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DOE OSTI2018

Improvement of Discharge Regulation System for Liquid and Gaseous Radioactive Materials in Korea - 18050

In this study, we analyzed radioactive waste management practices and discharge regulations for liquid and gaseous radioactive materials generated from the nuclear power plants. Liquid and gaseous radioactive materials are discharged into the environment in a controlled and monitored state after proper treatment. In order to prevent radiological hazards due to the release of radioactive materials, the standards for effluent control limits and off-site dose constraints at the boundary of exclusion area shall be met. In December 2015, the Nuclear Safety Act was partially amended to add the 'Discharge Plan for Liquid and Gaseous Radioactive Materials' to the application form for the power reactor operating licenses. The Discharge Plan shall include the total amount of liquid and gaseous radioactive materials per site, period (annual, quarterly, etc.), and radionuclide group. Therefore, nuclear power plant operators are required to set in advance the total amount of liquid and gaseous radioactive materials for each radionuclide group per site, and keep them below the control limits during the operation of the facilities. Accordingly, it is expected that public trust regarding regulations on effluent discharge as well as effluent control itself can be further improved. (authors)

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DOE OSTI2019

Inventory of Radioactive Waste in Canada - 19336

Since 1999, the Government of Canada has been conducting a regular exercise of gathering and compiling Canada's radioactive waste inventory and projection data from waste owners and making it available to the public in the form of a triennial Inventory Summary Report. The goal of this data collection exercise has been to support federal policy development, support the Canadian Nuclear Safety Commission's regulatory activities, provide consolidated radioactive waste information for the nuclear industry, promote transparency, and meet Canada's international commitments and growing demands internationally for radioactive waste data. The detailed national inventory report provides an overview of the production, accumulation and future projections of radioactive waste in Canada. Since the coming into force of the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management in June 2001, the data collection and reporting cycle has been aligned to provide the waste inventory data required for Canada's triennial National Report for the Joint Convention. This paper presents Canada's radioactive waste inventory and projection data as of the end of December 2016, and summarizes key findings from the analysis of the data. For this reporting cycle, the waste data collected was expanded to include more detailed information on the decommissioning schedules and associated waste volume projections for nuclear power plants, and research and prototype reactors, as well as plans for transitioning waste inventories from storage to long-term management and disposal facilities, based on current schedules for establishing these facilities in Canada. With this additional information, the Government of Canada and Canadian stakeholders are better able to understand the waste disposal capacity and schedules required to accommodate all nuclear fuel waste and radioactive waste that will be produced by Canada's existing fleet of nuclear power plants and research reactors. The collection and analysis of projected waste volumes to be emplaced in long-term management facilities is in line with and will support the proposed methodology of presenting waste inventories in terms of management strategy and disposal routes by the Organization for Economic Cooperation and Development Nuclear Energy Agency Expert Group on Waste Inventorying and Reporting Methodology. The paper describes some of the uses that are made of the waste inventory information, as well as Canada's approach to national inventory data collection and its experience and lessons learned. Canada continues to modernize the format of the Inventory Summary Report with the goal of disseminating the technical information into an attractive and public-friendly report. (authors)

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DOE OSTI2020

Development of the 3 m{sup 3} Low Level Radioactive Waste Container in Taiwan - 20037

Chinshan Nuclear Power Plant stopped its business operation in July, 2019, and Kuosheng Nuclear Power Plant will also be permanently shut down in 2023. Nuclear Reactor Facilities Regulation Act requires a nuclear facility must be dismantled in 25 years after being permanently ceased operation. According to the approved decommissioning plan of Chinshan Nuclear Power Plant and the proposed one of Kuosheng Nuclear Power Plant, the 3 m{sup 3} low level radioactive waste container is planned to store the low level radioactive wastes with higher radiation produced during the decommissioning. However, 3 m{sup 3} low level radioactive waste containers are not used or developed in Taiwan before. To meet such need, Institute of Nuclear Energy Research develops a new type of 3 m{sup 3} low level radioactive waste container and performs the corresponding analyses and tests based on Guidelines of Applying the Usage License of Low Level Radioactive Waste Containers and Regulations for the Safe Transport of Radioactive Material. In this article, it provides the information of the low level radioactive waste containers that have been approved or is under reviewing in Taiwan, and so do the design specifications of the developed 3 m{sup 3} waste container. Besides, the numerical evaluation and test results of the developed 3 m{sup 3} waste container are also included in this article. Based on the evaluation and test results, the developed 3 m{sup 3} waste container satisfies the requirements of the storage container and industrial package type 2. Institute of Nuclear Energy Research will submit the usage license applications to the authority this year, and the usage licenses would be granted in 2021, expectedly. (authors)

