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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

Development of a Methodology to Assess the Impact of Non-Conventional Waste Streams Following a Radiological Incident - 18271

The Environmental Protection Agency's (EPA's) Waste Estimation Support Tool (WEST) is a Geographic Information System (GIS)-based decision support tool for estimating waste generated from remediation and cleanup activities following a radiological incident. WEST uses the Federal Emergency Management Agency's (FEMA's) Hazus-MH software's infrastructure information combined with image classification capabilities to estimate the quantity of waste and debris that may result from a radiological incident. WEST can be used to create customized decontamination strategies that allow end-users to evaluate different means of decontamination and how those strategies may impact the resulting waste stream in each geographical locality. This capability can potentially reduce the response/recovery time frame and cost. One of the key observations from past applications of WEST is that planning scenarios are site-specific, especially when dealing with chemical, biological, radiological, or nuclear (CBRN) waste management issues. Furthermore, site-specific issues are not limited to resource limitations or response bottlenecks but should also account for differences in an area's geography and urban footprint, a phenomenon observed during the Fukushima response. For instance, a recent WEST case study found that the amount of waste generated per unit of affected area, for a given decontamination approach, is largely a function of the building surface area in the affected area (relative to the ground surfaces). However, differences in the geometry and density of contaminated objects in the landscape may impact the amount and characteristics of the waste stream. Although buildings typically constitute a large portion of the surface area in urban environments, other objects such as vehicles and trees can be just as prominent. For example, seasonal changes in the amount of foliage present can alter the non-structural surface area calculated for an area like New York City by 20-30%. Very little is known about the impact that these non-conventional waste streams have on overall remediation strategies, or to what extent differences in characteristics of urban versus rural environments, traffic activities, or seasonal variations may have on these factors. This paper will present the proposed methodology to incorporate into WEST the impacts that niche, nonconventional waste streams might have from rural and urban environments following a nuclear power plant incident or detonation of a radiological dispersal device or improvised nuclear device. (authors)

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DOE OSTI2018

How to Handle the Conflict between Safety and Security - 18564

The purpose of safety and security for nuclear activities are the same. They are both necessary measures to protect people and the environment from radioactive material. There are many measures that enhance both the safety and the security but there are also measures serving one area that are in direct conflict with the other. How information is handled is maybe the best example to demonstrate this conflict between interests. In the security field, information is handled on a need-to-know basis, preventing valuable details to fall into hands of antagonists, terrorists etc. The safety culture, on the contrary, is based on knowledge and transparency and it encourages the sharing of information and experience to improve the safety. There is little guidance on how to manage the conflicts between safety and security for a transport system moving nuclear fuel and radioactive waste and especially when there are conflicts between different legislation areas, for example the Act on Nuclear Activities and Safety of Life at Sea. The Swedish Nuclear Fuel and Waste Management Co, SKB, transports all Swedish spent fuel and operational waste from the Nuclear Power Plants to the central storage facilities in Sweden. To manage the transport system, SKB owns a fleet of packages, road vehicles and an INF 3 ship. For the shipments of nuclear material, the security focus has increased rapidly over the years after the 9/11 attack, followed by regulatory requirements on enhanced security. SKB is currently running a project to further strengthen the transport security, an activity that requires a careful balance between safety and security. This paper describes the methods used and the challenges experienced trying to manage the conflicts between safety and security for the Swedish nuclear transport system. (authors)

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DOE OSTI2019

Guidance on Good Practice for Waste Management in Decommissioning - 19080

The World Nuclear Association (WNA) is an international organization that represents the global nuclear industry. Its mission is to promote a wider understanding of nuclear energy among key international influencers by producing authoritative information, developing common industry positions, and contributing to the energy debate. The Waste Management and Decommissioning Working Group of WNA monitors developments and shapes industry positions in radioactive waste management in nuclear decommissioning. The Working Group promotes accepted international principles and methods, including the sustainable management of natural resources, appropriate re-use and recycling of material, as well as safe and cost-efficient disposal of radioactive waste. In 2015, the WNA decided to identify international good practices in decommissioning and waste management and to appoint a group of international experts to produce a report bringing together this knowledge. The report is aimed at policy- and decision-makers, as well as nuclear professionals looking for guidance or facing decommissioning challenges related to waste management. The scope of the report covers commercial nuclear plants and nuclear research facilities, including legacy plants being decommissioned after normal operation. Although light water and graphite reactor types are mainly considered, the methods described can be applied to other nuclear facilities. The report is due to be published in February 2019. This paper summarizes its findings and recommendations. (authors)

