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DOE OSTI2017

Deep Borehole Disposal Research in the United States - 17427

The U.S. Department of Energy (DOE) Office of Nuclear Energy (NE) manages a research and development (R and D) program for the disposal of spent nuclear fuel and high-level radioactive waste in the United States. Deep boreholes are being evaluated for disposal of some smaller DOE-managed waste as an alternative to disposal in a mined geologic repository. The deep borehole disposal concept consists of drilling borehole(s) to a total depth of about 5,000 m (16,400 ft - or greater than three miles) into crystalline basement rock, placing waste packages in the lower emplacement zone portion of the borehole, and sealing and plugging the upper portion of the borehole. The required bottom-hole diameter of the borehole(s) depends on the waste package configuration for the reference concept, but ranges from 22 to 43 cm (8.5 to 17 inches). Additional research and development is desired in several important areas for further consideration of deep borehole disposal of radioactive waste. A Deep Borehole Field Test (DBFT) will be conducted by DOE to further assess the viability of deep borehole disposal as an alternative for the disposal of smaller DOE-managed waste forms. The DBFT will be used to evaluate three main areas: 1) evaluation of the capability for drilling and construction of deep, large-diameter boreholes; 2) downhole scientific analyses to assess hydrogeochemical conditions that control waste stability and containment; and 3) engineering activities to assess the viability and safety of waste package emplacement and retrieval in deep boreholes. The DBFT will include first drilling a characterization borehole, followed by an optional field test borehole, to a total depth of about 5,000 m (16,400 feet) into crystalline basement rock in a geologically stable continental location. The initial smaller diameter characterization borehole will be drilled and completed to facilitate downhole scientific testing and analysis. If site conditions are found to be suitable, DOE intends to drill a larger-diameter field test borehole to evaluate emplacement activities using surrogate waste packages. The surrogate waste packages will not contain any radioactive waste, nor will any radioactive waste be used in these tests. One of the advantages of deep borehole disposal is that it would give DOE the flexibility to consider options for disposal of smaller waste forms. Deep borehole disposal also potentially offers earlier disposal of some wastes than might be possible in a mined repository, and could reduce costs associated with projected treatments of some wastes. In order to accomplish the DBFT, DOE will require the support of multiple national laboratories, along with a site contractor to acquire a suitable test site and to manage the site and the required testing activities. DOE issued a competitive solicitation via a request for proposal (RFP) in July, 2015, which requested proposals to provide a test site and site management services. The contract was awarded in January, 2016, to a team led by Battelle Memorial Institute which included a proposed test site in Pierce County, North Dakota. After efforts to acquire both the initial test site in North Dakota and an alternative proposed site in Spink County, South Dakota were unsuccessful, activities were suspended. The experiences in Pierce County, ND and Spink County, SD highlighted the importance of public engagement and support for the DBFT, and that relevant levels of government and other public stakeholders should be involved from the beginning. Using the lessons learned in North and South Dakota, DOE issued a new RFP on August 22, 2016 which emphasized local, state, and tribal (if applicable) government engagement, as well as public and other stakeholder involvement ahead of proposal submittals and throughout the contract execution phases. The new RFP allowed for multiple initial awards and multiple phases of contract execution. In December, 2016, DOE announced the selection of four companies - AECOM, ENERCON, RE/SPEC, and TerranearPMC - to begin exploring the possibility of conducting a DBFT under the terms of the new RFP. Ultimately, only one site will be chosen for the field test. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗
DOE OSTI2017

Radiochemical Methodology Applied To Determination of gamma-Emitting Radionuclides In Waste Samples From IEA-R1 Reactor - 17265

