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At least 793 records · Page 44
All sourcesNASA NTRSDOE OSTI
DOE OSTI2015

The radium industry in France and the remediation of polluted sites - 15256

According to the French Law of 28 June 2006 relative to the management of radioactive materials and waste, Andra is in charge of a public service mission that involves the clean-up of orphan sites that have been polluted by radioactivity. Andra is currently working, or has worked in the past, on around thirty sites in mainland France. The clean-up strategy is selected after a comparative analysis of the cost and the advantages of the different scenarios based on the ALARA principle. Whenever reasonable, Andra tries to achieve total clean-up, so that the site can be re-used without any constraint. However, for certain cases, it is opted for a less ambitious scenario, which means restricting the possibilities of use of the site after clean-up. In all cases, the chosen scenarios guarantee that there will be no radiological impact on the planned new use of the site. If the site is an orphan site, a National Advisory Committee for Public Funding in the field of Radioactivity (known as CNAR) decides which scenario presents the best cost-benefit profile and whether to provide public subsidies to fund the work. The multidisciplinary composition of the CNAR, with members from public administrations and organizations, politicians, qualified personalities and non-governmental organizations, guarantees a decision that has been carefully considered from all aspects. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗
DOE OSTI2019

Robotics on KM-IT platform - 19107

The Knowledge Management Information Tool (KM-IT) is a web-based system developed to maintain and preserve the Department of Energy's (DoE's) knowledge base. The system was developed by Florida International University's Applied Research Center (FIU-ARC) with the support of the D and D community including the DOE Office of Environmental Management, and with the collaboration and support of the DoE's Energy Facility Contractors Group (EFCOG) and the former ALARA Centers at Hanford and Savannah. The KM-IT system is a community driven system tailored to serve the technical issues faced by the workforce across the DOE Complex. This KM-IT web-based interactive system is operational and available for use at www.dndkm.org and is currently comprised of the following modules: Web Crawler, Hotline, Technology, Hanford's ALARA Center Reports, Specialist Directory, Lessons Learned, Best Practices, Video/Picture Library, Vendors and Industry News. The Web Crawler dynamically searches through the KM-IT repository as well as the web and displays search results based on the search criteria. The Hotline allows registered users to post questions/problems related to D and D and to receive solutions from a subject-matter specialist. The Technology module serves as repository of D and D technologies and contains technology/ demonstration fact sheets and vendor information. D and D community members can add Lessons Learned, Best Practices, and Pictures/Videos to the D and D repository, after a formal approval process. The Vendor module provides a directory of commercial vendors who provide D and D related technologies, supplies, and services. KM-IT makes an excellent use of the knowledge that exists within the D and D community by allowing D and D project managers around the DOE complex to collaborate by sharing innovative ideas, past experiences, and practices and by maintaining a directory of subject matter specialists. FIU is working on developing a new knowledge base using the existing KM-IT framework to provide focused information on robotics. FIU will develop the robotics technology and vendor modules to provide information related to robotics technologies and its application to many different areas including D and D, remote systems and waste processing. This robotics knowledge base will provide the ability to search through the information repository as well as display customized summary information including robotics technology descriptions, benefits, limitations, videos and pictures. The vendor module will provide information related to industry vendors for these technologies and include updated vendor contact information. The vendor module will also provide a search capability based on keywords as well as categories. The robotics knowledge base will publish commercially available technologies as well as the technologies that are still in the research and development phase with national laboratories and academic universities. The robotics KM-IT will be developed in phases to support all of the features of the KM-IT platform and will be published on www.rkmit.org. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗
DOE OSTI2019

Accelerated Leach Testing of GLASS (ALTGLASS Version 4.0)

The Accelerated Leach Testing of GLASS (ALTGLASS) database is a collection of data from short- and long-term product consistency tests (PCT, ASTM C1285 A and B) on high level waste (HLW) as well as low activity waste (LAW) glasses. The database provides both U.S. and international researchers with an archive of experimental data for the purpose of studying, modeling, or validating existing models of nuclear waste glass corrosion. The ALTGLASS database is maintained and updated by researchers at the Savannah River National Laboratory (SRNL).