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DOE OSTI2022

Considerations For The Management Of Spent Nuclear Fuel from Advanced Reactors

The intent of this presentation is to give some key considerations for the management of spent nuclear fuel from Advanced Reactors. It will be presented at the Management of Spent Fuel, Radioactive Waste and Decommissioning in SMRs or Advanced Reactor Technologies conference organized by OECD – NEA in Ottawa (Canada) on November 2022 in the session: Operational feedback on managing and disposal of existing waste streams and how some of these concepts can be applied in future endeavours, such as SMRs/Advanced Reactors.

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗
DOE OSTI2016

Characterization of Low Level and Intermediate Nuclear Waste: improvements in calorimetric measurement combined radiological modelling - 16144

Since 40 years, calorimetry allows to determine precisely amounts of nuclear material within a container. Combined with gamma spectrometry, calorimetric measurements give plutonium contents with a low level of uncertainty for each isotope. Calorimetry is used in a lot of nuclear facilities all around the world for plutonium or tritium inventories. It is one of the best solutions to estimate the overall quantity of nuclear material on a wide range of mass, from a few milligrams up to kilograms of radionuclides. In the case of drums containing nuclear waste, characterization was very challenging due to complex matrix, volume and low level activities. The measurement time was a real problem with large volume container and organic matrix with high air content. New designs of SETARAM calorimeters allow to measure nuclear material contents in very large container (up to 385 liters) and/or with a very low detection limit (10 μWatt). These new concepts are based on single measurement cell and vacuum chamber for low level uncertainties. The acquisition system and electronic temperature regulation are highly improved to increase the detection limit, accuracy and precision of the measurement. These modern technological developments within the calorimetry field give the promise of faster measurement times and precise measurements. These devices can be used in waste management of nuclear facilities with a better accuracy and lower uncertainties than others techniques. It is a non-destructive and non-intrusive method. There is no matrix effect which can bias the results. Waste can also be in solid, liquid or gas phase. The new calorimeters are able to give amounts of plutonium, tritium or others alpha or beta emitter radionuclides and allow determining the classification of waste (low level or intermediate). A measurement approach combining very large volume calorimeter, gamma spectrometry and radiological modelling will be presented as an integrated automatic waste characterization system. This system with a calculation step is taking into account the gamma emitters contribution on the total thermal power measured within the calorimeter. The aim of the system is to give a precise quantification of the radionuclides in the waste container with a precise value of the total uncertainties. (authors)

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DOE OSTI2018

Public Views on Nuclear Facility Siting and Radioactive Waste Management in the United States: Methodology and Response Reference Report for the 2017 Energy and Environment Survey

This report presents the questions and responses to a nationwide survey of U.S. residents taken May 2017. The focus of the 2017 survey is public perceptions on (1) nuclear energy and new nuclear technology, such as small modular reactors; (2) the risks and benefits of nuclear energy; (3) different options for managing spent nuclear fuel (SNF); and (4) the role of individuals, organizations and elected officials in locating SNF facilities. Highlights of survey results related to nuclear energy found the U.S. public (1) wants nuclear energy to continue to contribute 20% of total electrical power produced for the next 20 years; (2) is more supportive of adding new reactors at existing sites than at new sites; and (3) is more supportive of small modular reactors than traditional reactors. Highlights related to risks and benefits of nuclear energy include (1) the public believes that terrorist attacks are the greatest threat and that energy independence is the greatest benefit; (2) 56% of the public believes that nuclear power has both high benefit and high risk; (3) the 2011 accident at the Fukushima nuclear facility continues to negatively influence the perceived benefits and risks of nuclear energy except for those who perceive nuclear power as low risk and high benefit; (4) building new reactors is supported by those who perceive nuclear power as low risk and high benefit, and opposed by those who perceive it as high risk and low benefit. Highlights related to SNF management options include (1) support remains higher for permanent disposal than either consolidated interim storage or continued on-site storage; (2) support for private initiatives for interim storage in New Mexico and Texas are higher than generic storage and disposal options; (3) the general public is more likely to increase support if a majority of the local and state residents support an SNF facility. Highlights related to the role of individuals, organizations, and elected officials include (1) 54% of the public agrees that if an SNF facility is deemed safe by regulators, political considerations should not derail the location; (2) 47% of the US public agrees that non-governmental organizations should be able to provide input to locating an SNF facility; (3) 36% of the public believes that the federal government should lead siting of an SNF facility while 25% believes private companies should lead; (4) 81% of the public believes local residents and farmers/ranchers should have a say in the final decision on locating a SNF facility and 56% believe that they should have veto power; and (5) only 27% of the public believes the state governor should have a say and veto power.