The Brazilian reactor IEA-R1 has been in operation since 1957. It is an open pool-type nuclear research reactor, operating at 2 to 5 MW that uses water as coolant, moderator and biological shield. Polypropylene filter cartridges are part of the water treatment system of the reactor and become radioactive as they remove suspended solid material from the cooling water during the operation of the reactor. Annually, the replacement of the filters from the reactor's water treatment system generates about 36 units. The development of a method for the characterization of the radionuclides present in the filters is required for routine operation in the Radioactive Waste Management Facility (RWMF) in order to determine the radioisotopic inventory of the waste packages. Wastes from nuclear reactors contain transuranic elements, activation and fission products, only few of them emitting gamma radiation measurable by simple gamma scanning methods. The method of the Scaling Factors (SF) uses empirically determined proportions between the concentrations of Difficult to Measure (DTM) radionuclides and that of easily measurable gamma emitters called Key Nuclide (KN), to calculate DTM concentrations. The objective of this study is to describe a method of the dissolution of the filter cartridges for determination of gamma emitting radionuclides. To determine the activity of a sample by means of of gamma spectrometry, it is necessary previous knowledge of the efficiency curve for a given geometry, which can be obtained by calibrating the efficiency and energy of the detector. The need to dissolve the filter cartridges has arisen given the difficulty in obtaining a standard source with the same filter geometry. Therefore, for this work, the calibration curve was constructed using a mixed gamma-ray standard with known activities, same geometry, density, physical state and chemical composition of the source to be analyzed. A sample with background count (BG) was prepared and analyzed under the same conditions as the samples and the result was subtracted from the results obtained for each filter sample. After many tests, it was possible to establish a method for the dissolution of filter cartridges for the determination of gamma-emitting radionuclides. A mixed gamma-ray standard was produced in liquid form, containing the following radionuclides: {sup 241}Am, {sup 137}Cs and {sup 60}Co, which have photo-peaks at the following energies: 59.54, 661.66 and 1332.49 keV, respectively. (authors)

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DOE OSTI2018

Development of a Waste Management Organization for the Whiteshell Laboratories Closure Project - 18317

Whiteshell Laboratories (WL) has been generating and managing radioactive waste for over fifty years in support of a wide variety of research and operational applications. The current mission of the WL site, located in Manitoba, Canada, is to fully decommission the site to an approved end-state criterion and to disposition the waste in compliance with national and provincial regulations. To expedite the decommissioning schedule from over thirty years to nine years, which was a contractual commitment for the site operating company, Canadian Nuclear Laboratories (CNL), it became apparent that a centralized and optimized organization be established to coordinate all waste management activities and to fulfill the mission to process, condition, transport and disposition all radioactive wastes, which include Low-Level Waste (LLW), Intermediate-Level Waste (ILW) and High-Level Waste (HLW). The WL Waste Management Division was effectively established as a two-person operation in 2016 and has rapidly expanded to fulfill the mandate of managing nearly 30,000 cubic meters of LLW, ILW and HLW. This paper outlines the early lessons learned from managing important organizational changes without disrupting ongoing work practices; developing executive-level waste management strategies based on options studies and cost-benefit analysis comparisons; selection of storage vs. disposal disposition strategies; evaluation and selection of transportation methods and packages for LLW, ILW and HLW; and the need to develop an entire suite of programmatic documentation and procedures to support and instill a strong conduct of operations culture. The waste management strategy, which now focuses on transporting the waste to another province (Ontario) in a disposal ready form, represents the first large-scale radioactive waste transportation campaign in Canada that includes all three classes of waste. This paper provides additional insight on the overall waste management strategies for the WL Closure Project. (authors)

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DOE OSTI2021

The legacy of weapons grade plutonium production: Health status of Hanford complex workers who manage the waste

The extent and etiology of health effects in workers who maintain underground storage tanks at the Hanford Nuclear Reservation (Hanford) have been subjects of controversy and concern for several decades. Hanford is a decommissioned nuclear production complex managed by the US Department of Energy in southeast Washington State. This integration-of-evidence review evaluates the relationship between exposure to vapors from mixed chemical and radioactive waste stored in underground storage tanks at Hanford and worker health. Hanford workers’ health information was gathered from technical reports, media reports, and published literature, including the systematic search of seven databases. This review describes the health status and health concerns of Hanford tank farm workers based on the integration of the available health effects data from disparate sources. In interviews with external groups, Hanford workers reported both irritant-type symptoms and diseases that they believe are attributable to tank farm vapors. However, the results of this integration-of-evidence review indicated that no pervasive pattern of occupational disease was identified that can be associated with exposure to tank farm vapors. Inhalation exposure to asbestos and beryllium is associated with lung disease from various types of nuclear industry work but not from work on tank farms. This review concluded that while irritant-type symptoms and isolated cases of occupational disease are plausible under certain conditions, the currently available data do not support a pervasive pattern of occupational disease associated with vapor exposure.

