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The united kingdom's changing requirements for spent fuel storage

The UK is adopting an open fuel cycle, and is necessarily moving to a regime of long term storage of spent fuel, followed by geological disposal once a geological disposal facility (GDF) is available. The earliest GDF receipt date for legacy spent fuel is assumed to be 2075. The UK is set to embark on a programme of new nuclear build to maintain a nuclear energy contribution of 16 GW. Additionally, the UK are considering a significant expansion of nuclear energy in order to meet carbon reduction targets and it is plausible to foresee a scenario where up to 75 GW from nuclear power production could be deployed in the UK by the mid 21. century. Such an expansion, could lead to spent fuel storage and its disposal being a dominant issue for the UK Government, the utilities and the public. If the UK were to transition a closed fuel cycle, then spent fuel storage should become less onerous depending on the timescales. The UK has demonstrated a preference for wet storage of spent fuel on an interim basis. The UK has adopted an approach of centralised storage, but a 16 GW new build programme and any significant expansion of this may push the UK towards distributed spent fuel storage at a number of reactors station sites across the UK.

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Technical basis for extending storage of the UK's advanced gas-cooled reactor fuel

The UK Nuclear Decommissioning Agency has recently declared a date for cessation of reprocessing of oxide fuel from the UK's Advanced Gas-cooled Reactors (AGRs). This will fundamentally change the management of AGR fuel: from short term storage followed by reprocessing to long term fuel storage followed, in all likelihood, by geological disposal. In terms of infrastructure, the UK has an existing, modern wet storage asset that can be adapted for centralised long term storage of dismantled AGR fuel under the required pond water chemistry. No AGR dry stores exist, although small quantities of fuel have been stored dry as part of experimental programmes in the past. These experimental programmes have shown concerns about corrosion rates.

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Implementing Geological Disposal of Radioactive Waste Technology Platform From the Strategic Research Agenda to its Deployment - 12015

Several European waste management organizations (WMOs) have initiated a technology platform for accelerating the implementation of deep geological disposal of radioactive waste in Europe. The most advanced waste management programmes in Europe (i.e. Finland, Sweden, and France) have already started or are prepared to start the licensing process of deep geological disposal facilities within the next decade. A technology platform called Implementing Geological Disposal of Radioactive Waste Technology Platform (IGD-TP) was launched in November 2009. A shared vision report for the platform was published stating that: 'Our vision is that by 2025, the first geological disposal facilities for spent fuel, high-level waste, and other long-lived radioactive waste will be operating safely in Europe'. In 2011, the IGD-TP had eleven WMO members and about 70 participants from academia, research, and the industry committed to its vision. The IGD-TP has started to become a tool for reducing overlapping work, to produce savings in total costs of research and implementation and to make better use of existing competence and research infrastructures. The main contributor to this is the deployment of the IGD-TP's newly published Strategic Research Agenda (SRA). The work undertaken for the SRA defined the pending research, development and demonstration (RD and D) issues and needs. The SRA document describing the identified issues that could be worked on collaboratively was published in July 2011. It is available on the project's public web site (www.igdtp.eu). The SRA was organized around 7 Key Topics covering the Safety Case, Waste forms and their behaviour, Technical feasibility and long-term performance of repository components, Development strategy of the repository, Safety of construction and operations, Monitoring, and Governance and stakeholder involvement. Individual Topics were prioritized within the Key Topics. Cross-cutting activities like Education and Training or Knowledge Management as well as activities remaining specific for the WMOs were as well identified in the document. For example, each WMO has to develop their own waste acceptance rules, and plan for the economics and the funding of their waste management programmes. The challenge at hand for the IGD-TP is to deploy the SRA. This is carried out by agreeing on a Deployment Plan (DP) that guides organizing the concrete joint activities between the WMOs and the other participants of the IGD-TP. The first DP points out the coordinated RD and D projects and other activities that need to be launched to produce these results over the next four to five years (by the end of 2016). The DP also describes general principles for how the joint work can be organised and funded. (authors)