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗
DOE OSTI2019

Panel Session 52: US DOE Featured Site Idaho - Managing a Multi-Mission Site (4/5)

This panel focused on discussions related to managing a multi-mission site. The Idaho National Laboratory (INL) Site supports Department of Energy (DOD) Environmental Management (EM), Nuclear Energy (NE), Homeland Security, and the US Navy. Missions cross boundaries in areas such as spent nuclear fuel, waste management, and shared services. The EM mission is split between two separate contracts: the research component with the INL and the execution component with the Idaho Cleanup Project (ICP). Panelists discussed the unique aspects of managing a multi-mission site and their challenges and lessons learned. Presentation proposed: Managing a Multi-Mission Site (Robert Boston, US DOE (USA), Juan Alvarez, Battelle - Idaho National Laboratory (USA), John Zimmerman, US DOE Idaho Operations Office (USA), Frederick Hughes, Fluor Idaho, LLC (USA))

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DOE OSTI2018

3-D Gamma-ray Mapping from Unmanned Aerial Systems for Nuclear Decommissioning - 18439

Advanced gamma-ray detection technologies integrated with sophisticated robotic platforms will enable safer and more cost and time-efficient capabilities in support of nuclear decommissioning, waste management, and environmental remediation activities within the United States Department of Energy (U.S. DOE) complex and in the global nuclear power industry. In the Applied Nuclear Physics program at Lawrence Berkeley National Laboratory, we have developed the Nuclear Scene Data Fusion (SDF) capability to map gamma-ray emitting sources in large-scale, 3-D environments in real-time. This powerful capability has been successfully deployed in real-world environments, from a test-bed in Berkeley, CA to the exclusion zone in Fukushima Prefecture, Japan to support environmental remediation and contamination mapping efforts within evacuated communities, and is also currently being further developed in support of decommissioning efforts at the Fukushima Dai-ichi Nuclear Power Plant (FDNPP) in collaboration with the Japan Atomic Energy Agency (JAEA). In this work, we will provide an overview of SDF adapted for gamma-ray mapping onboard an UAS, as well as results from measurements demonstrating point and distributed source mapping. (authors)

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DOE OSTI2015

Progress of teaching and learning of nuclear engineering courses at College of Engineering, Universiti Tenaga Nasional (UNITEN)

Developing human capital in nuclear with required nuclear background and professional qualifications is necessary to support the implementation of nuclear power projects in the near future. Sufficient educational and training skills are required to ensure that the human resources needed by the nuclear power industry meets its high standard. The Government of Malaysia has made the decision to include nuclear as one of the electricity generation option for the country, post 2020 in order to cater for the increasing energy demands of the country as well as to reduce CO{sub 2} emission. The commitment by the government has been made clearer with the inclusion of the development of first NPP by 2021 in the Economic Transformation Program (ETP) which was launched by the government in October 2010. The In tandem with the government initiative to promote nuclear energy, Center for Nuclear Energy, College of Engineering, Universiti Tenaga Nasional (UNITEN) is taking the responsibility in developing human capital in the area of nuclear power and technology. In the beginning, the College of Engineering has offered the Introduction to Nuclear Technology course as a technical elective course for all undergraduate engineering students. Gradually, other nuclear technical elective courses are offered such as Nuclear Policy, Security and Safeguards, Introduction to Nuclear Engineering, Radiation Detection and Nuclear Instrumentation, Introduction to Reactor Physics, Radiation Safety and Waste Management, and Nuclear Thermal-hydraulics. In addition, another course Advancement in Nuclear Energy is offered as one of the postgraduate elective courses. To enhance the capability of teaching staffs in nuclear areas at UNITEN, several junior lecturers are sent to pursue their postgraduate studies in the Republic of Korea, United States and the United Kingdom, while the others are participating in short courses and workshops in nuclear that are conducted locally and abroad. This paper describes the progress of teaching and learning in nuclear engineering and technology at UNITEN that include curriculum development, students’ enrolment and performance, and teaching staff’s human resource development.

