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Search indexed NASA NTRS and DOE OSTI research on propulsion, heat transfer, battery materials and energy systems. Follow report and document links to the original sources.

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All sourcesNASA NTRSDOE OSTI
DOE OSTI2013

The Management of the Radioactive Waste Generated by Cernavoda NPP, Romania, an Example of International Cooperation - 13449

The design criteria and constraints for the development of the management strategy for radioactive waste generated from operating and decommissioning of CANDU Nuclear Units from Cernavoda NPP in Romania, present many specific aspects. The main characteristics of CANDU type waste are its high concentrations of tritium and radiocarbon. Also, the existing management strategy for radioactive waste at Cernavoda NPP provides no treatment or conditioning for radioactive waste disposal. These characteristics embodied a challenging effort, in order to select a proper strategy for radioactive waste management at present, when Romania is an EU member and a signatory country of the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management. The helping of advanced countries in radioactive waste management, directly or into the frame of the international organizations, like IAEA, become solve the aforementioned challenges at adequate level. (authors)

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DOE OSTI2013

Handling of Highly Radioactive Radiation Sources in a Hot Cell Using a Mechanically Driven Cell Crane - 13452

In 2010, Siempelkamp Nukleartechnik GmbH was awarded the contract for design and erection of a Hot Cell for handling and storage of highly radioactive radiation sources. This Hot Cell is part of a new hot cell laboratory, constructed for the NHZ (Neues Handhabungszentrum = New Handling Center) of the Nuclear Engineering Seibersdorf GmbH (NES). All incurring radioactive materials from Austria are collected in the NHZ, where they are safely conditioned and stored temporarily until their final storage. The main tasks of the NES include, apart from the collection, conditioning and storage of radioactive waste, also the reprocessing and the decontamination of facilities and laboratories originating from 45 years of research and development at the Seibersdorf site as well as the operation of the Hot Cell Laboratory [1]. The new Hot Cell Laboratory inside the NHZ consists of the following room areas: - One hot cell, placed in the center, for remote controlled, radiation protected handling of radioactive materials, including an integrated floor storage for the long-term temporary storage of highly radioactive radiation sources; - An anteroom for the loading and unloading of the hot cell; - One control room for the remote controlling of the hot cell equipment; - One floor storage, placed laterally to the hot cell, for burial, interim storage and removal of fissionable radioactive material in leak-proof packed units in 100 l drums. The specific design activity of the hot cell of 1.85 Pbq relating to 1-Me-Radiator including the integrated floor storage influences realization and design of the components used in the cell significantly. (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)

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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)

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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.

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DOE OSTI2012

Radiological Survey of Contaminated Installations of Research Reactor before Dismantling in High Dose Conditions with Complex for Remote Measurements of Radioactivity - 12069

Decontamination and decommissioning of the research reactors MR (Testing Reactor) and RFT (Reactor of Physics and Technology) has recently been initiated in the National Research Center (NRC) 'Kurchatov institute', Moscow. These research reactors have a long history and many installations - nine loop facilities for experiments with different kinds of fuel. When decommissioning nuclear facilities it is necessary to measure the distribution of radioactive contamination in the rooms and at the equipment at high levels of background radiation. At 'Kurchatov Institute' some special remote control measuring systems were developed and they are applied during dismantling of the reactors MR and RFT. For a survey of high-level objects a radiometric system mounted on the robotic Brokk vehicle is used. This system has two (4π and collimated) dose meters and a high resolution video camera. Maximum measured dose rate for this system is ∼8.5 Sv/h. To determine the composition of contaminants, a portable spectrometric system is used. It is a remotely controlled, collimated detector for scanning the distribution of radioactive contamination. To obtain a detailed distribution of contamination a remote-controlled gamma camera is applied. For work at highly contaminated premises with non-uniform background radiation, another camera is equipped with rotating coded mask (coded aperture imaging). As a result, a new system of instruments for remote radioactivity measurements with wide range of sensitivity and angular resolution was developed. The experience and results of measurements in different areas of the reactor and at its loop installations, with emphasis on the radioactive survey of highly-contaminated samples, are presented. These activities are conducted under the Federal Program for Nuclear and Radiation Safety of Russia. Adaptation of complex remote measurements of radioactivity and survey of contaminated installations of research reactor before dismantling in high dose conditions has proven successful. The radioactivity measuring devices for operation at high, non-uniform dose background were tested in the field and a new data of measurement of contamination distribution in the premises and installations were obtained. (authors)