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The French Geological Repository Project Cigeo - 12023

The French Agency for Radioactive Waste Management, ANDRA, was launched by law in 1991 to perform and develop the research programme for managing high level and intermediate level long-lived radioactive waste generated by the French nuclear fleet. After a 15-year intensive research programme, including the study of alternative solutions, an overall review and assessment of the results was organized, including a national public debate. As a result, the Parliament passed a Planning Act on radioactive waste management in 2006. Commissioning of a geological repository by 2025 was one of the most important decisions taken at that time. To reach this goal, a license application must be submitted and reviewed by the competent authorities by 2015. A detailed review and consultation process is, as well, defined in the Planning Act. Beside the legal framework the project needs to progress on two fronts. The first one is on siting. A significant milestone was reached in 2009 with the definition of a defined area to locate the underground repository facilities. This area was approved in March 2010 by the Government, after having collected the opinions and positions of all the interested parties, at both National and local levels. A new phase of dialogue with local players began to refine the implementation scenarios of surface facilities. The final site selection will be approved after a public debate planned for 2013. The second one is the industrial organization, planning and costing. The industrial project of this geological repository was called Cigeo (Centre Industriel de Stockage Geologique). Given the amount of work to be done to comply with the given time framework, a detailed organization with well-defined milestones must be set-up. Cigeo will be a specific nuclear facility, built and operated underground for over a hundred years. The consequence of this long duration is that the development of the repository facilities will take place in successive operational phases. The characteristics of the first waste packages received will determine the work and the corresponding investments by 2025 on the repository site. One of the main challenges will be to accommodate both activities of mining and nuclear operations at the same time and at the same location. From the technical standpoint, ventilation and fire risk cannot be managed through a simple transposition from current nuclear industry practices. The reversibility demand also leads to concrete proposals with regard to repository management flexibility and waste package retrievability. These proposals contribute to the dialogue with stakeholders to prepare for the public debate and a future law which will determine the reversibility conditions. New design developments are expected to be introduced in the application from the current studies conducted until 2014. The possibility of optimization beyond 2015 will be kept open taking into account the one hundred years operating time as well as the capability to integrate feedback gained from the first construction and operation works. The industrial committed work aims to reach the application stage by 2015. The license application procedure was defined by the 2006 Act. Subject to authorization, the construction might begin in 2017. (authors)

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An Overview of IAEA Activities to Support Pre-disposal Management of Radioactive Wastes in Member States - 12334

The International Atomic Energy Agency (IAEA) promotes safe and effective management of radioactive waste and has suitable programmes in place to serve the needs of Member States in this area. These programmes cover the development and use of safety standards, planning, technologies and approaches needed for the management of different types of radioactive waste, resulting both from the nuclear fuel cycle and nuclear applications. In the pre-disposal area, the assistance to Members States covers a wide range of topics, including policy and strategy, inventory assessment, technologies and approaches for waste minimization, selection of technical options for waste processing and storage, improvement in operating practices at nuclear facilities, optimization of waste management capacity, etc. and is delivered through the publication of technical guidance documents, coordinated research projects, networks, technical cooperation projects and organization of training and technical review services. This report presents an overview of recent IAEA accomplishments aiming to support activities in pre-disposal management of radioactive waste with focus on technological aspects. (authors)

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Sellafield's Role in the Socio-Economic Development of West Cumbria - 12459