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DOE OSTI2019

Fiscal Year 2018 Annual Summary Report for the Area 3 and Area 5 Radioactive Waste Management Sites at the Nevada National Security Site, Nye County, Nevada

The U.S. Department of Energy Standard Disposal Authorization Statement and Tank Closure Documentation (DOE-STD-5002-2017) requires preparation of an Annual Summary Report comparing low-level radioactive waste disposal facilities operations with the Disposal Authorization Statement (DAS) and its supporting technical documents including the performance assessment (PA) and the composite analysis (CA). The fiscal year (FY) 2018 Annual Summary Report for the Area 3 and Area 5 Radioactive Waste Management Sites (RWMSs) was prepared by reviewing planned and discovered changes, waste receipts, monitoring results, research and development (R&D) results, and the status of DAS conditions and issues to assess the validity of the DASs, PAs, and CAs. The Area 3 RWMS was placed in stand-by in 2006 and remained inactive in FY 2018. Resumption of waste disposal operations is planned for FY 2019. No proposed actions, new information, or discoveries affecting the Area 3 RWMS were identified in FY 2018. No significant changes have occurred since preparation of the most recent special analysis, which indicates a continuing reasonable expectation of meeting the PA performance objectives and measures, and the CA dose constraint in DOE O 435.1, “Radioactive Waste Management.” No changes were made to documents supporting the Radioactive Waste Management Basis (RWMB) including the PA, CA, DAS, waste acceptance criteria (WAC), closure plan, monitoring plan, or maintenance plan. Monitoring results for the most recent year with available data, calendar year (CY) 2017, indicate no changes to long-term trends and no results inconsistent with expected performance. R&D results for the Area 3 RWMS Drainage Lysimeter Facility continue to be consistent with the conceptual site model (CSM). All Area 3 RWMS DAS conditions and secondary issues were closed in 2002. The Area 5 RWMS continued disposal operations within the Northern Expansion Area in FY 2018. Eighty-six changes involving proposed actions, new information, or discoveries affecting the Area 5 RWMS PA and CA were screened during FY 2018 in the Unreviewed disposal question (UDQ) process. Twenty-two changes required UDQ evaluations and two changes resulted in unreviewed composite analysis question evaluations. None of the proposed actions, new information, or discoveries had significant impacts on the PAs or CAs. All of the planned changes were implemented. No special analyses were performed, and no changes were made to documents supporting the RWMB including the PA, CA, DAS, WAC, closure plan, monitoring plan, or maintenance plan. Planning continued and construction commenced on development of the Western Expansion Area within the Radioactive Waste Management Complex. All Area 5 RWMS DAS conditions and secondary issues were closed in 2002. The cumulative effects of changes occurring since preparation of the Area 5 RWMS PA and CA were assessed with the current baseline PA/CA model. Model results indicate that there is a reasonable expectation that the PA performance objectives and measures, and the CA dose constraint in DOE O 435.1, “Radioactive Waste Management,” can be met. No PA or CA mean result exceeds 50% of its performance objective. Monitoring results and R&D results continue to be consistent with the CSM. Monitoring results for CY 2017 indicate no changes to long-term trends and no results inconsistent with expected performance. R&D results for the Area 5 RWMS Weighing Lysimeter Facility continue to be consistent with the CSM. The FY 2018 review of Area 3 RWMS and Area 5 RWMS disposal operations supports the following conclusions: The Area 3 and Area 5 RWMS PA and associated CA assumptions and conclusions remain valid based on consideration of all changes identified or planned; The reasonable expectation that the Area 3 and Area 5 RWMSs will meet the performance objectives identified in DOE O 435.1, “Radioactive Waste Management”, remains valid; and The DAS, based on interpretation of the data collected, monitoring results, and other information, continues to be adequate.

