Academic literature on the topic 'Radioactive waste disposal in the ground – United States – History'

Canada, along with other countries that are considering the permanent disposal of high-level radioactive wastes from nuclear power generation, is undertaking a program of research into deep geological disposal. This program, led by Atomic Energy of Canada Limited (AECL) with support from Energy, Mines and Resources Canada, other federal government departments, universities, and industrial consultants, has been in progress since early in 1973. Geoscience research, the subject of this symposium, complements research on fuel waste immobilization to provide the data and information essential to the design and assessment of a complete disposal concept involving both natural and engineered barriers to the migration of radioactive material from the waste vault.During the early phases of the program, prior to 1975, an evaluation of the potential of Canadian salt deposits for nuclear waste disposal, as well as a preliminary assessment of the suitability of other geological formations, was made. Because the Province of Ontario was, and remains, the principal region in Canada for nuclear power development and because resources available for geoscience research would not permit simultaneous, intensive research on a number of rock types, the decision was taken to direct the main thrust of the geoscience research toward plutonic igneous rocks of the Canadian Shield in Ontario (Scott 1979). Lesser studies of salt and other sedimentary formations, including seabed, are continuing within the Geological Survey of Canada.Because the rock mass surrounding the vault will provide the principal barrier to the migration of radionuclides, should these be released from the emplaced wastes, knowledge and understanding of potential pathways through the rock mass and of the mechanisms of radionuclide transport and retention within the rock mass over the functional lifetime of the vault are fundamental requirements.Accordingly, the objectives of the geoscience research program (Dormuth and Scott 1984) are the following:(1) Develop and apply techniques to define the physical and chemical properties of large rock masses and of fluids within these rock masses.(2) Use these techniques in selected field research areas to calibrate and evaluate models developed to calculate fluid flow and mass transport through a large rock mass containing a hypothetical underground nuclear fuel waste-disposal vault.(3) Establish procedures to evaluate quantitatively rock bodies for their potential as disposal sites and thereby acquire the capability to compare different rock bodies.(4) Determine the long-term stability of plutonic rock masses by assessing the potential disturbance by seismic activity, glaciation, meteorite impact, and other disruptive events and processes.To achieve these objectives it has been necessary to undertake simultaneously a large number of research tasks involving the disciplines of geology, geophysics, hydrogeology, geomechanics, geochemistry, and mathematics. Some of these tasks are concerned primarily with regional aspects of the Canadian Shield, such as stress distribution, glaciation, and tectonic history; others with details of the surface and subsurface geology and hydrogeology of specific field research areas; and still others with the development and application of exploration technology to detect and evaluate the structural characteristics of igneous rock masses of relatively high integrity and uniformity. Field and office studies are supported by laboratory investigations of the physical and chemical properties of plutonic rocks, with specific reference to origin, history, and ability to retard or transmit radionuclides.Deep exploratory drilling and detailed surface mapping are carried out at designated field research areas in the Canadian Shield. Geoscience work at research areas has the two-fold purpose of (i) testing new and existing exploration techniques for the evaluation of rock masses; and (ii) through application of these airborne, surface, and subsurface techniques, providing the field data necessary for the development of concepts and models that form the basis for establishing site-selection criteria and performing safety analyses.The latest research areas have been established at Atikokan, Ontario, an area underlain by granitic rocks, and at East Bull Lake north of Massey, Ontario, where gabbroic rocks are the dominant type. These research areas complement previously established research areas developed on granitic rocks at AECL properties at Chalk River, Ontario, and Pinawa, Manitoba, and at a research area, also on granitic terrane, near White Lake, Ontario, where work was done early in the program to test geophysical exploration and borehole-logging equipment.The ability to predict subsurface geological and hydrogeological conditions at future waste-disposal sites is one of the primary goals of geoscience research in the Canadian Nuclear Fuel Waste Management Program (CNFWMP). One of the most important program elements designed to test this predictive capability was the construction of the Underground Research Laboratory (URL) in the Lac du Bonnet Batholith near the site of the Whiteshell Nuclear Research Establishment. Airborne, surface, and borehole methods were used to develop a geological model on the site, and hydrogeological investigations were carried out to establish preconstruction groundwater characteristics. As the excavation of the URL facilities proceeded, the geological features encountered and the changes in the hydrogeological systems were carefully monitored. These data are being used to assess and improve the geological and hydrogeological models being developed for the rock mass surrounding the URL.The URL provides an excellent opportunity to (i) study the effect of excavation techniques, heat, and stress on a rock mass; (ii) simulate and study the complex systems that may exist in a disposal vault environment; and (iii) develop and test shaft- and drift-sealing techniques. Recently, a bilateral agreement between AECL and the United States Department of Energy was signed for co-operative research on nuclear fuel waste disposal. A substantial part of this co-operative effort will be directed toward extension of the URL shaft beyond its present depth of 240 m and conducting a variety of nonnuclear experiments within the shaft and excavated chambers of the URL.From the time of formalization of CNFWMP over 10 years ago, a concerted effort has been made by AECL and other program participants to ensure both peer review of and widespread accessibility to results of research arising from CNFWMP. This symposium is the third to be sponsored by the Geological Association of Canada (GAC)—the two previous symposiums were held at GAC annual meetings in Winnipeg in 1982 and Toronto in 1978. In addition to these major symposia, general information meetings sponsored by AECL have been held annually at various centres across Canada, and research elements of CNFWMP formed a significant part of the technical program for an international meeting held by the Canadian Nuclear Society in Winnipeg in September 1986.Since 1979 the CNFWMP review process has been further enhanced by the Technical Advisory Committee chaired by L. W. Shemilt, McMaster University. This committee, comprising members nominated by major Canadian scientific and technical societies including the Canadian Geoscience Council, has annually provided a publicly available report of constructive criticism and recommendations for improvement in the research content of CNFWMP.During the second half of 1988 it is expecte