It would be hard to imagine what West Cumbria, a remote area in the North West of England, would look like without the huge Sellafield nuclear complex. The site is owned by the Nuclear Decommissioning Authority (NDA) and managed by Nuclear Management Partners (NMP), an international private partnership consisting of URS from the United States of America, AMEC from the UK and AREVA from France. Today some 10,000 people work at Sellafield with many more employed through the site's supply chain, a large percentage of which is located directly in West Cumbria. The Government, through the NDA, has committed around pounds 1.5 billion a year for the next three years as we at NMP bring our vast global expertise and experience to deliver substantial improvements to the clean-up mission there. Of this total budget, more than Pounds 800 million a year is spent in that supply chain and around 30 percent of that goes directly to firms in West Cumbria. But the dependency on the nuclear industry is immense and, with the site now entering an extensive decommissioning programme, the threats to jobs, and therefore the local economy, is severe. While Sellafield provides wealth, there are areas of deep deprivation and worklessness. Consequently, Sellafield Ltd, NMP and NDA have partnered with the local community leaders and politicians to form Britain's Energy Coast, a strategic regeneration body driving economic improvements and projects to deliver a vibrant economy for West Cumbria, long into the future. While the threats to our economy are real, the opportunities are potentially transformational. The UK is on the brink of a nuclear renaissance and, if we are successful through the Energy Coast programme, West Cumbria will become the hub, not only of the nuclear industry, but also of green energy production in the UK, with obvious benefits to our local economy. But to achieve this, Sellafield and its new owners are having to change the opportunistic ways of the past to provide a new strategic mode of socio-economic contribution to deliver a sustainable future for the local community. The results so far have been impressive, with over pounds 56 m being committed to socio-economic projects, but the long term aim is to achieve pounds 116 m investment through public/ private partnership. Sellafield is fundamental to this goal. (authors)

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The Windscale Advanced Gas Cooled Reactor (WAGR) Decommissioning Project A Close Out Report for WAGR Decommissioning Campaigns 1 to 10 - 12474

The reactor core of the Windscale Advanced Gas-Cooled Reactor (WAGR) has been dismantled as part of an ongoing decommissioning project. The WAGR operated until 1981 as a development reactor for the British Commercial Advanced Gas cooled Reactor (CAGR) power programme. Decommissioning began in 1982 with the removal of fuel from the reactor core which was completed in 1983. Subsequently, a significant amount of engineering work was carried out, including removal of equipment external to the reactor and initial manual dismantling operations at the top of the reactor, in preparation for the removal of the reactor core itself. Modification of the facility structure and construction of the waste packaging plant served to provide a waste route for the reactor components. The reactor core was dismantled on a 'top-down' basis in a series of 'campaigns' related to discrete reactor components. This report describes the facility, the modifications undertaken to facilitate its decommissioning and the strategies employed to recognise the successful decommissioning of the reactor. Early decommissioning tasks at the top of the reactor were undertaken manually but the main of the decommissioning tasks were carried remotely, with deployment systems comprising of little more than crane like devices, intelligently interfaced into the existing structure. The tooling deployed from the 3 tonne capacity (3te) hoist consisted either purely mechanical devices or those being electrically controlled from a 'push-button' panel positioned at the operator control stations, there was no degree of autonomy in the 3te hoist or any of the tools deployed from it. Whilst the ATC was able to provide some tele-robotic capabilities these were very limited and required a good degree of driver input which due to the operating philosophy at WAGR was not utilised. The WAGR box proved a successful waste package, adaptable through the use of waste box furniture specific to the waste-forms generated throughout the various decommissioning campaigns. The use of low force compaction for insulation and soft wastes provided a simple, robust and cost effective solution as did the direct encapsulation of LLW steel components in the later stages of reactor decommissioning. Progress through early campaigns was good, often bettering the baseline schedule, especially when undertaking the repetitive tasks seen during Neutron Shield and Graphite Core decommissioning, once the operators had become experienced with the equipment, though delays became more pronounced, mainly as a result of increased failures due to the age and maintainability of the RDM and associated equipment. Extensive delays came about as a result of the unsupported insulation falling away from the pressure vessel during removal and the inability of the ventilation system to manage the sub micron particulate generated during IPOPI cutting operations, though the in house development of revised and new methodologies ultimately led to the successful completion of PV and I removal. In a programme spanning over 12 years, the decommissioning of the reactor pressure vessel and core led to the production 110 ILW and 75 LLW WAGR boxes, with 20 LLW ISO freight containers of primary reactor wastes, resulting in an overall packaged volume of approximately 2500 cubic metres containing the estimated 460 cubic metres of the reactor structure. (authors)