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DOE OSTI2019

Radiological Risk From Disused Radioactive Sealed Sources in Egypt - 19083

Sealed sources are radioactive nuclear substances encased in a sealed capsule or in a cover to which the substance is bonded, and are used for a variety of activities, such as medical, industrial, academic and research, as well as commercial applications. While most sources are of relatively low activity, there are many of medium or very high activity. In use radioactive sealed sources after time become disused sources according to several reasons like, if the source activity became less than the desired activity (unfit for the intended application), if the model of the instrument became old fashion and no longer uses, if the source had been damaged, and if the user company was shut down and no longer in business. In developing countries, thousands of radium needles, teletherapy sources, oil well logging neutron sources, and miscellaneous industrial radioactive gauges are annually collected as waste and stored in centralized waste facilities. Although these sources become disused, it still dangerous and the mismanagement of high activity sources is responsible for most of the radiological accidents that result in loss of life or disabling injuries. On the other hand, these sources may be a target for criminal acts in countries where final disposal options are unavailable. Egyptian Atomic Energy Authority (EAEA) represented in Hot Labs and Waste Management Center (HLWMC) is responsible by the national nuclear law (law No. 7 /2010) for management of all kinds of radioactive waste including disused radioactive sealed sources from all Egyptian territories. Categorization of disused sources is necessary to ensure that the controls and security measures that are applied to the sources are adequate with its radiological risk. The aim of this work is to use the international Atomic Energy Agency (IAEA) categorization system to provide a simple, logical system for grading disused radioactive sealed sources in Egypt as well as to update the inventory of such sources which already collected as waste in Egypt. The categorizations of radioactive sealed sources are based on their potential to cause harm to human health. This study revealed that nearly 980 sources have been defined in Egypt as disused sources with a total activity of 46100 Ci according to available data in July 2018. (author)

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DOE OSTI2019

Radioactive Waste Minimization - Clearance for Reuse, Recycling and Disposal - 19598

Virtually all activities related to radioactive materials and to the utilization of nuclear energy generate radioactive waste. Due to limited storage facilities and waning public acceptance for long-term disposal of radioactive waste as well as the associated cost, implementation of strategies and methods for its effective reduction are mandatory. Clearance of materials is one possible concept to reach this goal. The International Atomic Energy Agency (IAEA) defines the process of clearance as 'the removal of radioactive materials or radioactive objects within authorized practices from any further regulatory control by the regulatory body.' Thus, these materials are no further treated as radioactive waste and may be recycled or disposed of conventionally. In quantitative terms, clearance is generally related to the '10 μSv-Concept' This means that the effective dose expected to be incurred by any member of the public due to cleared materials is of the order of 10 μSv or less in a year. A combination of appropriate clearance concepts, methods and measurement techniques, following an integrated clearance strategy for a project, allows the return of up to 97 % of the mass of a decommissioned NPP to the conventional waste cycle. This includes the concept of clearance for a specific purpose, often referred to as 'conditional clearance', i.e. the case where a certain condition has to be fulfilled before the act of clearance has been completed. As a technical expert organization, TUV NORD EnSys accompanied the development, implementation and execution of clearance procedures in more than 13 nuclear power-plants and installations, either operational or in various states of decommissioning. Thus, TUV Nord EnSys has abundant experience in and a comprehensive overview on the implementation of different clearance strategies and procedures. Considering the increased waste-volumes and additional waste-streams to be handled during decommissioning, the transition to a decommission-focused clearance system is of vital importance for successful waste-minimization. This paper provides a view on the perspective of a technical support organisation (TSO) towards implementation of a holistic clearance strategy into the decommissioning concept for radioactive waste minimization. (authors)

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DOE OSTI2016

Assessment on security system of radioactive sources used in hospitals of Thailand

