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All sourcesNASA NTRSDOE OSTI
DOE OSTI2017

End of the (Fuel) Cycle: What can South Australia learn from the world? - 17047

This project consists of a study of five countries' nuclear waste policy histories, a review of the presence and role of bureaucracy, how these factors have influenced their citizens' attitudes towards nuclear waste and progress made towards the planning, siting and construction of nuclear waste repositories. A survey was sent to a selected stratified sub-group of the community questioning their attitude towards the location of a potential nuclear waste repository in South Australia and what the most influential factor responsible for their opinion was. France is currently in the process of converting its underground nuclear waste research facility in Bure into the country's first high-level nuclear waste repository. Sweden is also constructing an underground high level nuclear waste repository, after decades of planning, community engagement and candidate site selection processes. The Nuclear Energy Agency estimates that Switzerland will construct a low and intermediate level nuclear waste repository by 2035 and a high level nuclear waste repository by 2045. Finland will be the first country in the world to successfully construct and operate a high-level nuclear waste repository and it is expected to be operational in 2023. The project summarises the most influential factors affecting the success of five case-study countries in managing their nuclear and radioactive waste and apply them to an Australian context. It also highlights the outcome of the surveys and connects the result to those previously conducted in the five case-study countries. (authors)

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DOE OSTI2019

Deployment of a 3D Sonar System at Savannah River: Results, Implications and Next Steps - 19718

Waste solids mapping is required at SRS to support the closure of high level radioactive waste tanks. The current mapping methodologies utilize a combination of video inspections and still camera photos to record the solids location and height in the tank with interpretation by site Engineering personnel. Tank liquid level is recorded during capture of the images to determine the height of solids. If no liquid is present, the images are compared to known waste tank features (e.g., cooling coils, support columns) to determine the height of the solids. In December of 2017, NuVision Engineering and Fortis Engineering conducted a demonstration of Sonar technology in SRS F-Tank Farm (FTF) Tank 7 using three risers (Risers 1, 5, and Center) for the purposes of mapping waste solids in the tank. Tank 7 was not the ideal choice for a 'first-of-a-kind' deployment given its congested internals but was selected based on the priority of tank farm operations. Savannah River Remediation (SRR) evaluated the results of this demonstration against the current solids mapping methodologies to determine potential future application of Sonar technology to support upcoming sludge or salt waste removal, decisions to cease waste removal and perform sampling and analysis, final residuals volume determinations, and applicability for use in H-Tank Farm (HTF) Type IV tanks. The efficiency of the Sonar mapping technology against the current mapping techniques and the relative costs of each were also evaluated. The Sonar demonstration performed in the three risers of Tank 7 resulted in a tank floor coverage of approximately 26%. This limited coverage was primarily due to shadow effects and image distortions created by vertical cooling coils and support columns within the waste tank. A comparison of the images produced during the Sonar demonstration and the historical Tank 7 mapping, performed in 2011 upon completion of Bulk Waste Removal Efforts (BWRE), showed physical similarities between the mounds located near the Sonar deployment risers. The technology performed well in accurately mapping solids in those areas accessible to coverage. The Sonar mapping technology may achieve more benefits if configured to work around internal obstructions, or in a Type IV tank, where the lack of vertical cooling coils may allow for a larger coverage area. (authors)

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DOE OSTI2017

Decontamination and Decommissioning Program of a Radiopharmaceuticals Production Facility - 17103