Cherry, Debra↗
DOE OSTI2017

Optimization of Low Level Waste Disposal Policy, Strategies and Techniques - 17201

The mission of low level radioactive waste disposal facilities is to accept and dispose of waste in compliance with all applicable laws, regulations, license requirements, and social expectations. These facilities need to provide a cost effective disposal service to the waste generators, so that the cost savings could be passed down to business, industry, and ultimately, to the general public. To fulfil this mission, waste disposal facilities need to establish and maintain review and optimization mechanisms to respond to changing circumstances that may impact the long-term safe, cost effective operation of their facilities. Maintaining existing disposal resources available as long as possible, managing increased demand for disposal space as a consequence of growing number of nuclear facilities to be decommissioned, and developing capacity for future needs and uncertainties are some of the key challenges that drive optimization of disposal facilities. While the concept of optimization of low level waste disposal facilities is not new, the framework for holistic optimization of waste disposal facilities, enabling them to provide cost effective, sustainable services to the nuclear industry, as well as maintaining optimized safety and radiation protection systems is a notable gap in the current radioactive waste management body of knowledge. A comprehensive optimization framework is required to support the implementation of safe, effective, and sustainable integrated waste management strategies. (authors)

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DOE OSTI2019

Cameco Corporation's Vision in Motion Project - 19128

Cameco Corporation is a world leader in uranium production. Cameco is also a major supplier of uranium processing services required to produce fuel for the generation of clean energy. These operations are based in Blind River, Cobourg and Port Hope, Ontario and are collectively referred to as the Fuel Services Division. The Fuel Services Division produces uranium trioxide from uranium ore concentrate at the Blind River Refinery. Cameco produces uranium hexafluoride and uranium dioxide at the Port Hope Conversion Facility. Cameco operates a fuel manufacturing facility in Port Hope, Ontario and a metal fabrication facility located in Cobourg, Ontario. The company manufactures fuel bundles utilized in the Candu reactors. Cameco is undertaking a major site cleanup and renewal of its Port Hope Conversion Facility (PHCF) which is located in the Municipality of Port Hope (MPH). This undertaking is known as the Vision in Motion (VIM) project. This project is unique and timely opportunity that has been made possible because of the Port Hope Area Initiative (PHAI). The PHAI Port Hope project is being undertaken by Canadian Nuclear Laboratories (CNL) and includes the construction of a long-term waste management facility (LTWMF) in the MPH. VIM entails an extensive remediation and redevelopment of much of the PHCF and includes: - the cleanup and demolition of a number of old or underutilized buildings; - the removal of contaminated soils, building materials and stored wastes; and - modifications to existing buildings at the PHCF with associated landscaping and infrastructure. Overall, the VIM project will allow for environmental remediation, improved site operations, enhancement of site safety and security through site design and improved aesthetics. This paper will discuss the status of this project underway at the Port Hope Conversion Facility. After years of community consultation, planning, and a successful environmental assessment and licensing of the project, the VIM project at the PHCF is now underway. Physical transfer of waste materials began in June 2018. Cameco is committed to seeing the project through to completion and is working with CNL to ensure this happens within the operating time frame of the LTWMF. Cameco keeps the CNSC and MPH well informed of all project related activities. (authors)

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DOE OSTI2019

Pipe Overpack Container Fire Testing: Phase II-B

The Pipe Overpack Container (POC) was developed at Rocky Flats to transport plutonium residues with higher levels of plutonium than standard transuranic (TRU) waste to the Waste Isolation Pilot Plant (WIPP) for disposal. In 1996 Sandia National Laboratories (SNL) conducted a series of tests to determine the degree of protection POCs provided during storage accident events. One of these tests exposed four of the POCs to a 30-minute engulfing pool fire. This test resulted in one of the POCs generating sufficient internal pressure to pop off its drum lid and expose the top of the pipe container (PC) to the fire environment. The initial contents of the POCs were inert materials that would not generate large internal pressure within the PC if heated. However, POCs are now being used to store combustible Transuranic (TRU) waste at Department of Energy (DOE) sites. At the request of DOE's Office of Environmental Management (EM) and National Nuclear Security Administration (NNSA), SNL started conducting a new series of fire tests in 2015 to examine whether PCs with combustibles would reach a temperature that could result in: (1) decomposition of inner contents and (2) subsequent generation of sufficient gas to cause the PC to over-pressurize and release its inner contents. In 2016, Phase II of the tests showed that POCs tested in a pool fire failed within 3 minutes of ignition with the POC lid ejecting. These POC lids were fitted with a NUCFIL-019DS filter and revealed that this specific filter did not relieve sufficient pressure to prevent lid ejection. In the Fall of 2017, Phase II-A was conducted to expose POCs to a 30-minute pool fire with similar configurations to those tested in Phase II, except that the POC lids were fitted with an UltraTech (UT) 9424S filter instead. That specific filter was chosen because of its design to help relieve internal pressure during the fire and thus prevent lid ejection. In Phase II-A, however, setups of two POCs stacked upon one another were never tested, which led to this phase of tests, Phase II-B. This report will describe the various tests conducted in Phase II-B, present results from these tests, and implications for the POCs based on the test results will be discussed.

