup of surface contaminated stainless steels. This report summarizes work accomplished after 9-months of a 3-year project. Activities are ongoing at Sandia National Laboratories and at Boston University.'
Date: June 1998
Creator: van den Avyle, J. A.
Partner: UNT Libraries Government Documents Department

Seismic-reflection and ground penetrating radar for environmental site characterization. 1998 annual progress report

Description: 'The project''s goals are threefold: (1) to examine the complementary site-characterization capabilities of modern, three-component shallow-seismic techniques and ground-penetrating radar (GPR) methods at depths ranging from 2 to 8 m at an existing test site; (2) to demonstrate the usefulness of the two methods when used in concert to characterize, in three-dimensions, the cone of depression of a pumping well, which will serve as a proxy site for fluid-flow at an actual, polluted site; and (3) to use the site as an outdoor mesoscale laboratory to validate existing three-dimensional ground-penetrating radar and seismic-reflection computer models developed at the Univ. of Kansas. To do this, useful seismic and GPR data are being collected along the same line(s) and within the same depth range. The principal investigators selected a site in central Kansas as a primary location and, although the site itself is not environmentally sensitive, the location chosen offers particularly useful attributes for this research and will serve as a proxy site for areas that are contaminated. As part of an effort to evaluate the strengths of each method, the authors will repeat the seismic and GPR surveys on a seasonal basis to establish how the complementary information obtained varies over time. Because the water table fluctuates at this site on a seasonal basis, variations in the two types of data over time also can be observed. Such noninvasive in-situ methods of identifying and characterizing the hydrologic flow regimes at contaminated sites support the prospect of developing effective, cost-conscious cleanup strategies in the near future. As of the end of May 1998, the project is on schedule. The first field work was conducted using both of the geophysical survey methods in October of 1997, and the second field survey employed both methods in March of 1998. One of the stated tasks ...
Date: June 1, 1998
Creator: Steeples, D.W. & Plumb, R.
Partner: UNT Libraries Government Documents Department

ADVANTAGES, DISADVANTAGES, AND LESSONS LEARNED FROM MULTI-REACTOR DECOMMISSIONING PROJECTS

Description: This paper discusses the Reactor Interim Safe Storage (ISS) Project within the decommissioning projects at the Hanford Site and reviews the lessons learned from performing four large reactor decommissioning projects sequentially. The advantages and disadvantages of this multi-reactor decommissioning project are highlighted.
Date: February 27, 2003
Creator: Morton, M.R.; Nielson, R.R. & Trevino, R.A.
Partner: UNT Libraries Government Documents Department

Initiating the D&D Project for the EBR-II

Description: A novel decommissioning project is underway to close the Experimental Breeder Reactor-II (EBR-II) “fast” reactor at the Idaho National Laboratory (INL), Materials and Fuels Complex (MFC) facility near Idaho Falls, ID. The facility was placed in cold shutdown in 1994 and work began on the removal of the metallic sodium coolant. The bulk of the sodium was drained and treated beginning in 2001. The residual sodium heel was chemically passivated to render it less reactive in 2005 using a novel carbon dioxide treatment. Approximately 700 kg of metallic sodium and 3500 kg of sodium bicarbonate remain in the facility. A RCRA Waste Treatment Permit, issued in 2002 by the State of Idaho Department of Environmental Quality, requires annual progress toward closure of the facility, and that all regulated materials be removed or deactivated, and the waste products removed by 2022. The baseline sodium removal technology would result in about 100,000 gallons of low-level waste solution requiring treatment along with separate handling of the large components (intermediate heat exchanger, rotating plug, etc) outside of the primary tank.
Date: August 1, 2010
Creator: Demmer, Rick
Partner: UNT Libraries Government Documents Department

Final Site Specific Decommissioning Inspection Report #2 for the University of Washington Research and Test Reactor, Seattle, Washington

Description: During the period of August through November 2006, ORISE performed a comprehensive IV at the University of Washington Research and Test Reactor Facility. The objective of the ORISE IV was to validate the licensee’s final status survey processes and data, and to assure the requirements of the DP and FSSP were met.
Date: March 20, 2007
Creator: Roberts, S. J.
Partner: UNT Libraries Government Documents Department