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗
DOE OSTI2013

Unique Regulatory Approach for Licensing the Port Hope Remediation Project in Canada - 13315

The Port Hope remediation project is a part of a larger initiative of the Canadian Federal Government the Port Hope Area Initiative (PHAI) which is based upon a community proposal. The Government of Canada, through Natural Resources Canada (NRCan) is investing $1.28 billion over 10 years to clean up historic low-level radioactive waste in the Port Hope Area and to provide long-term safe management of the low-level radioactive wastes in the Port Hope Area. These wastes arose from the activities of a former Federal Crown Corporation (Eldorado Nuclear) and its private sector predecessors. In Canada, historic waste are defined as low-level radioactive waste that was managed in a manner no longer considered acceptable, but for which the original producer cannot reasonably be held responsible or no longer exists and for which the Federal Government has accepted responsibility. In Canada, under the current regulatory framework, the environmental remediation is not considered as a distinct phase of the nuclear cycle. The regulatory approach for dealing with existing sites contaminated with radioactive residues is defined on the basis of risk and application of existing regulations. A unique regulatory approach was taken by the Canadian Nuclear Safety Commission (CNSC) to address the various licensing issues and to set out the requirements for licensing of the Port Hope Project within the current regulatory framework. (authors)

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DOE OSTI2010

Safety Design Strategy for the Remote Handled Low-Level Waste Disposal Project

In accordance with the requirements of U.S. Department of Energy (DOE) Order 413.3A, “Program and Project Management for the Acquisition of Capital Assets,” safety must be integrated into the design process for new or major modifications to DOE Hazard Category 1, 2, and 3 nuclear facilities. The intended purpose of this requirement involves the handling of hazardous materials, both radiological and chemical, in a way that provides adequate protection to the public, workers, and the environment. Requirements provided in DOE Order 413.3A and DOE Order 420.1B, “Facility Safety,” and the expectations of DOE-STD-1189-2008, “Integration of Safety into the Design Process,” provide for identification of hazards early in the project and use of an integrated team approach to design safety into the facility. This safety design strategy provides the basic safety-in-design principles and concepts that will be used for the Remote-Handled Low-Level Waste Disposal Project.

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DOE OSTI2012

Safety Design Strategy for the Remote Handled Low-Level Waste Disposal Project

In accordance with the requirements of U.S. Department of Energy (DOE) Order 413.3A, “Program and Project Management for the Acquisition of Capital Assets,” safety must be integrated into the design process for new or major modifications to DOE Hazard Category 1, 2, and 3 nuclear facilities. The intended purpose of this requirement involves the handling of hazardous materials, both radiological and chemical, in a way that provides adequate protection to the public, workers, and the environment. Requirements provided in DOE Order 413.3A and DOE Order 420.1B, “Facility Safety,” and the expectations of DOE-STD-1189-2008, “Integration of Safety into the Design Process,” provide for identification of hazards early in the project and use of an integrated team approach to design safety into the facility. This safety design strategy provides the basic safety-in-design principles and concepts that will be used for the Remote-Handled Low-Level Waste Disposal Project.

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DOE OSTI2023

Solubility behavior and thermodynamic modeling of sodium monosulfoaluminate (“U‐phase”) in cementitious systems

Abstract The “U‐phase,” a sodium‐containing (alumino‐ferrite‐monosubstituent) AFm phase, has been observed to form in sodium‐enriched highly alkaline cementitious systems, for example, of relevance to nuclear waste, and saline industrial brine management. But, minimal information is available of the U‐phase's (e.g., solubility or thermodynamic properties) due to its limited stability and its tendency to transform into ettringite or monosulfoaluminate. Herein, the U‐phase was systematically synthesized at four temperatures (5, 15, 25, and 50°C) and fully characterized in terms of its thermochemical properties. The average composition of the synthesized U‐phase (4CaO·Al 2 O 3 ·1.85SO 3 ·0.85Na 2 O·12H 2 O) deviates slightly from typical disclosures in the literature. The solubility product of the U‐phase formation was measured from conditions of oversaturation. The measured thermodynamic data accurately predicted experimental observations of U‐phase formation in cementitious environments. In general, it was noted that the U‐phase forms and persists (i.e., remains stable) at pH > 13.7 and [Na + ] concentrations superior to 1 mol/L.