Unsecured radioactive sources have caused deaths and serious injuries in many parts of the world. In Thailand, there are 17 hospitals that use teletherapy with cobalt-60 radioactive sources. They need to be secured in order to prevent unauthorized removal, sabotage and terrorists from using such materials in a radiological weapon. The security system of radioactive sources in Thailand is regulated by the Office of Atoms for Peace in compliance with Global Threat Reduction Initiative (GTRI), U.S. DOE, which has started to be implemented since 2010. This study aims to perform an assessment on the security system of radioactive sources used in hospitals in Thailand and the results can be used as a recommended baseline data for development or improvement of hospitals on the security system of a radioactive source at a national regulatory level and policy level. Results from questionnaires reveal that in 11 out of 17 hospitals (64.70%), there were a few differences in conditions of hospitals using radioactive sources with installation of the security system and those without installation of the security system. Also, personals working with radioactive sources did not clearly understand the nuclear security law. Thus, government organizations should be encouraged to arrange trainings on nuclear security to increase the level of understanding. In the future, it is recommended that the responsible government organization issues a minimum requirement of nuclear security for every medical facility using radioactive sources.

07 ISOTOPE AND RADIATION SOURCES↗
DOE OSTI2020

A Dose Assessment Model for Radioactive Waste Exposed by Gully Erosion at West Valley - 20513

The Western New York Nuclear Service Center (WNYNSC), located approximately 48 km south of Buffalo, New York, is the site of a former nuclear fuel reprocessing and radioactive waste disposal facility. Spent nuclear fuel was processed there from 1966 to 1972, leaving behind radioactive and chemical wastes in two disposal areas and a waste tank farm. Site operations also resulted in releases of radioactivity to site soils, groundwater, and to surface waters draining the site. The New York State Energy Research and Development Authority (NYSERDA) and the U.S. Department of Energy (DOE) are collaborating in a process of decision making for decommissioning those facilities remaining at the WNYNSC following the completion of Phase 1 decommissioning. Neptune and Company, Inc. (Neptune) was contracted to develop a probabilistic performance assessment (PPA) computer model to assist the agencies in this process. The PPA Model includes a contaminant transport component focusing on the movement of contaminants within and among environmental media including groundwater and surface water transport, contaminant translocation by plants and animals, diffusion, and erosion. The model also includes evaluation of potential exposure and health effects for a Resident Farmer exposure scenario, where the Resident Farmer represents a critical group, described as that group of individuals reasonably expected to receive the greatest exposure to residual radioactivity for any applicable set of circumstances. The West Valley Site is located in the glaciated Allegheny Plateau region of western New York State. The waste reprocessing and disposal areas were constructed on a relatively fat area of plateau dissected by drainages of Buttermilk Creek, including Erdman Brook, Franks Creek, and Quarry Creek. An important aspect of the contaminant transport component of the PPA model is consideration of erosive processes such as slumping of the stream slopes and the advance of gullies from these streams. These erosion processes remove material from the plateau, growing the size of the creek valleys and making them wider and deeper. Of particular interest for the impact of erosion is radioactive waste contained in the Nuclear Regulatory Commission (NRC)-Licensed Disposal Area (NDA), the New York State-Licensed Disposal Area (SDA), and residual radiological inventory in the underground storage tanks at the Waste Tank Farm (WTF). The PPA Model is organized around geographically-defined facilities which were constructed upon the plateau, including the NDA, SDA, and WTF. Ongoing stream erosion processes will potentially transfer radioactive waste and residual inventory from these facilities to the ground surface on adjacent hillslope areas where erosion has breached the facility. Hence, it is important to evaluate the consequences of potential exposures to a Resident Farmer on the hillslopes below a breached facility. Two interrelated aspects of the dose assessment model related to hillslope exposure are discussed: 1) representation of the physical processes related to transport of radionuclides from facilities onto the hillslopes, and from the hillslopes into adjoining creeks where contaminated material migrates downstream with surface water and sediment, and; 2) adaptation of the activities associated with the Resident Farmer scenario to assess potential exposures to contamination in the hillslope areas. This discussion will cover the conceptual basis of the hillslope exposure and transport models, and also implementation in the PPA computer model. (authors)

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DOE OSTI2017

Risks of Hazardous Substances in Radioactive Waste for the Konrad Repository in Germany - 17522