A systematic review of near-surface repositories for radioactive waste in the United States (US) was conducted. The main focus of the review consisted of a literature search of available documents and other published sources on low level radioactive waste (LLRW) disposal practices, remediation of LLRW sites in the US, and public participation for remediation efforts of near-surface radiological waste disposal sites in the US. This review was undertaken to provide background information in support of work by the United Kingdom’s (UK) Low Level Waste Repository (LLWR) and to aid in optimizing the future management of this site. The review contained a summary of the US and UK radiological waste classification requirements including a discussion of the waste types, disposal requirements, and the differences between US and UK disposal practices. A regulatory overview and evolution of regulatory requirements in the US is presented. The UK regulatory environment is also discussed and contrasted to the US process. The public participation, as part of the US regulatory process, is provided and the mechanism for stakeholder identification and involvement is detailed. To demonstrate how remediation of radiologically impacted sites is implemented in the US, existing US case studies, in which remediation activities were carried out, were reviewed. The following information was compiled: type of wastes disposed of to US shallow ground facilities [with comparison with UK classifications], facility designs (with special emphasis on those directly comparable to the subsurface conditions in the UK), and deficiencies identified in operation or in demonstrating safe post closure; and processes and difficulties in remedial actions encountered at the selected sites. Stakeholder involvement is discussed within the case studies. Publicly available information related to radiological waste management and disposal practices were reviewed. Two sites are presented in this publication for discussion. These US sites were selected based on the site similarities to conditions in the UK.

As a result of nuclear weapons production, the United States of America produced significant quantities of transuranic waste, which consists of clothing, tools, rags, residues, debris and other items contaminated with small amounts of radioactive man-made elements — mostly plutonium — with an atomic number greater than that of uranium. Transuranic waste began accumulating in the 1940s and continued through the Cold War era. Today, most transuranic waste is stored at weapons production sites across the United States. In 1957, the National Academy of Sciences concluded that the most promising disposal option for radioactive wastes was disposal in deep geologic repositories situated in the salt formations. After nearly a decade of study, the United States Department of Energy decided in January 1981 to proceed with construction of the Waste Isolation Pilot Plant (WIPP) at a site 41.6 km (26 miles) southest of Carlsbad, New Mexico. After years of study, construction, and permitting, the WIPP facility became operational in early 1999. As the United States continues to clean up and close its former nuclear weapon facilities, the operation of WIPP will continue into the next several decades. This paper will provide on overview of the history, regulatory, and public process to permit a radioactive repository for disposal of transuranic wastes and the process to ensure its long-term operation in a safe and environmentally compliant manner.

Abstract In 1957, the National Academy of Sciences concluded that the most promising disposal option for radioactive wastes was burial in deep geologic repositories situated in salt formations. In 1981, after decades of study, the United States initiated construction of the Waste Isolation Pilot Plant (WIPP) at a desert site 41.6 km (26 miles) southeast of Carlsbad, New Mexico. This paper provides an overview of the history and the regulatory and public process to permit a repository for disposal of transuranic wastes. In addition, the process to ensure its long-term operation in a safe and environmentally sound manner will also be discussed.