Materials Science↗
DOE OSTI2022

The Role of Pulse Radiolysis in Advanced Nuclear Fuel Cycles

The effects of ionizing radiation are ubiquitous throughout all aspects of a nuclear fuel cycle. The complexity and intensity of these effects are greatest during reactor operations and in the management of used nuclear fuel and waste. Radiation-induced processes typically promote the chemical transformation of molecules and materials with the formation of potentially detrimental degradation products and corresponding changes in physical and chemical properties, which ultimately impact the effectiveness and longevity of nuclear technologies. Consequently, a molecular-level understanding of radiation effects over multiple time, distance, and material domains is essential for the innovation and deployment of next generation nuclear technologies. Attaining this knowledge necessitates a firm grasp of radiation-induced reaction kinetics, for which pulsed electron radiolysis is the methodology of choice. Presented here are several recent studies from our group that demonstrate the critical role of pulsed electron radiolysis techniques in the advancement of our understanding of radiation-induced chemistry under advanced nuclear fuel cycle conditions. Research topics include late actinide redox chemistry, radiation robustness of used nuclear fuel reprocessing complexants, and the behavior of metal cations in high temperature molten salt media.

38 RADIATION CHEMISTRY, RADIOCHEMISTRY, AND NUCLEA↗
DOE OSTI2026

Alpha-Imaging Detector System Development for Large Area Monitoring

Effective management and disposal of legacy nuclear waste are essential for ensuring safe work environments and minimizing environmental impacts. Monitoring airborne actinide contamination is particularly critical due to the high internal dose potential of alpha-emitting radionuclides. Traditional continuous air monitoring systems (CAMs) used in the industry are limited in the volume of air they can sample, potentially leading to inaccurate radiation detection over large areas. For example, in 2018, elevated levels of airborne Plutonium-239 were detected beyond the controlled areas of the Hanford Plutonium Finishing Plant, highlighting the potential risks to both plant workers and nearby residents. To address these challenges, high-efficiency particulate absorbing (HEPA) air purifiers can enhance air flow by up to 1.5 orders of magnitude, thereby increasing monitoring efficiency and providing a cost-effective solution for large-area surveillance. To quantify the activities of alpha-emitting radionuclides on HEPA filters, the Savannah River National Laboratory is developing an advanced alpha-imaging detection system. This system includes scintillating materials combined with a digital scientific camera. A significant concern in operating such a large-area airborne monitoring system is the handling of HEPA filters, which may be contaminated with radioactive particles. To mitigate these hazards, it is crucial to ensure that any contamination is securely fixed onto the filters. Efforts have been made to optimize the sensitivity of scintillator-epoxy composites and apply them to HEPA filters. These materials were characterized using fluoroscence spectroscopy. These techniques confirmed the purity of the raw materials, the dispersion of scintillators in the epoxy matrix, and the stability of their optical and structural properties post-modification. The optimal scintillator-epoxy composite was selected for use on alpha-spiked HEPA filters to evaluate the efficiency of the sprayer. HEPA filters, embedded with alpha particles collected by an air purifier deployed in an airborne radiation area, have been tested to assess detection efficiency. Future work will focus on employing multiple imaging sensors simultaneously to enhance sensitivity across different regions of the HEPA filter.