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Development of an Integrated System for the Long-term Preservation of Records, Knowledge and Memory relating to Radioactive Waste Disposal Facilities - 17099

The Nuclear Energy Agency (NEA) has co-ordinated an international initiative to develop a common approach to the preservation of records, knowledge and long-term memory (RK and M), focused on radioactive waste disposals. The work programme has run in two phases, starting in 2011, with the current phase of the project due to be completed in 2018. Preparations for final reporting are now underway. The detailed implementation of an approach to RK and M preservation for any disposal facility will always remain a national decision. However, the NEA project has produced a 'menu' of tools and techniques that can be accessed and adapted to suit national needs. The common source of these menu components will help to ensure that the memory of the repository is kept alive, that messages to future populations can be clearly understood, and that evidence derived from the disposal environment can be properly interpreted. This paper describes the vision for implementation of the RK and M initiative within national programmes. Practical testing of some components of the menu of tools and techniques is currently underway in France, Sweden and USA, with encouraging results. Other disposal facilities, both under development or in planning, are invited to 'road test' the products and provide feedback. Refinement and maintenance of the tools remains important, and the NEA is committed to ensuring the continued accessibility and availability of the project outputs into the future. (authors)

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'A Good Decision Is Based On Information, Not On Numbers' - A Process For National Strategic Decision Making - 17203

Waste management decision making is the process used by waste owners to determine and justify choices in across the lifecycle of a waste (from the manner of generation or retrieval to final disposition). In the UK, waste owners in the nuclear industry are obligated, by their environmental permits and authorisations, to demonstrate the application of robust and well-underpinned decision making processes for waste management. This is captured through the requirement for waste owners to demonstrate the identification and implementation of Best Available Technique (BAT). The National Waste Programme (NWP), led by LLW Repository Ltd, is a UK wide programme which leads the implementation of the UK National Strategy for the management of solid LLW from the nuclear industry [1] and which aims to deliver a self-sustaining culture for optimised management of Low Level Waste (LLW) in the UK. Recognising the requirement on waste owners, the NWP has - in conjunction with appointed contractors - led the development and publication of national strategic optioneering studies (so-called national strategic BAT studies) to support waste owners. Recognising the benefits that this approach to optioneering and strategic decision making could have for other waste producers, this paper provides an overview of the process used for the development of the suite of national strategic BAT assessments for the NWP. It details: the main phases of the process, the key features of each process phase, the benefits of the approach and key learning from its deployment in practice. Note: The legislative regime in England and Wales requires the identification and application of BAT. There is an equivalent regime in Scotland known as Best Practicable Environmental Option (BPEO) and Best Practicable Means (BPM). The requirements are comparable across the two legislative regimes and, for the purposes of simplicity, the term BAT will be utilised in this paper. The approach and outcomes of the national strategic optioneering process described are applicable across the UK. (authors)

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Dounreay Site's Interim End State-Environmental Safety Strategy - 17509

The Dounreay nuclear licensed site, located in Caithness on the north coast of Scotland, was the United Kingdom's (UK) site for Fast Reactor research and development. The Dounreay facilities are now being decommissioned and the site restored in accordance with UK Government policy to manage civil nuclear liabilities. This site closure and environmental restoration programme is to achieve levels of residual radiological and chemical contamination sufficiently low that the site will be safe for future use. This document sets out the Environmental Safety Strategy for the site remediation and closure programme, which will follow completion of facility decommissioning and demolition. The document summarises the contractual definition of the Dounreay site end states and also the associated regulatory regimes. An overview of the approach and processes for achieving the Interim End State (IES) are provided, along with consideration of how Dounreay will demonstrate that the IES has been achieved. (authors)

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Strategic considerations for developing future underground research facilities - 15114