On May 2012, Best Medical Belgium (BMB) S.A., a manufacturer of pharmaceutical products located on the nuclear site of Fleurus, was declared bankrupt. According to the Belgian law, ONDRAF/NIRAS (Belgian Radioactive Waste Management Agency) was entrusted with the clean-up and the decommissioning operations of the former BMB facilities, nowadays known as 'ONDRAF/NIRAS Site Fleurus' (ONSF). In June 2015, ONSF launched a Decontamination and Decommissioning (D and D) program, for which Tractebel supports the definition of the clean-up and decommissioning strategies; the drafting of the Final Decommissioning Plan (FDP) and License Application for decommissioning; and the follow-up of the clean-up and upcoming D and D works on site. Four nuclear buildings are part of the clean-up and D and D activities. One of them, Building 14 (B14), represents the most challenging task with the clean-up of highly contaminated areas and their further decommissioning up to greenfield. Beside its two cyclotrons successively used for the production of radioisotopes, this building features hot cells and glove boxes used for the purification of radioisotopes and the conditioning of the final pharmaceutical product. The present paper aims at presenting the development of the D and D program in terms of modifications of existing facilities to allow carrying out the clean-up and D and D activities and the management of dismantled radioactive materials in a safe, efficient and cost-effective way as well as in terms of strategic options to be developed for the FDP. To support the clean-up and D and D activities, several workshops have been designed in order to treat radioactive materials removed from the building rooms. Those workshops feature an input buffer storage area, a common output buffer storage area and installations for the treatment of radioactive materials and waste (handling devices, cutting means, decontamination means, free release measurements means, etc.). Some modifications to the existing auxiliary systems will be required in order to dispose of appropriate systems to operate those workshops in a safe way. Activated concrete structures will constitute the most important part of radioactive materials that will arise from the decommissioning activities. To limit the total decommissioning costs, and especially the costs associated to radioactive waste management, two strategies have been developed in order to manage a part of activated concrete as candidate for free release with a certain decay period or as candidate for conventional landfill. Both strategies will have to be further detailed and discussed with the competent Authorities to ensure they can actually be implemented. (authors)

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DOE OSTI2016

Inerting of Casks Cavity Atmospheres - The GNS Approach to Treat Hydrogen Generation in Sealed ILW Packages - 16043

A new approach to deal with the issue of hydrogen generation in sealed packages for radioactive waste with organic content is presented. The so-called 'inerting' of the cask cavity atmosphere can be either executed after loading or after interim storage via a new facility introduced by GNS. This new approach is approved by the German competent authority and yield to the recent prolongation of the Type B(U) certificate of approval of the GNS MOSAIK{sup R} cask. (authors)

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DOE OSTI2020

Decovalex-2019 (Executive Summary)

The DECOVALEX Project is an on-going international research collaboration, established in 1992, to advance the understanding and modeling of coupled Thermal (T), Hydrological (H), Mechanical (M) and Chemical (C) processes in geological in geological systems. DECOVALEX was initially motivated by the recognition that prediction of these coupled effects is an essential part of the performance and safety assessment of geologic disposal systems for radioactive waste and spent nuclear fuel. Later it was realized that these processes also play a critical role in other subsurface engineering activities, such as subsurface CO 2 storage, enhanced geothermal systems, and unconventional oil and gas production through hydraulic fracturing. Research teams from many countries (e.g., Canada, China, Czech Republic, Finland, France, Germany, Japan, Republic of Korea, Spain, Sweden, Switzerland, Taiwan, United Kingdom, and the United States) various institutions have participated in the DECOVALEX Project over the years, providing a wide range of perspectives and solutions to these complex problems. These institutions represent radioactive waste management organizations, national research institutes, regulatory agencies, universities, as well as industry and consulting groups. The overall aim of DECOVALEX-2019 was to increase the understanding of various thermo-hydro-mechanical-chemical processes of importance for radionuclide release and transport from a repository to the biosphere and how they can be described and modelled using mathematical models. The scientific and technical objectives are: to increase the basic understanding of T-H-M-C coupled processes in fractured rocks (crystalline, sedimentary, argillaceous) and buffer materials; to investigate the predictive capabilities of different codes to field experiments and to perform verification of codes; to exchange experimental data, and improve the understanding of the constitutive behavior of crystalline and argillaceous rock masses and buffer materials; and to perform THMC calculations in a performance/safety assessment context.