Pham, Phuong [Savannah River National Laboratory (↗
DOE OSTI2019

Safely Managing CNL's Shutdown Prototype Power Reactors - 30 years of Experience - 19157

Canadian Nuclear Laboratories (CNL) has over 30 years of experience managing three prototype power reactors from shutdown through storage with surveillance and into preparation from final decommissioning. CNL is responsible for the safe storage with surveillance of three prototype power reactors; Nuclear Power Demonstration (NPD), Gentilly-1(G1) and Douglas Point (DP). Each of the Canadian prototype power reactor sites have been maintained using different post shutdown management strategies, which were based on the site location, configuration, and intended designation of the respective sites. This paper will discuss the post shutdown strategies employed at the three sites, including details of their shutdown strategy, current conditions, and experience gained from the period of storage with surveillance. (author)

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DOE OSTI2018

Results of the OECD-NEA Initiative 'Preservation of RK and M Across Generations' - 18084

The OECD Nuclear Energy Agency (NEA) has co-ordinated an international initiative to develop understanding and guidelines related to the long-term preservation of records, knowledge and memory (RK and M) for radioactive waste repositories. The initiative will come to a close in April 2018. Currently, a number of deliverables are in the process of publication and a preview and overview is presented in this paper. Central is the 'Final Report of the RK and M Initiative', which sets out the RK and M fundamentals, including basic principles of RK and M preservation, the concept of oversight and the relevant time frames, the mediated and non-mediated transmission of messages, and ultimately the need for a systemic strategy. Furthermore, it presents a menu of approaches and mechanisms of RK and M preservation, such as markers, time capsules, archives, the Key Information File (KIF), education, art, land use control, and monitoring. Finally, the main report provides suggestions on how to develop a systemic strategy. A bibliography and a regulatory catalogue on RK and M preservation, and concept reports describing the KIF and the Set of Essential Records (SER), will complement the set of deliverables of the RK and M Initiative. (authors)

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DOE OSTI2011

Preface

A short preface is given to introduce the subject matter of the book titled Advanced Separation Techniques for Nuclear Fuel Reprocessing and Radioactive Waste Treatment. The subject matter of this book is the separation science and technology underlying the efforts to manage irradiated nuclear fuel, including progress towards achieving a closed fuel cycle. The book is organized into two parts. The first part is aimed at providing fundamental scientific and engineering information related to nuclear fuel cycle separations. The second part is devoted to describing specific technological solutions that are being pursued in the development of advanced nuclear fuel cycles.

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗
DOE OSTI2012

The EU Approach for Responsible and Safe Management of Spent Fuel and Radioactive Waste - 12118

In July 2011 legislation on responsible and safe management of spent fuel and radioactive waste was adopted in the European Union (EU). It aims at ensuring a high level of safety, avoiding undue burdens on future generations and enhancing transparency. EU Member States are responsible for the management of their spent fuel and/or radioactive waste. Each Member State remains free to define its fuel cycle policy. The spent fuel can be regarded either as a valuable resource that may be reprocessed or as radioactive waste that is destined for direct disposal. Whatever option is chosen, the disposal of high level waste, separated at reprocessing, or of spent fuel regarded as waste should be considered. The storage of radioactive waste, including long-term storage, is an interim solution, but not an alternative to disposal. To this end, each Member State has to establish, maintain and implement national policy, framework and programme for management of spent fuel and/or radioactive waste in the long term. Member States will invite international peer reviews to ensure that high safety standards are achieved. The EU approach is anchored in internationally endorsed principles and requirements of the IAEA safety standards and the Joint Convention and in this context makes them legally binding and enforceable in the EU. The EU approach of regulating the management of spent fuel and radioactive waste is anchored in the competence of the national regulatory authorities and in the internationally endorsed principles and requirements of the IAEA Safety Standards and the Joint Convention. Member States have to report to the Commission on the implementation of Directive 2011/70/Euratom for the first time by 23 August 2015, and every 3 years thereafter, taking advantage of the review and reporting under the Joint Convention. On the basis of the Member States' reports, the Commission will submit to the European Parliament and the Council a report on progress made and an inventory of radioactive waste and spent fuel present in the EU territory and the future prospects. Directive 2011/70/Euratom is a logical next step after the Council Directive 2009/71/Euratom on the nuclear safety of nuclear installations. The EU is the first major regional actor providing a binding legal framework on nuclear safety and on responsible and safe management of spent fuel and radioactive waste, and thus is a real model to progress spent fuel and waste management in a safe and responsible manner. (authors)