The suite of existing underground research facilities (URFs) and their various operational histories and contexts provides useful insights to consider when deciding a particular URF location and approach (generic or site-specific) for new disposal facility research programmes. Even the smallest URF represents a large capital investment and a significant ongoing operational mortgage when recognizing the typically decades-long site characterization and data collection thought necessary to support a defensible safety case or safety assessment. Thus making such investments should be approached with an understanding of the short- and long-term implications for such factors as cost, location, data quality, public acceptance, operational risk, opportunity for design optimization, etc. and with an understanding of the potential risk management issues to help ensure the URF programme achieves the intended objectives. (authors)

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German research and development for high level waste in light of the new site selection process - 15516

The German government decided 50 years ago, that radioactive waste is to be disposed of in Deep Geologic Repositories, preferably in a salt rock formation. Soon after, in 1967, research in the Asse salt mine was initiated. Since then substantial progress has been achieved in the development of the radioactive waste disposal programme in Germany. For a geologic repository for High Level Waste in salt a reference concept has been developed, which represented the radioactive waste management processes from transport of High Level Waste and Spent Nuclear Fuel to an interim storage site, waste conditioning and repackaging for disposal, to emplacement of the waste packages. The feasibility of the reference concept has been proven by demonstration tests for all relevant equipment: a pilot conditioning plant has been built as well as the main equipment for the entire transport chain including the shaft transport and emplacement technologies for heavy loads fulfilling strict requirements for nuclear and mining safety. Also the backfilling technology has been optimised for the purposes of a repository for radioactive waste. Finally, tests have been performed to verify thermo-mechanical models for the host rock. The demonstration tests have been performed to an extent which even would allow immediate licensing of the repository and the employed equipment. The Research and Development work was completed by further optimisation of the reference concept. Construction and operation of deep geologic repositories for low and intermediate level radioactive wastes in Germany benefited from the above mentioned but also stimulated the knowledge and experience build-up for the repositories for High Level Waste. Despite the well progressed work for a deep geologic repository in salt R and D work in Germany for already a long time also considered other host rock formations. While work for crystalline rock mainly consisted of relatively small contributions to international research projects due to the limited occurrence of suitable sites in Germany, projects and developments for repositories in clay formations have had an increasing contribution to the overall Research and Development work for radioactive waste repositories in Germany. In July 2013 a new site selection act was put into force, which set the initiating conditions for the German programme on radioactive waste management. Principally, a process was initiated to search for a site for a deep geologic repository for High Level Waste independent from earlier decisions. This means that a site shall be determined without predetermination by earlier decisions. Nevertheless, to enable a sound decision for a site selection it is necessary to be able draw back on the knowledge and experience from earlier activities. Otherwise, tedious learning processes would have to be experienced again. Since efforts to open up a site selection process again grew since the late 1990's projects had been implemented timely to capture existing knowledge. The paper at hand describes the achievements of R and D activities in Germany, the change of radioactive waste management policy and the endeavours to maintain the achievements. (authors)

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Life Cycle Costing in Radioactive Waste Packaging: Reducing Costs Whilst Accelerating Clean-Up - 16131

In recognition of the high up-front costs and potentially long timescales to implement the more traditional methods of encapsulating wastes, in the UK alternative approaches to help accelerate hazard reduction and reduce such costs are being deployed. When considering such the cost of alternative approaches to waste packaging strategies, it is important that the complete waste life cycle is taken into account. This paper will demonstrate that when evaluating waste packaging options, whilst individual elements (e.g. container costs) within an overall waste management programme may appear to offer a cost benefit by comparison with alternatives, the programme as a whole may not necessarily be the most cost effective solution when life cycle costs are taken into account, or when other technical issues are considered. To illustrate this point this paper will present a view of the application of LCC, utilising a number of waste packaging scenarios, to promote discussion and consideration of the benefits of undertaking a holistic assessment of the investment decision as part of an overall waste management strategy. (authors)

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Progress of the Czech Republic Deep Geological Repository Program - 16255