When disposing of radioactive waste with negligible heat generation, the activity of the radionuclides is limited. However, the waste including radioactive material comprises a certain proportion of non-radioactive material. The risk of hazardous contamination of the groundwater by non-radioactive substances must be taken into account. It must be ascertained that the non-radioactive material cannot affect near-surface groundwater, which is a resource for drinking water supply. To achieve this, limit values on the amount of hazardous substances in the total waste volume shall be determined. In 2002 a regulatory approval was granted to the 'Konrad' final storage facility for radioactive waste with negligible heat generation according to the German Water Resources Act. This approval is embedded in the license (plan-approval decision) based on the German Atomic Energy Act. The approval is based on the model of a possible discharge of contaminants from the final storage facility. In a long-term simulation spanning 300,000 years, contact of the waste with the groundwater in the surrounding rock formations over the postoperational phase was conservatively assumed. The maximum amount of allowable disposal of substances - such that no concern of affecting the near-surface groundwater arises - can be derived from the solubility of the respective substances. Implementing the permit according to the Water Resources Act requires: - classification of the waste through delivery declaration obligations - monitoring the substance inspection in the waste to assess its suitability for the disposal, and - stock keeping procedures for the disposal waste by the operator. While the repository is operated by the Federal Office for Radiation Protection (BfS) (http://www.bfs.de./EN/home/home{sub n}ode;), reporting to the Federal Environment Ministry, the statutory water permit is issued and applied by the State of Lower Saxony as responsible state authority. A waste package/container list supplements a comprehensive list of substances. From this - depending on the respectively conditioned waste - material vectors can be derived. For this purpose, BfS provides a database with a substances and container list to the waste owners. In the meantime, first experiences have been collected in applying the approval. More than 540 waste containers with a total mass of almost 6,000 Mg have been controlled and are ready for disposal. In our presentation we will show the recent development in supervising the preparation for the disposal of mixed waste. (authors)

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DOE OSTI2015

Radioactive waste management in France: taking-up present and future challenges - 15120

The reduction of the volume and radiotoxicity of radioactive waste has been one of the key drivers for the implementation of the French nuclear program. Interactions between the nuclear industry, the administration, the competent authorities and other stakeholders including the civil society has led to a continuous evolution of the industrial facilities, practices, solutions and products to move towards waste minimization. Bringing a solution to the management of ultimate radioactive waste is clearly a requirement for the sustainable development of nuclear energy whose crucial role in the world's future energy mix has been confirmed in the past few months by several international organizations. The first question to be answered concerns the definition of radioactive waste. This notion may be seen as self-evident. It is not. For example, used fuel is considered a High Level Waste in Finland or Sweden, but a recyclable material in countries including China, France, India, Japan, Russia, and the Netherlands. In France, a definition is provided by law to clarify this notion. Indeed, the 2006 French law concerning the Sustainable Management of Radioactive Materials and Waste stipulates that 'ultimate radioactive waste shall include any radioactive waste for which no further processing is possible under current technical and economic conditions, notably by extracting their recoverable fraction or by reducing their polluting or hazardous character'. Used fuel is thus reprocessed in order to reduce the final waste volume and long term radiotoxicity, while extracting value from the recovered materials. Even if the general approach and the processes may be common for waste management, it is important to clearly make the distinction between the wastes stemming from used fuel processing or conditioning (when considered as waste), the wastes generated through the operation of nuclear power plants and fuel cycle facilities, and the waste arising from the dismantling of nuclear installations. After a brief overview of the different types of waste stemming from nuclear power generation, this paper will review solutions and processes already implemented for their safe and efficient management. It will also practically illustrate the evolution of these processes and related facilities to further gain in efficiency, notably in terms of volume reduction; the related R and D outcomes will be addressed. It will also describe the upcoming challenges in this field and the envisioned solutions to respond to them; the efficiency, the completeness and consistency of these solutions with the currently considered global framework, based on a stepwise and long term approach from waste generation to disposal, will also be analyzed. (authors)