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗
DOE OSTI2020

Borehole Disposal: Update on the Science, Technology, and Potentially Suitable Radioactive Wastes - 20170

A recent Special Issue of the Energies Journal on Deep Borehole Disposal of Nuclear Waste has delivered a timely update on the science and technology of borehole disposal and the types of radioactive wastes it could potentially accommodate. The Special Issue papers discuss (i) circumstances under which a national waste management programme might wish to consider deep borehole disposal [1], (ii) a status report of deep borehole disposal options in Germany [2], (iii) the use of deep horizontal drill-holes in sedimentary, metamorphic or igneous rocks for disposal of spent nuclear fuel and high-level radioactive waste [3], (iv) the analysis of corrosion performance of engineered barrier systems [4], (v) a review of the potential cementing systems suitable for deep borehole disposal [5], (vi) the thermal evolution around heat-generating waste for a wide range of material properties and disposal configurations [6], (vii) a geochemical analysis of deep brines focussed on fluid-rock interactions [7], (viii) post-closure performance assessment calculations for deep borehole disposal of Cs/Sr capsules [8], and (ix) an example safety case for deep borehole disposal of nuclear wastes [9]. This paper provides an overview of the main findings from these publications and highlights some of the technological and scientific challenges that need to be overcome when developing a deep borehole disposal concept. (authors)

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DOE OSTI2020

Panel Session 13: D and D Collaboration Between US DOE EM and NNSA (R6.3)

This panel focused on the interaction and collaboration between US Department of Energy's Office of Environmental Management (DOE EM) and National Nuclear Security Administration (NNSA) offices and sites. Panelists with presentations: NNSA and DOE EM Collaboration on Facility Disposition (Deborah Couchman-Griswold); DOE EM and NNSA D and D Collaboration at the Y-12 National Security Complex (Diane McDaniel); Working Together to Achieve Environmental Cleanup Success in Oak Ridge (Laura Wilkerson, James Daffron); DOE-EM - NNSA (Rick Demmer)

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DOE OSTI2019

Future Transition of WIPP from EM to Another DOE Office - 19256

The U. S. Department of Energy (DOE) Carlsbad Field Office (CBFO) has a primary mission to assist federal government entities disposition transuranic (TRU) radioactive waste. The main resource for disposition is the deep geologic repository known as the Waste Isolation Pilot Plant (WIPP). Other resources include a complete transportation system and a program that assists in the certification and shipment of TRU waste to WIPP known as the National TRU Program (NTP). All of these resources are managed by CBFO, which currently is part of the DOE Environmental Management (EM) program. EM's primary mission for DOE is to clean up the legacy remaining from many years of nuclear weapons research and production. But, CBFO estimates the need for WIPP and NTP will continue beyond the mission of EM and will assist other entities such as the National Nuclear Security Administration (NNSA), the Office of Science (OS) and the Navy. As the inventory of legacy TRU waste is reduced, the inventory of new TRU waste will continue from ongoing missions. So, over the life span of WIPP the primary customers of CBFO will shift from legacy EM sites to newly-generated TRU waste sites. And, somewhere along the way CBFO estimates that it will transition, primarily from an EM support (legacy waste) entity to a primarily a NNSA support (newly-generated waste) entity to facilitate ongoing DOE missions. This paper will address the need for that change at a programmatic level and will include some ideas for conceptual planning for such a transition. (author)

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DOE OSTI2018

Decontamination and Decommissioning Activities of a Radiopharmaceuticals Production Facility - 18067