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DOE OSTI2017

Applying State-of-the-Art Tools for Safety-Optimized D and D - 17410

Decommissioning, Demolition and Disposal of 'hot' facilities (D3) is a relatively new science to the extent it has been part our public consciousness for ∼50-years. Due to the high hazard of uncontrolled exposure and the possibility of environmental release, the technologies applied to D3 have not embraced many of the recently developed engineering tools, especially those that leverage the digital and optical advances of the past 10-years. This summary paper provides an overview of how we are layering readily available technologies with sophisticated techniques to D3, ranging from agile program management to advanced modular construction to augmented reality. Using this approach, we are significantly improving safety and ALARA aspects while saving costs, optimizing schedules, maintaining quality and engaging the customer and the regulator in the D3 environment. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗
DOE OSTI2012

Study on Evaluation of Project Management Data for Decommissioning of Uranium Refining and Conversion Plant - 12234

Some of nuclear facilities that would no longer be required have been decommissioned in JAEA (Japan Atomic Energy Agency). A lot of nuclear facilities have to be decommissioned in JAEA in near future. To implement decommissioning of nuclear facilities, it was important to make a rational decommissioning plan. Therefore, project management data evaluation system for dismantling activities (PRODIA code) has been developed, and will be useful for making a detailed decommissioning plan for an object facility. Dismantling of dry conversion facility in the uranium refining and conversion plant (URCP) at Ningyo-toge began in 2008. During dismantling activities, project management data such as manpower and amount of waste generation have been collected. Such collected project management data has been evaluated and used to establish a calculation formula to calculate manpower for dismantling equipment of chemical process and calculate manpower for using a green house (GH) which was a temporary structure for preventing the spread of contaminants during dismantling. In the calculation formula to calculate project management data related to dismantling of equipment, the relation of dismantling manpower to each piece of equipment was evaluated. Furthermore, the relation of dismantling manpower to each chemical process was evaluated. The results showed promise for evaluating dismantling manpower with respect to each chemical process. In the calculation formula to calculate project management data related to use of the GH, relations of GH installation manpower and removal manpower to GH footprint were evaluated. Furthermore, the calculation formula for secondary waste generation was established. In this study, project management data related to dismantling of equipment and use of the GH were evaluated and analyzed. The project management data, manpower for dismantling of equipment, manpower for installation and removal of GH, and secondary waste generation from GH were considered. Establishment of the calculation formula for dismantling of each kind of equipment makes it possible to evaluate manpower for dismantling the whole facility. However, it is not easy to prepare calculation formula for all kinds of equipment that exist in the facility. Therefore, a simpler evaluation method was considered to calculate manpower based on facility characteristics. The results showed promise for evaluating dismantling manpower with respect to each chemical process. For dismantling of contaminated equipment, a GH has been used for protection of the spread of contamination. The use of a GH increases manpower for installation and removal of GH etc. Moreover, structural materials of the GH such as plastic sheets, adhesive tape become a burnable secondary waste. To create an effective dismantling plan, it is necessary to carefully consider use of a GH preliminarily. Thus, an evaluation method of project management data such as manpower and secondary waste generation was considered. The results showed promise for evaluating project management data of GH by using established calculation formula. (authors)

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗
DOE OSTI2018

Mixing Waste + Thermal Treatment: A Solution to the Problematic Waste Challenge? - 18366