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS↗
DOE OSTI2017

Section 180(c) Policy Implementation Exercise: Multiple Views - 17383

The Department of Energy (DOE) Office of Nuclear Energy's Office of Integrated Waste Management (formerly the Nuclear Fuels Storage and Transportation Planning Project) recently completed a two-year Section 180(c) Proposed Policy Implementation Exercise (the Exercise) with volunteers from eight states and one Native American Tribe. Under Section 180(c) of the Nuclear Waste Policy Act of 1982, as amended (NWPA), DOE is responsible for providing technical and financial assistance to states and Tribes for training of local public safety officials through whose jurisdictions the Secretary of Energy plans to transport spent nuclear fuel (SNF) or high-level radioactive waste to a NWPA-authorized facility. In the 2000's, DOE staff worked closely with state and tribal representatives to develop a revised proposed policy to implement Section 180(c), including grants for assessment and planning activities, as well as grants for training public safety officials. This revised proposed policy was published in a Federal Register Notice in 2008 (2008 FRN) (73 Federal Register 64933, Oct. 31, 2008). The purpose of the Exercise was to evaluate the efficacy of DOE's 2008 revised proposed policy for implementing Section 180(c), and identify outstanding issues to be resolved. DOE presented an interim update on the Exercise at the 2016 Waste Management Symposium and the Exercise concluded in June 2016. This paper describes the remaining activities of the Exercise that occurred since the 2016 Waste Management Symposium, and presents the perspectives of one state and one Tribal participant in the Exercise as well as DOE's perspective. The paper concludes with a discussion of the lessons learned from the Exercise, what steps are next, and how the Exercise may inform and improve future consultations between DOE and state, tribal, and local public safety officials. (authors)

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DOE OSTI2015

Fuel Cycle Technologies 2014 Achievement Report

The Fuel Cycle Technologies (FCT) program supports the Department of Energy’s (DOE’s) mission to: “Enhance U.S. security and economic growth through transformative science, technology innovation, and market solutions to meet our energy, nuclear security, and environmental challenges.” Goal 1 of DOE’s Strategic Plan is to innovate energy technologies that enhance U.S. economic growth and job creation, energy security, and environmental quality. FCT does this by investing in advanced technologies that could transform the nuclear fuel cycle in the decades to come. Goal 2 of DOE’s Strategic Plan is to strengthen national security by strengthening key science, technology, and engineering capabilities. FCT does this by working closely with the National Nuclear Security Administration and the U.S Department of State to develop advanced technologies that support the Nation’s nuclear nonproliferation goals.

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗
DOE OSTI2019

Management and Disposal of U.S. Department of Energy Spent Nuclear Fuel - 19133

Congress created the U.S. Nuclear Waste Technical Review Board (NWTRB) in the 1987 Nuclear Waste Policy Amendments Act (Public Law 100-203) to evaluate the technical and scientific validity of activities undertaken by the Secretary of Energy to implement the Nuclear Waste Policy Act. In accordance with this mandate, the NWTRB reviewed the U.S. Department of Energy's (DOE) efforts to manage the inventory of spent nuclear fuel (SNF) that is under its control (DOE SNF) at several facilities around the country: the Hanford Site in Washington, the Idaho National Laboratory (INL) in Idaho, the Savannah River Site (SRS) in South Carolina, and the Fort St. Vrain independent spent fuel storage installation (ISFSI) in Colorado. While disposal of SNF and high-level radioactive waste (HLW) in a deep geologic repository remains the ultimate objective of the DOE nuclear waste management program, there is significant uncertainty about when such a repository will be constructed in the United States. Until disposal occurs, it is essential to manage DOE SNF in a way that will facilitate its eventual disposal, and it is also important to improve understanding of processes related to packaging and storage of the SNF that could affect its future transportation and disposal. The NWTRB's review, which was a multi-year effort, was documented in a report to Congress and the Secretary of Energy and is summarized here. The NWTRB reviewed the quantities and characteristics of DOE SNF at each of the four sites. It also examined DOE packaging and storage activities and plans at each of the sites. The NWTRB highlighted three main issue areas in its review. First, the review identified issues related to managing the aging of DOE SNF and the facilities used to store the DOE SNF. Second, the review addressed issues related to packaging of stored non-naval DOE SNF into a standard canister. Third, the NWTRB assessed issues that could affect disposal of DOE SNF if DOE continues to evaluate a range of repository settings. Based on the information and findings developed as part of its review, the NWTRB made six recommendations to Congress and the Secretary of Energy related to aging management, packaging, and disposal of DOE SNF. DOE has begun to address some of the NWTRB recommendations. (author)