The Czech Republic operates two NPPs with 6 pressurized water reactors. Czech state is fully responsible for the disposal of all radioactive waste including spent nuclear fuel and it provides the Radioactive Waste Repository Authority (SURAO) established in 1997. According to the RWM Policy a deep geological repository (DGR) considered to be the only feasible option for the final disposal of spent fuel. The State Policy set out important milestones for DGR development - the selection of candidate sites by 2020 and the selection of a final site by 2025. The final commissioning of a DGR is planned for 2065. The initial stages of DGR development involved the screening of geological conditions of the whole territory. Granites would provide the most suitable rock environment for DGR siting purposes. By the end of 2012 SURAO will have proposed 7 sites for the potential geological surveys and the first stage of site characterization work. Licenses for geological survey for this stage are in the force since October 2015. Main goal of RD and D programme is to support the siting programme for the selection of the candidate sites, to adapt a DGR design on suitable sites and to support the safety case. SURAO decided to enhance the extent of in-situ RD and D at a depth corresponding to that of the future DGR. In 2013 SURAO commenced the construction of the Bukov Underground Research Facility in the southern section of the Rozna uranium mine at a depth of 600 m below the surface in crystalline rock environment. (authors)

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Major Achievements of the Springfields Decommissioning Program - 16512

Since the 1940's, Springfields has manufactured fuel products for the UK's nuclear power stations and for international customers. The early operations were in support of the atomic weapons program, closely followed by fuel manufacture for electricity generation via the Magnox power stations commencing in the late 1950's. In 2005, responsibility for the assets and liabilities of Springfields was transferred to the Nuclear Decommissioning Authority (NDA). A new company, Springfields Fuels Limited, was created to run the site, which was managed and operated by Westinghouse Electric UK Ltd on the NDA's behalf. On April 1, 2010, Westinghouse entered into an agreement with the NDA for a long-term lease of the Springfields site, which transferred responsibility for the commercial fuel manufacturing business and Springfields Fuels Limited to Westinghouse. Today, the main Springfields activities include: - Oxide fuels for Advanced Gas-cooled and Light Water Reactors, as well as intermediate fuel products, such as powders, granules and pellets, - Manufacture of Uranium Hexafluoride (now in Care and Maintenance), - Processing and recovery of Uranium residues, - Decommissioning and demolition of redundant plants and buildings. Some 120 plant buildings and support facilities have been successfully decommissioned and demolished in the period 1996 to date. These range from 1940's buildings, subsequently converted for nuclear fuel manufacture, together with some of the formerly sealed chemical agent manufacture and storage facilities. Decommissioning of the now redundant Magnox manufacturing facilities is ongoing at Springfields without compromising the other site operations. Westinghouse is managing all activities related to the whole lifecycle, planning, design, safety case, radiation protection, Post Operational Clean Out (POCO), service diversions, characterization, decommissioning all phases through to ground remediation, waste disposal and agreed end states. Decommissioning of process plants starts with the removal of the majority of radiological activity or hazard contained within the plant. This is known as Post Operational Clean Out. Once this is complete, the plant may be dismantled. Work is scoped and defined within packages (at plant or cell level) to aid control and commercial monitoring as the decommissioning is progressed. This package approach also enables clean or lightly contaminated items to be removed separately to aid potential re-cycling and minimize decontamination and waste disposal costs. Westinghouse is further optimising work package delivery by planning parallel POCO and Decommissioning work phases within plant at a cell level to systematically remove redundant plant and reduce hazard earlier, whilst optimising use of both internal and external resources to reduce total project cost. Waste and Residues from all phases are disposed of via authorized disposal routes and in accordance with our environmental authorizations. On completion of decommissioning and removal of plant and equipment the building is re-assessed radiologically, categorized and appropriate remediation work progressed to render it safe for conventional demolition. The major elements of the success achieved to date can be attributed to the following elements: - Overall programme management with extensive experience of planning, cost, and risk management. Integration of the programme within a major commercial site without compromising safety or operations. - Complete site EHS management working within a complex regulatory framework including the Nuclear Site Licenses, Environmental Authorisations and Security requirements. - Avoiding safety complacency by use of rigorous and systematic process to emphasise safety over competing goals. Including structured use of Human Performance and Corrective Action and Learning processes. - Unique safety experiences attained through complex hazard reduction across a broad range of uranium manufacturing and chemical hazard/agent facilities. - Project leadership and excellence utilizing a core site team to deploy repeatable processes and safe practices to deliver complex scope within budget and schedule. - Optimised use of internal and external resources, with extensive use of Operating Experience to drive continuous improvement and problem resolution. - Management of Contractors from initial selection, pre-qualification, tender assessment and Performance using varied contract forms across delivery phases. - Use of Westinghouse expertise for safety case, waste management, uranium recovery, health physics and design. - Implementation of a work package to ensure gated discreet manageable packages. Underpinned by package specific method statements, with appropriate hold points to maintain management and control of the works. - Continuous local safety focus via safety planning, induction, plant specific training, proactive risk assessment, and a defined approach to decoupling operating plant safety cases enabling focussed and usable documentation. This paper will provide an overview of the latest decommissioning activities achieved on the Springfields site and will focus on best practices that allowed Westinghouse to maintain the program on time and on budget. (authors)