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DOE OSTI2012

On-site Destruction of Radioactive Oily Wastes Using Adsorption Coupled with Electrochemical Regeneration - 12221

Arvia{sup R}, working with Magnox Ltd, has developed the technology of adsorption coupled with electrochemical regeneration for the degradation of orphan radioactive oil wastes. The process results in the complete destruction of the organic phase where the radioactivity is transferred to liquid and solid secondary wastes that can then be processed using existing authorised on-site waste-treatment facilities.. Following on from successful laboratory and pilot scale trials, a full scale, site based demonstrator unit was commissioned at the Magnox Trawsfynydd decommissioning site to destroy 10 l of LLW and ILW radioactive oils. Over 99% of the emulsified oil was removed and destroyed with the majority of activity (80 - 90%) being transferred to the aqueous phase. Secondary wastes were disposed of via existing routes with the majority being disposed of via the sites active effluent treatment plant. The regeneration energy required to destroy a litre of oil was 42.5 kWh/l oil. This on-site treatment approach eliminates the risks and cost associated with transporting the active waste oils off site for incineration or other treatment. The Arvia{sup R} process of adsorption coupled with electrochemical regeneration has successfully demonstrated the removal and destruction of LLW and ILW radioactive oils on a nuclear site. Over 99.9% of the emulsified oil was removed, with the majority of the radioactive species transferred to the aqueous, supernate, phase (typically 80 - 90 %). The exception to this is Cs-137 which appears to be more evenly distributed, with 43% associated with the liquid phase and 33 % with the Nyex, the remainder associated with the electrode bed. The situation with Plutonium may be similar, but this requires confirmation, hence further work is underway to understand the full nature of the electrode bed radioactive burden and its distribution within the body of the electrodes. - Tritium gaseous discharges were negligible; hence no off-gas treatment before direct discharge to atmosphere is necessary. All secondary wastes were suitable for disposal using existing disposal routes, with the majority of the activity being successfully discharged as active water via the site active drains. - Oil destruction was achieved at a rate of 28.2 ml/hr using a regeneration energy of 42.5 kWh/l oil. The treatment of different active and non-active oils was achieved using the same operating parameters, providing strong evidence that the process is robust and will treat a wide range of oils, organic wastes and additives. - Currently the design of a plant capable of processing 1000 ml/hr is being established in discussion with Magnox Ltd. The plant will run automatically with little operator attention and so process between 5-8 m{sup 3} of ILW oil per annum. (authors)

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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)

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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)

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DOE OSTI2019

Taking in Nuclear Operation of the Plasma Facility for Treatment Industrial Radioactive Waste - 19346

The operation and maintenance of nuclear power plants, the nuclear fuel cycle in general, research laboratories and pharmaceutical, medical and industrial facilities generate low-level radioactive waste which, along with the historical radioactive waste from past nuclear activities, needs to be treated and stored, awaiting final disposal. Plasma technology offers a very effective way of treating this waste with a high volume reduction factor (VRF), free from organics, liquids and moisture, and meets without a doubt the acceptance criteria for safe storage and disposal. By means of a plasma beam of approximately 5000 deg. C, the inorganic materials are melted into a glassy slag, containing most of the radioactive isotopes while the organic material is gasified and afterwards oxidized in an afterburner and purified in an off-gas cleaning system. This paper describes the principles of plasma, the different waste feed systems, off-gas treatment and operational experience and future plasma plants. More specifically, it presents the new full-scale plasma facility for the treatment of radioactive waste at the Kozloduy Nuclear Power Plant in Bulgaria for which construction and assembly was finalized end of August 2016. It also describes in more detail the Site Acceptance Tests (SAT) of this facility. Previous paper describes the construction and testing of the plasma melting facility at the Kozloduy NPP in Bulgaria. Now the paper focus on the nuclear starting up conducted in May 2018 with real radioactive waste and illustrates the first operational results such as types of waste treated, volume reduction factors, etc The Project was co-financed through a grant by Kozloduy International Decommissioning fund (KIDSF) administrated by the EBRD and through Bulgarian national funding -Nuclear Facilities Decommissioning Fund and Radioactive Waste Fund. The KIDSF is funded by the European Union as well by the contributors to the KIDSF - Austria, Belgium, France, Greece, Ireland, The Netherlands, Spain, United Kingdom and Switzerland. (author)

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DOE OSTI2020

Geographic Information System Based Emergency Response Training Assessments for DOE Radioactive Materials Transport - 20027