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DOE OSTI2015

EDF industrial strategy for the management of radioactive waste - 15204

In France, EDF is in charge of electronuclear power operation since the sixties and consequently has to manage radioactive waste. Radioactive waste management is based on the control of each industrial step, taking into account the classification by activity level and radioactive half life. The main steps are to limit waste quantities at the generation stage, sort out non-rad and recoverable items from the waste, recycle, treat and package the radioactive waste as soon as it is generated, limit the use of interim storage, prepare and achieve as soon as reasonably practicable conditioning and disposal. EDF aims to empower operators in charge of NPP operating and of decommissioning and to centralize interfaces with the stakeholders in order to pool management routes and to guarantee the consistency of our industrial policy. The French regulatory framework for the management of radioactive waste and material is set by the French 2006 planning Act, in line with the European Directive. The legal framework structures interactions between EDF and the regulatory bodies (Nuclear Safety Authority, General Directorate for Energy and Climate), the French National Radioactive Waste Management Agency (ANDRA) and other waste producer (mainly AREVA Company and CEA). Regarding short lived waste, management routes are in current operation for the large majority of this waste generated both by power plants in service and during decommissioning. EDF is working on new management route for metallic materials knowing the future evolution of deposits is the field of large refit and decommissioning activities. Regarding long lived waste, disposal development represents a major stake for EDF. EDF contributes to design studies of the geological disposal center and collaborates with ANDRA for the acceptance of future national waste disposal. (authors)

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DOE OSTI2016

Development and Maintenance of a Comprehensive Radioactive Waste Management Basis - 16349

In accordance with DOE Order 435.1, 'Radioactive Waste Management', radioactive facilities and activities must have a documented basis of operation consisting of procedures, and physical and administrative controls that ensure protection of workers, the public, and the environment. To fulfill this requirement, Department of Energy (DOE) facilities are required to have an approved Radioactive Waste Management Basis (RWMB) which provides assurance that controls are developed, documented, and implemented for management of radioactive waste. The required elements of the RWMB vary with the type of waste management operation or facility and the types of hazards associated with the facility. Therefore, a graded approach is used per DOE guidance. The Idaho National Laboratory Waste Management Program (WMP) has developed and implemented a thorough RWMB for each of its five operational areas in addition to facility specific DOE Order 435.1 compliance tables which served as a tool for developing each RWMB. With approximately 40 facilities generating and/or managing radioactive waste, the WMP has encountered several challenges in keeping RWMBs current and accurate, in addition to ensuring facilities are continually maintaining compliance in evolving conditions in support of programs and projects in a continuously expanding research environment. Prior to initial radioactive waste generation, nuclear facility management must demonstrate compliance via the facility safety basis and approved laboratory-wide and facility specific documents which are then incorporated into the RWMB and subsequently approved by the DOE-Idaho Operations field office designated point of contact. The WMP has incorporated several areas of improvement to its RWMB management strategy to help facilities maintain compliance in new and changing conditions. Improvements included providing ad hoc facility management training for new facility managers, adding a reviewer from the WMP during the environmental checklist process, and performing annual RWMB reviews which involve not only facility management, but also Waste Generator Services support personnel, and other support organizations, as applicable. (authors)

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DOE OSTI2016

A National Disposal Facility for Radioactive Waste for Iraq - 16610

Radioactive waste resulted in the past in Iraq from a number of nuclear activities and facilities all of them seriously damaged or destroyed during the Gulf war. The task of decommissioning such facilities and managing the resulting waste is being supported by the International Atomic Energy Agency (IAEA), the European Union (EU), and the United States (US). A national policy for radioactive waste management for Iraq has been drafted by the Ministry of Science and Technology (MoST); a draft strategy for radioactive waste management implementation is in preparation. In this framework, Iraq is considering locating a radioactive waste disposal facility at the Al-Tuwaitha site, near the capital city of Bagdad. In the framework of its Instrument for Nuclear Safety Cooperation the EU has recently started a cooperation project named 'Feasibility Study, Basic Design, and Engineering Design of an Engineered Radioactive Waste Disposal Facility' for Iraq (Project IQ4.01/11). The project aims at producing the design of a repository for the radioactive waste resulting from the decommissioning activities and from the continuing use of radioisotopes in medicine and the oil and gas industry in the country. The contract for this cooperation project was awarded by the European Commission in April 2015 to the consortium of two international engineering companies, Nukem Technologies Engineering Services GmbH and DBE Technology GmbH, both of Germany, and Javys a.s., the national waste management agency of Slovakia. The planned Iraqi near-surface repository is constrained by the complex security conditions in the country. This has led to the decision of using whenever possible the Al-Tuwaitha site, were most of the waste is located, as the repository location. The project work will therefore focus on assessing whether and which part of the waste expected to result from the decommissioning and remediation activities is amenable for surface disposal in an appropriately engineered facility. In addition, careful review of the site characteristics shall provide enough elements to justify and validate the political decision of disposing of the waste in Al Tuwaitha. Thereafter, the project work will focus on the conceptual and later the engineering design of the repository. Finally, a Safety Analysis will provide the basis for regulatory decisions about the further steps for realization of the Iraqi final disposal facility. (authors)