58 GEOSCIENCES↗
DOE OSTI2016

Pathways for Disposal of Commercially-Generated Tritiated Waste

From a waste disposal standpoint, tritium is a major challenge. Because it behaves like hydrogen, tritium exchanges readily with hydrogen in the ground water and moves easily through the ground. Land disposal sites must control the tritium activity and mobility of incoming wastes to protect human health and the environment. Consequently, disposal of tritiated low-level wastes is highly regulated and disposal options are limited. The United States has had eight operating commercial facilities licensed for low-level radioactive waste disposal, only four of which are currently receiving waste. Each of these is licensed and regulated by its state. Only two of these sites accept waste from states outside of their specified regional compact. For waste streams that cannot be disposed directly at one of the four active commercial low-level waste disposal facilities, processing facilities offer various forms of tritiated low-level waste processing and treatment, and then transport and dispose of the residuals at a disposal facility. These processing facilities may remove and recycle tritium, reduce waste volume, solidify liquid waste, remove hazardous constituents, or perform a number of additional treatments. Waste brokers also offer many low-level and mixed waste management and transportation services. These services can be especially helpful for small-quantity tritiated-waste generators, such as universities, research institutions, medical facilities, and some industries. The information contained in this report covers general capabilities and requirements for the various disposal/processing facilities and brokerage companies, but is not considered exhaustive. Typically, each facility has extensive waste acceptance criteria and will require a generator to thoroughly characterize their wastes. Then a contractual agreement between the waste generator and the disposal/processing/broker entity must be in place before waste is accepted. Costs for tritiated waste transportation, processing and disposal vary based a number of factors. In many cases, wastes with very low radioactivity are priced primarily based on weight or volume. For higher activities, costs are based on both volume and activity, with the activity-based charges usually being much larger than volume-based charges. Other factors affecting cost include location, waste classification and form, other hazards in the waste, etc. Costs may be based on general guidelines used by an individual disposal or processing site, but final costs are established by specific contract with each generator. For this report, seven hypothetical waste streams intended to represent commercially-generated tritiated waste were defined in order to calculate comparative costs. Ballpark costs for disposition of these hypothetical waste streams were calculated. These costs ranged from thousands to millions of dollars. Due to the complexity of the cost-determining factors mentioned above, the costs calculated in this report should be understood to represent very rough cost estimates for the various hypothetical wastes. Actual costs could be higher or could be lower due to quantity discounts or other factors.

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DOE OSTI2019

Chemical durability of glasses

The chemical durability of silicate glasses has long been studied for many applications, in particular when glasses are subjected to environmental weathering and aqueous corrosion. Typical applications include optical instruments, glass vessels, radioactive waste confinement, and bone reparation. Glass corrosion involves ion exchange, water diffusion, network dissolution-recondensation, and secondary phase precipitation. These reactions may impact, among other things, the release of contaminants from waste glasses, and the glass mechanical, optical and catalytic properties. The glass corrosion mechanisms and alteration product formation have been well studied as a function of many environmental parameters (temperature, pH, water composition, etc.). The present chapter describes the general phenomena behind glass corrosion and details glass dissolution in aqueous conditions on one hand and glass vapor hydration on the other hand. The latter phenomenon has not received the same level of attention in the literature relative to the corrosion in aqueous solutions. Research and Development needs, in particular in complex systems such as radioactive waste geological repositories, are discussed in the conclusion of the chapter.

Abdelouas, Abdesselam↗
DOE OSTI2019

Development of a Trace Detection Method for Mercury Speciation in Hanford Tank Waste - 19014

The U.S. Department of Energy's (DOE) Hanford Site in southeast Washington State stores 56 million gallons of chemical and radioactive waste stored in underground tanks. Mercury species in liquid and solid fractions of Hanford tank waste pose a risk to the implementation and execution of DoE's River Protection Project mission due to mercury concentration limits imposed under waste acceptance criteria, toxicity characteristic leaching procedure restrictions for secondary waste disposal, and air emission permits. Although there is currently no processing of tank waste at Hanford, waste processing is imminent, and representative mercury inventory tracking will be important to anticipate and mitigate stack emissions and secondary liquid waste disposal issues. A methodology to accurately determine total mercury and mercury speciation in Hanford tank waste, while maintaining low mercury detection limits, currently does not exist at Hanford. Moreover, the mercury species in the waste solids are unknown and may be waste type-specific. The development of an analytical method to separate and speciate mercury in tank waste was undertaken by the Pacific Northwest National Laboratory (PNNL) while leveraging an existing non-radiological, ultra-trace mercury detection technique frequently performed at PNNL's Marine Sciences Laboratory in Sequim, Washington. The ultimate goal of this work is to develop an analytical method to obtain detailed mercury speciation information and update flowsheet modeling assumptions related to mercury partitioning at Hanford. The first phase of testing was completed in the development of an analytical methodology for the low-level determination of total mercury, elemental mercury, methylmercury, and dimethylmercury in Hanford tank waste. This paper presents Phase I testing which focused on determining whether mercury species can be preconcentrated from aqueous Hanford tank waste solution onto a solid substrate, while simultaneously eliminating or very significantly reducing the parent radionuclide activity. This was demonstrated by developing protocols for the separation and preconcentration of total mercury and methylmercury onto solid substrates, then measuring the substrates for radiological content at PNNL's Radiochemical Processing Laboratory on the Hanford Site. The mercury content was successfully separated onto stable substrates and the radionuclide activity reduction was significant enough that the preconcentrated samples could be subjected to quantification using far less restrictive handling and radiological controls than would be required for the parent sample (i.e., contamination area fume hood vs. hot cell). This mercury separation method required no sample dilution, which enables maximum mercury detectability, while still allowing mercury speciation. (authors)