This paper provides a case history of a highly successful approach that was developed and implemented for the U.S. Department of Energy (DOE) for the cleanup and remediation of a large and diverse population of uranium mill tailings sites located in the Western United States. The paper addresses the key management challenges and lessons learned from the largest DOE Environmental Management Clean-up Project (in terms of number of individual clean-up sites) undertaken in the United States. From 1986 to 1996, the Department of Energy’s Grand Junction Projects Office (GJPO) completed approximately 4600 individual remedial action site cleanup projects for large- and small-scale properties, and sites contaminated with residual hazardous and radioactive materials from former uranium mining and milling activities. These projects, with a total value of $597 million, involved site characterization, remedial design, waste removal, cleanup verification, transportation, and disposal of nearly 2.7 million cubic yards of low-level and mixed low-level waste. The project scope included remedial action at 4,200 sites in Grand Junction, Colorado, and Edgemont, South Dakota; 412 sites in Monticello, Utah; and, 44 sites in Denver, Colorado. The projects ranged in size and complexity from the multi-year Monticello Millsite Remedial Action Project, which involved investigations, characterization, remedial design, and remedial action at this uranium millsite along with design of a 2.5 million cubic yard disposal cell, to the remediation and reconstruction of thousands of smaller commercial and residential properties throughout the Southwestern United States. Because these projects involved remedial action at a variety of commercial facilities, businesses, churches, schools and personal residences, and the transportation of the waste through towns and communities, an extensive public involvement program was the cornerstone of an effort to promote stakeholder understanding and acceptance. The Project established a DOE model for rapid, economical, and effective remedial action. During the ten years of the contract, the management operations contractor (Duratek) met all project milestones on schedule and under budget, with no cost growth from the original scope. By streamlining remediation schedules and techniques, ensuring effective stakeholder communications, and transferring lessons learned from one project to the next, the contractor achieved maximum efficiency and the lowest remediation costs of any similar DOE environmental programs at the time.

This paper addresses the experience, knowledge, and expertise that Duratek has acquired while performing environmental remediation at two large low-level radioactive waste (LLRW) disposal facilities in the United States. Environmental remediation and related waste disposal has been the company’s primary line of business line since it was founded in 1969. It has disposed of more than half of the low-level radioactive waste generated in the U.S. over the past thirty years, working with almost every radioactive waste generator in the country. That experience has allowed the company to develop a unique understanding of safe, efficient, and cost-effective LLRW disposal methods. The paper also tracks the history of waste disposal technology at the Barnwell Disposal Site in South Carolina and the U.S. Department of Energy Environmental Restoration Disposal Facility (ERDF) at Oak Ridge, Tennessee. In particular, it describes the evolution of trench design, operations, and disposal procedures for these facilities. It also discusses the licensing of one the most active waste disposal sites in the U.S., the success of which has been assured to customers and stake-holders because of: • Well trained personnel who are dedicated to the design, construction and operation of safe and efficient disposal facilities; • Commitment to strong community relations; • Comprehensive knowledge of proven disposal strategies, technologies, and management practices; • Capability and readiness to respond rapidly to routine and emergency situations; • Established record of comprehensive and responsive communications with regulatory authorities; • Commitment to quality, compliance and personnel health, and safety; and • Financial systems that ensure long-term facilities management.

Utilities worldwide are using dry-cask storage systems to handle the ever-increasing number of discharged fuel assemblies from nuclear power plants. In the United States and possibly elsewhere, this trend will continue until an acceptable disposal path is established. The recent Fukushima nuclear power plant accident, specifically the events with the storage pools, may accelerate the drive to relocate more of the used fuel assemblies from pools into dry casks. Many of the newer cask systems incorporate dual-purpose (storage and transport) or multiple-purpose (storage, transport, and disposal) canister technologies. With the prospect looming for very long term storage — possibly over multiple decades — and deferred transport, condition- and performance-based aging management of cask structures and components is now a necessity that requires immediate attention. From the standpoint of consequences, one of the greatest concerns is the rupture of a substantial number of fuel rods that would affect fuel retrievability. Used fuel cladding may become susceptible to rupture due to radial-hydride-induced embrittlement caused by water-side corrosion during the reactor operation and subsequent drying/transfer process, through early stage of storage in a dry cask, especially for high burnup fuels. Radio frequency identification (RFID) is an automated data capture and remote-sensing technology ideally suited for monitoring sensitive assets on a long-term, continuous basis. One such system, called ARG-US, has been developed by Argonne National Laboratory for the U.S. Department of Energy’s Packaging Certification Program for tracking and monitoring drums containing sensitive nuclear and radioactive materials. The ARG-US RFID system is versatile and can be readily adapted for dry-cask monitoring applications. The current built-in sensor suite consists of seal, temperature, humidity, shock, and radiation sensors. With the universal asynchronous receiver/transmitter interface in the tag, other sensors can be easily added as needed. The system can promptly generate alarms when any of the sensor thresholds are violated. For performance and compliance records, the ARGUS RFID tags incorporate nonvolatile memories for storing sensory data and history events. Over the very long term, to affirmatively monitor the condition of the cask interior (particularly the integrity of cover gas and fuel-rod cladding), development of enabling technologies for such monitoring would be required. These new technologies may include radiation-hardened sensors, in-canister energy harvesting, and wireless means of transmitting the sensor data out of the canister/cask.