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DOE OSTI2019

Transportation of Radioactive Waste in Support of Ontario Power Generation's Darlington Nuclear Generating Station Refurbishment Project - 19384

Ontario Power Generation's (OPG) Darlington Nuclear Generating Station (DNGS) is currently executing a major refurbishment of the first of their four Candu reactors. As expected, the volumes of Low and Intermediate Level Waste (LILW) generated from this large-scale project have been significant. As a result, unique solutions were needed for the safe and efficient transportation of radioactive waste from the Darlington Nuclear Generating Station to OPG's Western Waste Management Facility for volume reduction and interim storage. OPG's Nuclear Waste Management Division and the Darlington Refurbishment Project worked together to identify unique radioactive waste transportation solutions. These solutions included staging and temporary storage facilities, new waste containers and specialized transportation packages, additional human resources and enhanced planning and logistics required to transport large volumes of routine and non-routine radioactive waste in a manner that minimized the impact on employee and public safety, project schedule and project costs. From a facilities perspective a shielded 'Marshalling Area' that allowed for loaded transportation packages to be staged was built on the Darlington site and a temporary licensed off-site radioactive waste storage facility close to the DNGS was contracted through a third party vendor. These two facilities allowed for more consistent and efficient schedules that limited radioactive waste shipments during off-hours and avoided peak traffic periods thereby limiting the risk to Refurbishment critical path activities. Special purpose-built transportation packages and waste containers were designed and fabricated to handle unique waste streams such as feeder pipes and other miscellaneous intermediate level waste items associated with reactor dismantling. Twenty-four Type A qualified transportation packages mounted to six flat deck trailers were designed and fabricated to support the shipment of contaminated feeder pipes. An Intermediate Level Waste Utility Container (ILWUC) to be used in conjunction with the Type B qualified Trillium Transportation Package was designed and fabricated to handle unique intermediate level waste streams arising from the reactor dismantling process. Logistics software was used to plan the shipments to ensure waste transportation packages could be loaded, transported, unloaded and returned safely to the project site in a timely manner without impacting project schedules. Several shipping scenarios were simulated and adjusted using the software to ensure that the most efficient use of equipment and resources for the radioactive waste transportation aspects of the project. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗
DOE OSTI2018

Conception and Operation of a New Treatment Center for Radioactive Waste from High Energy Accelerators - 18293

CERN has operated high-energy accelerators for more than 60 years of research in fundamental physics. The side-product of this activity is the generation of low- and intermediate-level radioactive waste, most of which is in solid form and free of surface contamination. Today, one operational year produces about 400 tons of radioactive waste which need to be disposed of towards the final repositories of the two CERN Host States, France and Switzerland. A new facility for the collection, interim storage, characterization and treatment of radioactive waste became operational at CERN in 2015. This facility was specifically conceived for an accelerator complex with a wide range of challenging waste items, which are often unique in their irradiation history as well as in their physical, chemical and radiological characteristics. The disposal rate was ramped up in 2016 with a unique treatment process tailored for metallic low-level waste. In 2017, two parallel processes were successfully tested for the elimination of radioactive cables and for the recycling of valuable metals. This paper gives an overview of the challenges in the design, commissioning and operation of the CERN radioactive waste treatment center. It outlines the methodology followed for the conception of the elimination processes, which can be of guidance for the development of similar facilities. (authors)