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DOE OSTI2019

Legacy Waste Removal from Standpipes and Bunkers at Whiteshell Laboratories, Canada - 19040

In 1963 Atomic Energy of Canada Limited (AECL) founded the Whiteshell Nuclear Research Establishment (now Whiteshell Laboratories, WL) in Pinawa, Manitoba to conduct nuclear research. In 1997 AECL made a business decision to discontinue research programs and operations at WL. One of the major decommissioning tasks at WL is to remove radioactive waste from 171 in-ground standpipes and 7 Intermediate Level Waste bunkers located in the Waste Management Area (WMA). Veolia Nuclear Solutions, through its subsidiary Kurion (Canada) Inc., has been selected to design, fabricate, and commission a remote waste access and conditioning system to remediate the waste from the standpipes and ILW bunkers at WL. The agreement builds on Veolia Nuclear Solutions' successfully deploying similar technologies at other projects. This paper describes the bunkers and standpipes structures, the types of wastes stored, the potential hazards (flammable gas and pyrophoric materials), and the equipment proposed by Kurion for safely extracting, sorting, segregating and packaging this waste. (authors)

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DOE OSTI2020

Conducting Industrial Hygiene Exposure Assessments at Scale Using Non-Parametric Upper Tolerance Limits at the Hanford Site - 20439

Chemical vapors are generated in the radioactive waste storage tanks at the Hanford Site due to ongoing chemical and radiological activity. Hanford's Tank Operations Contractor conducts exposure assessments for individual tank farms to identify, evaluate, and recommend controls or other worker protection measures for chemical, physical, and biological hazards present within each tank farm. These exposure assessments conform to the American Industrial Hygiene Association assessment strategy and recommended statistical procedures. The exposure assessment process involved manually processing tens of thousands of records that were collected over several years and entered into a central database. Working with Pacific Northwest National Laboratory, this process has been largely automated, providing a scalable analysis process that reduced processing time by over 90%, while providing defensible results and improved data quality. (authors)

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DOE OSTI2016

Free-standing Liquids in a Resin Disposal Container - How Unidentified Legacy Issues and Decisions Can Affect Current Radwaste Processing Activities - 16605

On Monday, October 27, 2014 a radwaste and transportation specialist was informed that a condensate filter demineralizer (CFD) radwaste disposal container exceeded the radioactive waste disposal facility free-standing liquid requirement for acceptance for disposal (limit is 0.5% of waste volume or 5.6 gallons); 8.5 gallons was measured). As a result, on October 28, the plant was informed that our disposal site use permit was suspended, pending a point-of-origin inspection by the agreement state regulatory authority. This paper details the investigation conducted to identify causes, especially legacy issues one may not necessarily identify, and documents corrective actions taken to assure similar issues are not repeated. Actions taken to prevent recurrence have been successful. The five containers shipped, including 14-033, were verified dewatered and dried to comply with the disposal facility waste acceptance criteria. Although discoloration is viewed in the dewatering sight glass, milky color has not been viewed and the dewatering process has continued. Isolation of the lowest set of dewatering filter laterals for use at the end of the dewatering process has worked well and use of the dewatering verification filters has provided evidence that each CRF resin liner was successfully dewatered and dried. To date, 37 CFD liners have been successfully dewatered, dried, verified, transported to the disposal facility, and buried without incident. If similar issues are encountered, you should keep an open mind regarding causes including, but not limited to discussions with your vendor and conduct a search of past procedure revisions to gain additional insight regarding program/procedure changes and how they could have an effect on issues, which occur today.