On May 2012, Best Medical Belgium S.A. (BMB), a manufacturer of pharmaceutical products located on the nuclear site of Fleurus, was declared bankrupt. According to the Belgian law, ONDRAF/NIRAS (Belgian Radioactive Waste Management Agency) was entrusted with the clean-up and decommissioning operations of the former BMB facilities, nowadays known as 'ONDRAF Site Fleurus' (ONSF). In June 2015, ONSF launched a Decontamination and Decommissioning (D and D) program, for which Tractebel: - Supports the definition of the clean-up and decommissioning strategies; - Drafts the Final Decommissioning Plan (FDP) and Safety Analysis Report (SAR) that will be submitted to FANC/AFCN (Belgian Federal Agency for Nuclear Control) in order to get the License for decommissioning; - Drafts the technical specifications of the public tendering process related to the D and D program; - Ensures the day to-day follow-up of the D and D activities on site. Four nuclear buildings are part of the D and D activities. One of them, building 14 (B14), represents the most challenging and extensive task with the clean-up of highly contaminated areas and its further decommissioning up to the final state. This building features two cyclotrons (CGR and IBA cyclotrons) successively used to produce radioisotopes, as well as hot cells and glove boxes used for their purification and the conditioning of the final pharmaceutical product. The present paper aims at presenting the most recent development steps of the clean-up phase regarding the adaptations of existing facilities and the upcoming activities in preparation of the decommissioning activities. To allow the sorting and the treatment of the radioactive material identified in the physical and radiological inventory, several workshops have been implemented within the B14 building in order to deal with radioactive materials arising from the clean-up and D and D activities. Following the conceptual design phase, Tractebel has actively monitored the on-site activities for the construction of those workshops such as: - The modification of the civil works; - The revamping of the ventilation system; - The installation of dedicated lifting equipment and workstations equipped with cutting devices; - The assembly of a docking station for filling the radioactive packages. The removal of the activated concrete surrounding the IBA cyclotron requires the erection of a containment structure and an extension structure. The containment structure, composed of light metallic beams, is located above the cyclotron and its irradiation zones. For operational security reasons and working efficiency, the cutting process of the concrete ceilings and walls will be performed from the top inside the containment structure by means of an eight tons overhead bridge crane. Concrete blocks resulting from the cutting process will then be lifted, without any loss of containment, towards the extension zone of the nuclear zone of the IBA cyclotron for further resizing, sorting and evacuation towards the identified waste routes. To prepare this task which will be performed during the decommissioning phase, Tractebel sets up the necessary technical specifications. (authors)

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

Waste is our Product. Developing, Implementing and Optimising Waste Management at Dounreay - 19039

The UK's Fast Breeder Reactor Research programme was centred at Dounreay, in the very north of Scotland, from 1955. Since 1994, the site has been focused on decommissioning, and represents one of the most complex, technically challenging and hazardous nuclear clean-up projects in Europe. Since 2012, Dounreay Site Restoration Ltd (DSRL) has been contracted by the NDA as the Site License Company to deliver the defined scope of work, under a Target Cost contract, to decommission the site to achieve the Interim End State by 2030-2033, whilst managing the transition of its people. All parties, including DSRL's Parent Body Organisation Cavendish Dounreay Partnership Ltd (a consortium of Cavendish Nuclear, AECOM, and Jacobs), recognise that there are significant technical and regulatory challenges to achieve this, as well as safely managing the transition for our workforce on what is effectively a 'closure' contract. The product of decommissioning is waste; over the course of the programme, a full range of higher activity and lower level radioactive wastes will be generated, and must be safely managed. This paper will address: - The Policy issues relating to radioactive waste management at Dounreay, including particular issues relating to implementation of Scottish policy, including how Waste Management is Optimised. - An overview of the decommissioning programme and the delivery of an Interim End State; - The type, range and nature of radioactive wastes requiring safe management at Dounreay; - Higher Activity Wastes (HAW): - Setting higher activity waste strategy; defining products and interim storage requirements; - Technical, regulatory and stakeholder issues for HAW strategy; - Lower Activity Wastes: - Setting Low Level Waste (LLW) strategy; defining a disposal product and development and status for Dounreay's LLW Disposal Vaults; - Implementing LLW strategy; - Technical, regulatory and stakeholder issues for LLW strategy; - Optimising Waste Management -Optimising waste from generation (from decommissioning workfaces) through to disposal -why, and how; - The Waste Informed Decommissioning model as a methodology and approach; - Impact and importance of Waste Management on a target cost contract; - Establishment of a Waste Optimisation Programme to drive ownership, delivery and culture change; - Management responsibilities and informing organisational design; - Sharing and learning from Best Practice; - The Challenge - how to ensure workforce and teams are engaged in delivering optimisation requirements; - Conclusions. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗
DOE OSTI2017