Credible solutions exist for the management, treatment and disposal of all categories of Problematic Low Level Waste (PLLW); however the wastes are often ill defined and the costs associated tend to be disproportionately high; twenty times greater than that associated with LLW. The challenge posed to the nuclear industry is not one of technology but of economics and characterization. There are many PLLW categories, but the associated waste volumes are small (often < 100 m{sup 3}/category) which represents a poor value proposition to develop and deploy specialist technology for each. To meet the industry challenge, and to balance economics with safety and quality, a technology is required that is adaptable enough to process a large fraction of PLLW categories, present a favorable level of characterization and process in sufficient volumes to reduce cost. One approach is waste mixing which is becoming an accepted technique in waste management; however this does not address issues that make wastes problematic as it does not typically change the physico-chemical characteristics of the waste. Techniques are being developed for the conditioning of PLLW waste categories. Presently these are not commercially ready (low Technology Readiness Level, TRL) or have not met the economic challenge posed. GeoMelt is a thermal treatment technology with a track record over 30 years and capable of providing a viable solution. It has a demonstrated capability to co-process mixed wastes and is able to process wastes that fall into the PLLW category. This paper discusses how GeoMelt can be used to co-process waste economically and provides a feasible characterization strategy to present a viable approach to the conditioning and co-disposal of problematic wastes in the UK. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗
DOE OSTI2019

Technical Basis and Implementation of Groundwater Pathway Models Used for INL’s RH LLW Disposal Facility Performance Assessment

The Idaho National Laboratory’s (INL’s) Remote-Handled Low-Level Waste (RH LLW) Disposal Facility has been designed and constructed to receive waste generated on INL in support of the Office of Nuclear Energy (NE) and Naval Reactors (NR) missions. RH LLW is generated on the INL site from spent nuclear fuel handling and operations at the Naval Reactors Facility (NRF), the Advanced Test Reactor (ATR), and at the Material and Fuels Complex (MFC) in addition to other miscellaneous research activities. The facility has been designed to receive RH LLW currently in storage at INL facilities and new waste generated by nuclear research programs. RH LLW received at the facility is solid waste consisting of surface contaminated debris, ion exchange resins used to purify cooling water, and activated metals generated during reactor core change outs, Naval spent fuel management, and nuclear R&D. The facility has been designed to meet the requirements of DOE Order 435.1, Radioactive Waste Management [1] for all-pathways including groundwater and air, radon emissions limits, and inadvertent intrusion limits. The facility design includes a vault system incorporating robust concrete vaults oriented vertically in close-packed arrays, a hydraulic drainage system designed to limit water contact with the stainless steel waste canisters/liners and concrete vaults, and a robust monitoring system. Per the environmental assessment (EA) [2], all waste will be disposed of in stainless steel waste canisters/liners. During facility design and construction, site-specific data was collected to provide laboratory and field scale performance characteristics for the concrete vault and hydraulic drainage systems. Field-scale infiltration tests were conducted and monitored and the data was interpreted using numerical simulation. Based on interpretation of the observed laboratory and field test data, the facility performance assessment (PA) was developed. The PA groundwater pathway source release model differentially credits release from surface contaminated debris, ion exchange resins, and activated metals. It also credits failure of the steel waste canisters/liners with failure rates based on actual corrosion data. Once released, transport through the vadose zone and aquifer to downgradient receptor locations was simulated in the PA using a one-dimensional modeling approach based on historical three-dimensional modeling of historically-contaminated INL sites. This paper provides an overview of the groundwater pathway source release models and their technical implementation in the PA. It also describes the one-dimensional transport model used for the vadose zone and multi-dimensional model used for the aquifer.

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗
DOE OSTI2019

Oblivion Landscapes - 19008

This paper and presentation reflect on proposals that may offer ways to integrate hidden landscapes - such as the ones that house nuclear waste or other toxic/hazardous conditions - into concepts of collective memory, and mental/perceptive maps of populations - with the larger goal of creating new levels of awareness, intelligence and operability regarding their existence and potential future role in civilization. The proposals belong to a series of Architecture Design Studios called and dedicated to the theme of 'Planetology', within which is inserted the theme of Massive Oblivion Landscapes. In the context of this Symposium, these reflections may help rethink how to design modes of communication that lay out concepts of danger, waste and cultural memory. And, in this way, reclaim for these infrastructural landscapes, the role of information rich and culturally relevant typologies. (authors)

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