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DOE OSTI2019

Panel Session 12: Featured Country Canada - Engaging the Public and Indigenous Groups in Canadian Waste and D and D Projects

This panel will share insights from those directly involved in the dialogue among members of the Canadian public, elected officials of host communities, indigenous groups, project proponents, and the Canadian regulator. History has shown time and again that the early and meaningful engagement of stakeholders must go hand-in-hand with technical solutions in order to assure the successful start and finish of waste management and decommissioning projects. In this panel discussion, the requirements for consultation and communication, the tools and strategies used, the results of efforts to date, and plans will be addressed by those at the center of some of Canada's biggest and most controversial radioactive waste projects. Presentations proposed include: 1 - Engaging the Public and Indigenous Groups in Canadian Waste and D and D Projects (Candida Cianci, Canadian Nuclear Safety Commission (Canada)); 2 - Indigenous Engagement (Bob Watts, Nuclear Waste Management Organization (Canada)); 3 - Engaging the Public and Indigenous Groups Related to Canadian Waste and D and D Projects (Patrick Quinn, Canadian Nuclear Laboratories (Canada)); 4 - Engaging the Public and Indigenous Groups in Canadian Waste and D and D Projects Canadian Association of Nuclear Host Communities Point of View (Blair Skinner, Local Government District of Pinawa, Manitoba (Canada))

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DOE OSTI2016

Considerations of the Differences between Bedded and Domal Salt Pertaining to Disposal of Heat-Generating Nuclear Waste

Salt formations hold promise for eternal removal of nuclear waste from our biosphere. Germany and the United States have ample salt formations for this purpose, ranging from flat-bedded formations to geologically mature dome structures. As both nations revisit nuclear waste disposal options, the choice between bedded, domal, or intermediate pillow formations is once again a contemporary issue. For decades, favorable attributes of salt as a disposal medium have been extoled and evaluated, carefully and thoroughly. Yet, a sense of discovery continues as science and engineering interrogate naturally heterogeneous systems. Salt formations are impermeable to fluids. Excavation-induced fractures heal as seal systems are placed or natural closure progresses toward equilibrium. Engineering required for nuclear waste disposal gains from mining and storage industries, as humans have been mining salt for millennia. This great intellectual warehouse has been honed and distilled, but not perfected, for all nuances of nuclear waste disposal. Nonetheless, nations are able and have already produced suitable license applications for radioactive waste disposal in salt. A remaining conundrum is site location. Salt formations provide isolation, and geotechnical barriers reestablish impermeability after waste is placed in the geology. Between excavation and closure, physical, mechanical, thermal, chemical, and hydrological processes ensue. Positive attributes for isolation in salt have many commonalities independent of the geologic setting. In some cases, specific details of the environment will affect the disposal concept and thereby define interaction of features, events and processes, while simultaneously influencing scenario development. Here we identify and discuss high-level differences and similarities of bedded and domal salt formations. Positive geologic and engineering attributes for disposal purposes are more common among salt formations than are significant differences. Developing models, testing material, characterizing processes, and analyzing performance all have overlapping application regardless of the salt formation of interest.

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DOE OSTI2015

Using Project Complexity Determinations to Establish Required Levels of Project Rigor

This presentation discusses the project complexity determination process that was developed by National Security Technologies, LLC, for the U.S. Department of Energy, National Nuclear Security Administration Nevada Field Office for implementation at the Nevada National Security Site (NNSS). The complexity determination process was developed to address the diversity of NNSS project types, size, and complexity; to fill the need for one procedure but with provision for tailoring the level of rigor to the project type, size, and complexity; and to provide consistent, repeatable, effective application of project management processes across the enterprise; and to achieve higher levels of efficiency in project delivery. These needs are illustrated by the wide diversity of NNSS projects: Defense Experimentation, Global Security, weapons tests, military training areas, sensor development and testing, training in realistic environments, intelligence community support, sensor development, environmental restoration/waste management, and disposal of radioactive waste, among others.

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DOE OSTI2017

Hanford Site Composite Analysis Technical Approach Description: Automated Quality Assurance Process Design.

The U.S. Department of Energy (DOE) in DOE O 435.1 Chg. 1, Radioactive Waste Management, requires the preparation and maintenance of a composite analysis (CA). The primary purpose of the CA is to provide a reasonable expectation that the primary public dose limit is not likely to be exceeded by multiple source terms that may significantly interact with plumes originating at a low-level waste disposal facility. The CA is used to facilitate planning and land use decisions that help assure disposal facility authorization will not result in long-term compliance problems; or, to determine management alternatives, corrective actions, or assessment needs if potential problems are identified.