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DOE OSTI2018

Silver-functionalized silica aerogels and their application in the removal of iodine from aqueous environments

Here, one of the key challenges for radioactive waste management is the efficient capture and immobilization of radioiodine, because of its radiotoxicity, high mobility in the environment, and long half-life (t 1/2 = 1.57 × 10 7 years). Silver-functionalized silica aerogel (AgAero) represents a strong candidate for safe sequestration of radioiodine from various nuclear waste streams and subsurface environments. Batch sorption experiments up to 10 days long were carried out in oxic and anoxic conditions in both deionized water (DIW) and various Hanford Site Waste Treatment Plant (WTP) off-gas condensate simulants containing from 5 to 10 ppm of iodide (I – ) or iodate (IO 3 – ). Also tested was the selectivity of AgAero towards I – in the presence of other halide anions. AgAero exhibited fast and complete removal of I – from DIW, slower but complete removal of I – from WTP off-gas simulants, preferred removal of I – over Br – and Cl – , and it demonstrated ability to remove IO 3 – through reduction to I – .

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DOE OSTI2013

The analysis of metal melting application in the management of metallic radioactive materials arising from decommissioning of nuclear installations

Basic characterization of the waste management process during decommissioning of nuclear installations is described in the presented paper. A brief description is given of conditional and unconditional release of materials into the environment. The paper deals also with metal melting as prospective decontamination technique which can significantly reduce metallic radioactive waste. The material and radioactivity flow in the decommissioning process should be followed using the integrated material flow tool that is implemented into the standardized analytical decommissioning parameters calculation code OMEGA. Applying the integrated material flow tool, it is possible to monitor radiological and physical properties of individual material items listed in the nuclear installation input database, from dismantling up to their release into the environment or disposal in repository. Using the OMEGA code and two model databases, several scenarios related to metal melting are evaluated. The impact of applying different input decommissioning parameters on the metal distribution is the main result discussed in the paper. (authors)

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DOE OSTI2022

System Analysis Modeling and Intermodal Transportation for Commercial Spent Nuclear Fuel

The United States Department of Energy (DOE) has long term goals to develop solutions for managing the nation’s spent nuclear fuel (SNF) and high-level waste (HLW) inventory. The Integrated Waste Management (IWM) program under the DOE office of Nuclear Energy (DOE-NE) is employing system-level engineering and analysis principles to inform potential future waste management system architectures. Managing the spent nuclear waste requires the use of system-level analysis software that takes various aspects of the fuel cycle into account like waste generation, on-site/centralized storage, transportation infrastructure, and long-term disposal. The Next Generation System Analysis Model (NGSAM) is an agent-based model that was developed to simulate the transportation and storage of SNF and HLW. As an agent-based model, NGSAM has the capability to detail the interaction and movement of individual components and groups, such as rail cars and casks. The SNF inventory from commercial nuclear reactors is currently in temporary storage at multiple locations spread across the United States. Shipping of SNF from these locations relies on one of three transportation modes: rail, heavy-haul truck, or barge. Out of the three modes identified, rail is generally the most preferred due to the size of the canisters and casks the SNF would be shipped in. However, under some scenarios, a direct rail route might not be readily available to a reactor site or improving the rail infrastructure at shutdown sites might be too cost-prohibitive for utilities to opt for a direct rail transfer. Under such scenarios, using a barge or heavy haul truck to de-inventory the site and transfer the SNF to a nearby intermodal transfer site with adequate rail infrastructure where the payload could be transferred to a rail car might prove to be an attractive option. This work initially presents the various intermodal transportation options that could be used to transfer SNF from reactor sites to rail cars. This is followed by exploring the operational steps in each of these modes to move the SNF from a reactor site and transfer it to a rail car. This work also presents the procedure of implementing the intermodal transfer methodology in NGSAM using various Java methods. Finally, the process times for accomplishing each of the individual steps are furnished. The implementation ideology, assumptions, and future steps are presented in this work.

Gadey, Harish Reddy↗