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Innovative Waste Packaging and Associated Venting/Hydrogen Management - 16594

The original strategy for managing intermediate level waste (ILW) was developed in the 1980s by the UK Nuclear Industry Radioactive Waste Executive (NIREX), which is now the Radioactive Waste Management Limited (RWM), a wholly owned subsidiary of the Nuclear Decommissioning Authority (NDA). The strategy involved retrieving ILW, sorting and encapsulating it in cement based grout within thin walled stainless steel containers. The containers would then be transferred to a large purpose-built shielded ILW store on site, where they would be stored until the planned final deep geological disposal facility becomes available. In recognition of the high up-front costs of such a strategy, which requires remote facilities for the encapsulation and storage, and coupled with the long programme duration for the design, construction and commissioning of these facilities, waste management organisations responsible for managing the clean-up of legacy facilities within the UK have, in recent years, sought innovative solutions which could potentially both accelerate clean-up and hazard reduction on sites, and with a lower overall programme lifecycle cost. Many of the recent innovative solutions are focused around a new family of packaging designs known as robust shielded containers (RSCs). These are self-shielded containers manufactured from materials such as ductile cast iron or fabricated steel. These containers offer the potential to package wastes for disposal without encapsulation and avoid the need for a highly engineered remote handled shielded store for interim storage. The paper provides a high level overview of the generic concepts of RSCs developed by Croft and focuses on the specific challenges of wasteform evolution on waste package integrity and performance. In particular, the integrity and performance of the filtered vent system required to manage internal pressurisation and to ensure sufficient venting capacity of hydrogen and other evolved gases. The paper summarises the analysis by ARUP undertaken to substantiate the RSC integrity under detonation/deflagration explosion loadings arising from hydrogen accumulation. Analyses of the structural response of the filter assembly were undertaken for both detonation and deflagration explosion scenarios, with the loadings applied to the filter housing rim and to the filter vent cover. The paper also presents evidence of the mechanical performance of the filter medium in terms of pressure transients during deflagration events and the degree to which filtration efficiency is maintained. (authors)

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Chute Silo ILW Project Berkeley - 16649