Safety and security are priorities of U.S. Department of Energy (DOE) radioactive materials shipping campaigns. In the more than 70-year history of domestic transport of spent nuclear fuel (SNF), there has never been a transportation-related radiological injury. To support transportation planning, among the tools that DOE uses is the Stakeholder Tool for Assessing Radioactive Transportation (START). START contains geospatial data and transportation route analyses capabilities designed to support a range of DOE transportation planning initiatives. One of those functions is the capability to support emergency response planning and training for State and Tribal jurisdictions located on routes used for DOE shipments of radioactive materials. As part of the Department's commitment to public safety, DOE provides federally-funded radiological response training to emergency responders along DOE radioactive materials transportation corridors through its Transportation Emergency Preparedness Program (TEPP). START contains spatial data representing the locations and emergency-response capabilities of fire departments, police, hospitals, State emergency response centers, and where TEPP-trained personnel are based. The START tool supports State and Tribal users' ability to evaluate emergency-response coverage on active and potential DOE radioactive materials transport routes through their jurisdictions, provide expected response times to reach the scene of an incident, identify equipment available to support a response, and identify the number of response personnel and their respective training levels. In addition, START can be used to identify gaps in coverage along a transportation corridor where additional radiological emergency response training may be needed. This paper describes the data, features, and functionality DOE uses to provide a resource for emergency response training needs assessments for States and Tribes along active and potential routes for transporting radioactive materials, and illustrates its use. It also discusses future plans to integrate TEPP and Federal Emergency Management Agency (FEMA) radiological training data to provide a more comprehensive source of geospatial information on personnel who have received equivalent radiological response training. (authors)

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DOE OSTI2023

Proof of principle study: synchrotron X-ray fluorescence microscopy for identification of previously radioactive microparticles and elemental mapping of FFPE tissues

Biobanks containing formalin-fixed, paraffin-embedded (FFPE) tissues from animals and human atomic-bomb survivors exposed to radioactive particulates remain a vital resource for understanding the molecular effects of radiation exposure. These samples are often decades old and prepared using harsh fixation processes which limit sample imaging options. Optical imaging of hematoxylin and eosin (H&E) stained tissues may be the only feasible processing option, however, H&E images provide no information about radioactive microparticles or radioactive history. Synchrotron X-ray fluorescence microscopy (XFM) is a robust, non-destructive, semi-quantitative technique for elemental mapping and identifying candidate chemical element biomarkers in FFPE tissues. Still, XFM has never been used to uncover distribution of formerly radioactive micro-particulates in FFPE canine specimens collected more than 30 years ago. In this work, we demonstrate the first use of low-, medium-, and high-resolution XFM to generate 2D elemental maps of ~ 35-year-old, canine FFPE lung and lymph node specimens stored in the Northwestern University Radiobiology Archive documenting distribution of formerly radioactive micro-particulates. Additionally, we use XFM to identify individual microparticles and detect daughter products of radioactive decay. The results of this proof-of-principle study support the use of XFM to map chemical element composition in historic FFPE specimens and conduct radioactive micro-particulate forensics.

62 RADIOLOGY AND NUCLEAR MEDICINE↗
DOE OSTI2016

Dynamic Radioactive Source for Evaluating and Demonstrating Time-dependent Performance of Continuous Air Monitors

Evaluation of continuous air monitors in the presence of a plutonium aerosol is time intensive, expensive, and requires a specialized facility. The Radiation Protection Services Group at Los Alamos National Laboratory has designed a Dynamic Radioactive Source, intended to replace plutonium aerosol challenge testing. Furthermore, the Dynamic Radioactive Source is small enough to be inserted into the sampler filter chamber of a typical continuous air monitor. Time-dependent radioactivity is introduced from electroplated sources for real-time testing of a continuous air monitor where a mechanical wristwatch motor rotates a mask above an alpha-emitting electroplated disk source. The mask is attached to the watch’s minute hand, and as it rotates, more of the underlying source is revealed. The alpha activity we measured increases with time, simulating the arrival of airborne radioactive particulates at the air sampler inlet. The Dynamic Radioactive Source allows the temporal behavior of puff and chronic release conditions to be mimicked without the need for radioactive aerosols. The new system is configurable to different continuous air monitor designs and provides an in-house testing capability (benchtop compatible). It is a repeatable and reusable system and does not contaminate the tested air monitor. Test benefits include direct user control, realistic (plutonium) aerosol spectra, and iterative development of continuous air monitor alarm algorithms. We also used data obtained using the Dynamic Radioactive Source to elucidate alarm algorithms and to compare the response time of two commercial continuous air monitors.

07 ISOTOPE AND RADIATION SOURCES↗