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

Maintenance Plan for the Performance Assessments and Composite Analyses for the Area 3 and Area 5 Radioactive Waste Management Sites at the Nevada National Security Site (Rev.3)

U.S. Department of Energy (DOE) Order 435.1, Radioactive Waste Management, requires that performance assessments (PAs) and composite analyses (CAs) for low-level radioactive waste (LLW) disposal facilities be maintained by the responsible field office. This plan describes the activities performed to maintain the PA and the CA for the Area 3 and Area 5 Radioactive Waste Management Sites (RWMSs) at the Nevada National Security Site (NNSS). The plan is based on DOE Order 435.1 Radioactive Waste Management (DOE 2007), DOE Manual 435.1-1, Radioactive Waste Management Manual (DOE 2011), and DOE Standard DOE-STD-5002-2017, Disposal Authorization Statement and Tank Closure Documentation (DOE 2017). The facility’s Disposal Authorization Statement (DAS) specifies conditions for the continuing operation of a LLW facility. The DAS is issued based on a review of the facility's PA, CA, the maintenance plan, preliminary closure plan, and preliminary monitoring plan. The DAS specifies the limits and conditions on construction, design, operations, and closure of the low-level waste facility based on these reviews. The Maintenance Plan uses an Unreviewed Disposal Question (UDQ)/Unreviewed Composite Analysis Question (UCAQ) change control process to identify, evaluate, and control planned or discovered changes affecting the PA, CA, DAS, or other documents composing the Radioactive Waste Management Basis (RWMB). The UDQ/UCAQ process uses the PA and CA GoldSim models to calculate updated results, assess the significance of changes, and to assess the need to revise the PA, CA, or DAS. In addition to the change control process, the Maintenance Plan requires an annual review of all changes and an annual assessment of the need to revise RWMB documents, plans, and programs. The cumulative effect of all changes is assessed annually by preparing a revised PA and CA baseline model that is used to update PA and CA results. The updated results are used to assess compliance with the PA performance objectives and the CA dose constraint, and to assess the need to revise the PAs, CAs, and other documents, plans, and programs supporting the RWMB. An Annual Summary Report documenting the results and conclusions of the annual review is prepared and submitted to DOE.

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗
DOE OSTI2015

The challenge: Safe management on spent and disused sealed radioactive source in Thailand - 15654

When sealed radioactive sources are no longer in use, they should be returned back to the country of origin. However, most of them could not be returned to the country of origin, therefore the safety management of spent and disused radioactive source is need. Thailand Institute of Nuclear Technology (TINT) where is as the national waste management center, has the duty to ensure on the safety and the security for long term storage of spent and disused sealed sources before final disposal. The Radioactive Waste Management Center at TINT, is authorized to operate treatment, conditioning and storage of radioactive waste. This paper will describe the proper operational procedures on characterization technique, identification of unknown sources, volume reduction technique, re-packaging, registration and record keeping of spent and disused radioactive source. The successful results exhibit that the record keeping of spent and disused source is developed, and the national inventory of spent and disused source is up to date. This paper would confirm the safety management of radioactive waste in Thailand. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗
DOE OSTI2016

Radioactive Waste Management in HANARO (High Flux Advanced Neutron Application Reactor) - 16076

HANARO (High Flux Advanced Neutron Application Reactor) is a research reactor at the Korea Atomic Energy Research Institute (KAERI). Currently, it is the only research reactor generating a high neutron flux for neutron science and technology and the production of radioisotopes in Korea. Various kinds of radioactive wastes such as wastewater, spent ion exchange resins, solid waste and gaseous waste are generated from HANARO, as in other nuclear reactors. The most important feature of the radioactive waste in HANARO is that some radioactive waste is contaminated with tritium because HANARO uses heavy water as a reflector. At present, the waste generated from HANARO is transferred to and treated or stored at the Radioactive Waste Treatment Facility (RWTF) of KAERI. However, the RWTF does not have proper technology to treat radioactive waste contaminated with tritium from HANARO. Therefore, it is imperative to have a proper means to reduce the amount of radioactive waste and handle it more safely. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