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DOE OSTI2015

Searching for science in the past and present discussion on commingling policy in the US - 15083

Since 1985, the policy in the United States for disposing of nuclear waste has included commingling defense and civilian spent nuclear fuel (SNF) and high-level radioactive waste (HLW) in a mined geologic repository. Commingling policy is under discussion again because of developments over the last several years in the nuclear waste management and disposal program. The authors reviewed the extent to which scientific and technical information was involved in considerations of commingling from the 1950's to the present. Evaluations undertaken by the US Department of Energy (US DOE) in 1985 and April 2014 are compared and the technical issues of health and safety, transportation, and national security are addressed in both evaluations. (authors)

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DOE OSTI2016

Port Hope Area Initiative - Community Based Concepts Become Reality - 16538

The Port Hope Area Initiative (PHAI) involves the cleanup of historic low-level radioactive waste (LLRW) resulting from radium and uranium processing by the former Crown Corporation, Eldorado Nuclear Limited, and its predecessor companies, during the period between 1932 and 1988. The PHAI, which is based on a legal agreement between the Government of Canada and the adjacent municipalities of Port Hope and Clarington in Ontario, Canada, comprises two separate community-initiated projects for the long-term management of the historic LLRW located in each of these municipalities. The Port Hope Project involves the cleanup of approximately 1.2 million cubic metres of historic LLRW from various sites within the urban area of Port Hope, the construction and operation of an engineered aboveground mound where the waste will be safely contained, and the long-term maintenance and monitoring of the new waste management facility. The waste is currently located in 13 large-scale sites and an estimated 375 small-scale sites within the community. In contrast, the Port Granby Project involves the relocation of approximately 450,000 cubic metres of historic LLRW from the existing waste site on the north shore of Lake Ontario in rural Clarington, to a new engineered aboveground mound to be built 700 metres north of the shoreline. The work also involves the restoration of the existing site and long-term maintenance and monitoring the new facility. The PHAI entered Phase 2 (construction) of a three-phase program in early 2012, when $1.28 billion (Canadian) in federal funding was announced by the Minister of Natural Resources Canada. The funding, together with regulatory approval from the Canadian Nuclear Safety Commission (CNSC), which granted 10-year waste management licences to both projects, have permitted the PHAI to move forward with construction and remediation. Waste water treatment plants based on best-available technologies have been constructed for each project to remove a wide range of contaminants from groundwater, surface water and leachate collected during construction and operation of the aboveground mounds. Each treatment process has been designed to ensure the quality of treated water being discharged into Lake Ontario meets or exceeds stringent regulatory requirements, resulting in the enhanced protection of the Great Lakes Basin ecosystem. In 2015, the contract to build the Port Granby long-term waste management facility and remediate the existing waste site was awarded, and the long-awaited facility development will soon begin. The use of a dedicated internal waste transportation route along, which the LLRW will be trucked from the existing site to the new facility, is a key component of the design to minimize the impact on the local, rural community. In Port Hope, the removal of contaminated soil within the site for the new long-term management facility commenced in the fall of 2015. Over the next several years, multiple contracts will be awarded for construction and operation of the new waste management facility and remediation of the large and small-scale sites. In short, the Port Hope and Port Granby community-based concepts have matured into tangible projects with appropriate regulatory approvals and federal funding in place. Ongoing communications with the two communities have resulted in a well-informed public that understands the work to be done and is eager to see their projects take shape and become reality. As Canada's largest environmental remediation and restoration undertaking, the PHAI has never been closer to fulfilling its vision - working with the local communities to fulfil Canada's commitment for the cleanup of historic waste in Port Hope and Port Granby to leave an honourable legacy for future generations. (authors)

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DOE OSTI2020

Session 059 - Panel: Small Business Procurement and Contracting Opportunities within the US DOE Complex and USACE FUSRAP Sites (R1.7)

This panel session focused on small business procurement and contracting opportunities within the DOE Complex and USACE FUSRAP Sites. The federal government encourages prime contractors to obtain goods and services from small and disadvantaged businesses (Tier 2) and often tie these goals to contract award fee. Goods and services being considered for these procurements include decontamination and decommissioning, remediation, transportation and disposal of radioactive waste, health physics, emergency response planning and training, lab services, R and D products, waste treatment, maintenance, A/E and professional consulting. Panelists with presentations: Small Business Procurement and Contracting Opportunities within the US DOE Complex and USACE FUSRAP Program (Aaron Deckard; Subcontracting Opportunities with the DOE Primes (William Badger); Bechtel National, Inc. Small Business Opportunities (Lisa Tribuce-Leoung Tat); Small Business Procurement and Contracting Opportunities (Gina Joiner); Small Business Procurement and Contracting Opportunities - Flour (Katy Burnau); Environmental WORK, Formerly Utilized Sites Remedial Action Program (FUSRAP) (John Busse)

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