Sub-drain Water Treatment Facility for Reduction of Accumulated Waste Water Amount at the Fukushima NPS Site - 17572

At the Fukushima Daiichi Nuclear Power Station site, water treatment facility special for sub-drain and groundwater drain has been constructed by Tokyo Electric Power Company Holdings, Inc. and Hitachi-GE Nuclear Energy, Ltd., and it has been operated to remove radionuclides from the pumped groundwater. The facility consists of three kinds of equipment for collecting, purifying and transferring. The purification equipment removes radionuclides contained in the pumped groundwater. The purification equipment consists of filters for removal of solids and colloidal particles, and adsorbents for removal of ionic radionuclides. Five adsorption vessels are installed into the equipment; three vessels have adsorbent to remove Cs and Sr simultaneously, the fourth vessel has adsorbent to remove Sb and for the last has adsorbent to remove heavy metals. The vessels for Cs and Sr are operating as a so-called 'merry-go-round'. For the rational operation of the equipment, a simulation code has been developed to calculate the Sr concentration of outlet water which determines the replacement timings of the Cs-Sr adsorption vessels. The simulation code has been applied to planning of vessel replacement during the water treatment facility operation. The facility started operation in September 2015, and treated the pumped groundwater since then. As of October 2016, about 211,000 m{sup 3} of groundwater had been treated. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗
DOE OSTI2017

Improving Decommissioning Success using the Tool of Virtual Reality; Increasing Worker Safety and Project Schedule Stability - 17193

operations, especially underwater, is essential. Equally essential is a precise game plan for disassembly which focuses attention on the skilled remote handling operators who must produce the results. Project success is based on clean, efficient cuts and take-aways, prepared paths for waste placement and containment, programmed return paths; and practice, practice, practice on the part of the operators. Recently, our Partner, WAK Ruackbau- und Entsorgungs- GmbH (Decommissioning and Waste Management Company) was tasked with dismantling and decommissioning the Karlsruhe Reprocessing Plant. The most difficult task in this project is the dismantling of the vitrification plant. Waelischmiller was selected to address this high-consequence project. Together, WAK and Waelischmiller determined that development of a virtual reality suite, where management and operators could create a virtual vitrification layout and subsequently map and rehearse their dismantling plan was essential. This approach, using Virtual Reality (VR) as a tool in streamlining operations and rehearsing difficult moves and cuts, will be a game changer for this and future projects. It will be a first-of-a-kind in Germany. The VR suite is contained in a room at the Karlsruhe facility with a large screen, control cabinet, simulation computer, a Waelischmiller Joyarm and Masterarm. To support the dismantling of the vitrification plant, WAK/HWM will conduct interactive feasibility studies for each dismantling step. All movements; cuts, take-aways and vessel segment insertion into transportation and disposal casks will be established, programed and practiced within virtual test suite. This allows savings in cost-intensive and complex construction of test rigs. Operating personnel can be trained in the VR suite, without taking the risk of damaging expensive remote handling equipment.While the operators are working on the operating element, they stand in front of a wide screen. Instead of a real TELBOT{sup R}, a virtual TELBOT{sup R} is moving on the screen in virtual reality. While practicing, the operators cannot damage the arm and the equipment, which is a big advantage. Moreover an interactive feasibility study can be realized without building a real test rig (mock-up). Consequently significant cost-expenses can be reduced. This paper will describe the virtual suite used by the WAK in Karlsruhe and the advantages of this new and innovative approach, which is unique in decommissioning of nuclear facilities. The viewpoint of each (WAK and HWM), and the decisions and benefits realized along the project path will be detailed in the paper. (authors)