Magnox, a Tier 1 Site Licensed Company (SLC), is the management and operations contractor responsible for the decommissioning of twelve of the Nuclear Decommissioning Authority's (NDA) nuclear sites in the UK. Aquila Nuclear Engineering is a specialist Tier 3, turnkey engineering company based in the UK, delivering mission critical engineering solutions to Europe's nuclear and nuclear medicine industries. Berkeley Nuclear Power Station, Berkeley, England started generating electricity in 1962, ceasing operation 27 years later in 1989. The Chute Silo ILW Project at this Reactor Site had been set up to retrieve irradiated control rods and charge chutes disposed of within a subterranean vault (silo). The project involved in-silo size reduction of waste in to 30-35 waste baskets. The waste basket was then to be retrieved via a pintle grab and hoist mechanism in to a Transfer Flask (through a silo and a Transfer Flask gamma gate). The Transfer Flask was then to transit along existing crane rails, out of the silo building and over the top of an Import/Export Facility. A Ductile Cast Iron Container (DCIC) was to be imported into Import/Export Facility and inspected/prepared to receipt the waste basket from the Transfer Flask. Once filled, the DCIC was then to be sealed and exported to an on-site storage facility. Due to an issue with the Magnox Tier 2 Framework holder in delivering a cost effective and viable solution for their Chute Silo ILW Retrieval Project, Magnox took the ground breaking decision to 'self-perform'. This involved dividing the larger project into several smaller packages. Two of these packages - for the shielded Transfer Flask and the Import/Export facility - were put out for competitive tendering directly to the Tier 3 Supply Chain. The work completed by the Tier 2 Company was shared with the Tier 3's, but Magnox expressly requested the Tier 2 proposals were scrutinised and that far more cost effective, robust and simpler solutions were provided for within the Tier 3 Tenders. Aquila won both work packages and delivered them with significant and demonstrable cost savings, on time and under budget. This was achieved by the collaborative arrangements between Aquila and Magnox, the methodologies of both company's project teams and the innovation and 'fitness for purpose' of Aquila's design pragmatism. The original Tier 2 Framework holder's price to Magnox for the Chute Silo ILW Project was between UK Pounds 2-3 M. Aquila delivered the equivalent scope for under UK Pounds 1 M. Aquila's original programme was maintained despite the award of additional scope and (Magnox) delays on site. Aquila came under the original target price for each discrete phase of the project. The above was achieved because of: - the collaborative arrangements between Aquila and Magnox; - the methodologies of both company's project teams; - the design features put forward by Aquila (welcomed and adopted by Magnox). In 2014 Aquila Nuclear Engineering received formal recognition of its achievements on this project by winning an NDA Supply Chain Award for 'Best example of supplier 'going the extra mile''. Points highlighted in the award were: - improved customer focus, leading to stronger relationships - encouraging challenge and innovation - continuous suggestions for improvement - UK Pounds 1 million savings and three months programme reduction.

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The DISTINCTIVE University Consortium: Transforming High Activity Materials Research in the UK - 18212

The DISTINCTIVE consortium (Decommissioning, Immobilisation and Storage Solutions for Nuclear Waste Inventories) is a partnership of 11 research universities, working to decommission and clean up the legacy of civil nuclear energy generation, sponsored by the Engineering and Physical Sciences Research Council (EPSRC). An important component of the research programme is to develop the skills and facilities to address key research questions, requiring the use of highly radioactive materials. Here we highlight the outcomes of four research projects in which access to state of the art research facilities for working with radioactive materials, supported by international partnerships, has advanced research in plutonium storage and immobilisation, and the disposal of spent nuclear fuels. First, we have developed a viable formulation and process for immobilisation of the UK plutonium stockpile, including commissioning of a radiological hot isostatic press and validation studies using plutonium-239. Second, we have further underpinned the interim storage of PuO{sub 2}, through understanding of water and chlorine sorption / desorption, pertinent to the historic practice of containment within, and degradation of PVC bags. Third, we have developed a novel methodology to investigate the in situ radiolysis induced dissolution of actinide oxide thin films, using synchrotron radiation, to underpin the geological disposal of spent nuclear fuel. Fourth we monitored in situ the oxidation and self-ignition mechanism of uranium carbide, a legacy fuel from the Dounreay Prototype Fast Reactor that is waiting for oxidation treatment prior to permanent storage and/or disposal. Through this programme of research, the DISTINCTIVE consortium is rebuilding the UK capability for research with transuranic materials, which, hitherto, was eroded over decades of disinvestment. (authors)

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