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DOE OSTI2017

Characterization of accumulated nuclear fuel in South Korea with scenario

In this work, the AMORES Program which automatically prepares ORIGEN-S inputs, executes ORIGEN-S, and edits ORIGEN-S outputs based on the spent nuclear fuel (SNF) data and scenario on the nuclear power plant construction was introduced and applied to analyze the inventories, heat generations, radioactivities, and radio-toxicities of the SNFs generated in South Korea with realistic SNF data up to 2015 and three scenarios on the future NPP construction and operation from 2016 to 2035 or 2053. The scenario study for PWR shows that the scenario considering the most cancellations of the future NPPs shows 12.7%, 24.1%, 25.3%, and 15.7% reductions of the spent nuclear fuel inventories, radioactivities, thermal heat generations, and the radio toxicities, respectively at 2035, in comparison with the most optimistic scenario of NPPs construction. Also, the nuclide-wise decomposition was performed to show the nuclide-wise contributions to the total heat generation and radioactivity of the accumulated SNFs, which showed that the heat generation, radioactivity, and radio-toxicity of CANDU SNFs have significantly lower values due to the lower discharge burnup and no operation of CANDUs after 2027 than the PWR SNFs. (authors)

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DOE OSTI2020

2019 LDRD Annual Report

The Laboratory Directed Research and Development (LDRD) Program Annual Report for Savannah River National Laboratory for FY2019 focuses on the following project areas: legacy waste cleanup, nuclear materials threat reduction; nuclear deterrent, and secure energy & manufacturing.

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗
DOE OSTI2017

Development of a Small Liquid Sodium Purification Loop

Generation IV nuclear reactors provide management solutions to address spent fuel problems. The most researched Generation IV reactor is the sodium cooled fast reactor (SFR). Improved engineering is has allowed for systematic improvements in both the safety and efficiency of power production. However, before a SFR can be brought back online in the Untied States, constructive research must be pursued on numerous scales to ensure the capabilities of aforementioned reactors. While larger research facilities such as the one at Argonne National Laboratory or the University of Wisconsin - Madison address some of the larger scale studies surrounding the SFR, Fort Lewis College (FLC) is aiming to provide small scale studies on liquid sodium as a thermal hydraulic cooling system. The sodium diagnostic loop at FLC is constructed to conduct research that includes: analyzing pumping characteristics, thermal stratification, freeze plug analysis, and corrosion studies. The FLC loop is attached to an inert glovebox so these experiments can be conducted with an additional layer of safety. The objective of this sodium research apparatus is to combine the best features of each instrument commonly associated with sodium research loops in a cost effective manner while still obtaining high fidelity data. Furthermore, an innovative design of the loop maximizes the volume of available research space inside of the glovebox by mounting the diagnostic loop adjacent to the glovebox.

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗
DOE OSTI2016

Advanced Nuclear Fuels and Materials Development and Philosophy of the DOE Advanced Fuels Campaign

The mission of the Advanced Fuels Campaign (AFC) is to perform Research, Development, and Demonstration (RD and D) activities for advanced fuel forms (including cladding) to enhance the performance and safety of the nation's current and future reactors; enhance proliferation resistance of nuclear fuel; effectively utilize nuclear energy resources; and address longer-term waste management challenges. This includes development of a state-of-the art Research and Development (R and D) infrastructure to support the use of a 'goal-oriented science-based approach.' AFC uses this approach to develop a fundamental understanding of fuel and cladding fabrication methods and performance under irradiation, enabling the pursuit of multiple fuel forms for future fuel cycle options. This approach includes fundamental experiments, theory, and advanced modeling and simulation. One of the most challenging aspects of AFC is the management, integration, and coordination of major R and D activities across multiple organizations. AFC interfaces and collaborates with other Fuel Cycle Technologies (FCT) campaigns, universities, industry, various DOE programs and laboratories, federal agencies (e.g., Nuclear Regulatory Commission [NRC]), and international organizations. Key challenges are the development of fuel technologies to enable major increases in fuel performance (safety, reliability, power and burnup) beyond current technologies, and development of characterization methods and predictive fuel performance models to enable more efficient development and licensing of advanced fuels. AFC is challenged with the research and development of fuels for two different reactor technology platforms, namely transmutation fuel for non-water cooled reactors and advanced fuel development for light water reactor (LWR) systems. This presentation will provide an overview of the Advanced Fuel Campaign activities including the near term activities in advanced nuclear fuel system research and development as well as highlighting general activities pursued to improve the study, modeling, and simulation of irradiated nuclear materials. (authors)

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