Relevant bibliographies by topics / British Nuclear Fuels. Sellafield

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Academic literature on the topic 'British Nuclear Fuels. Sellafield'

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Published: 4 June 2021
Last updated: 2 February 2022

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Journal articles on the topic "British Nuclear Fuels. Sellafield"

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Howden, M. "Radioactive Effluent Treatment Plant—Sellafield Reprocessing Factory." Proceedings of the Institution of Mechanical Engineers, Part A: Power and Process Engineering 201, no. 1 (February 1987): 1–15. http://dx.doi.org/10.1243/pime_proc_1987_201_002_02.

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This paper outlines the reprocessing of spent radioactive fuel at the British Nuclear Fuels plant, Sellafield, and describes the development, construction and commissioning of a new site ion exchange effluent plant (SIXEP). Gives details of the processes involved including the ion exchange columns, the ion exchanger, the carbonating tower, the waste storage tanks, the tank emptying system, and pumps and valves Reviews the initial operation of the plant and discusses future developments in radioactive waste treatment.
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Smith, P. G., and A. J. Douglas. "Mortality of workers at the Sellafield plant of British Nuclear Fuels." BMJ 293, no. 6551 (October 4, 1986): 845–54. http://dx.doi.org/10.1136/bmj.293.6551.845.

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Douglas, AJ, RZ Omar, and PG Smith. "Cancer mortality and morbidity among workers at the Sellafield plant of British Nuclear Fuels." British Journal of Cancer 70, no. 6 (December 1994): 1232–43. http://dx.doi.org/10.1038/bjc.1994.479.

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Begg, F. H., G. T. Cook, M. S. Baxter, E. M. Scott, and Martin McCartney. "Anthropogenic Radiocarbon in the Eastern Irish Sea and Scottish Coastal Waters." Radiocarbon 34, no. 3 (1992): 707–16. http://dx.doi.org/10.1017/s0033822200063992.

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14C is produced as an activation product in nuclear reactors, and may be discharged to both the atmosphere and the marine environment during nuclear fuel reprocessing. In the UK, 14C is discharged, under license, into the Eastern Irish Sea by the British Nuclear Fuels plc (BNFL) reprocessing plant at Sellafield, Cumbria, northwest England, and is then transported into Scottish coastal waters. We analyzed intertidal biota samples to determine the effect of these discharges. The specific activities of 14C found in these samples indicate that the uptake and bioaccumulation of 14C is dependent on the type of organism and its feeding behavior. Measured 14C concentrations in mussels (Mytilus edulis) were higher than those in winkles (Littorina littorea), which were greater than those found in seaweed (Fucus spp.); maximum observed activities were ca. 7, 5 and 3.5 times the accepted current ambient level of 260 Bq kg−1 C, respectively. Annual Nori (Porphyra umbilicalis) samples were analyzed for their 137Cs, 241Am and 14C contents; both the 137Cs and 241Am results correlated well with published Sellafield discharge data (r = 0.877 and 0.918, respectively), whereas there was no significant correlation between measured 14C activities and the discharge record, indicating increased complexity in the chemical and biological behavior of 14C or some discrepancy in the estimated discharge records.
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Omar, R. Z., J. A. Barber, and P. G. Smith. "Cancer mortality and morbidity among plutonium workers at the Sellafield plant of British Nuclear Fuels." British Journal of Cancer 79, no. 7-8 (February 12, 1999): 1288–301. http://dx.doi.org/10.1038/sj.bjc.6690207.

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Woodhead, D. S., D. F. Jefferies, and C. J. Barker. "Contamination of beach debris following an incident at British Nuclear Fuels plc, Sellafield, November 1983." Journal of the Society for Radiological Protection 5, no. 1 (March 1985): 21–32. http://dx.doi.org/10.1088/0260-2814/5/1/003.

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7

LEE, TERENCE, and NICHOLAS BALCHIN. "LEARNING AND ATTITUDE CHANGE AT BRITISH NUCLEAR FUEL'S SELLAFIELD VISITORS CENTRE." Journal of Environmental Psychology 15, no. 4 (December 1995): 283–98. http://dx.doi.org/10.1006/jevp.1995.0025.

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8

McGeoghegan, D., M. Gillies, A. E. Riddell, and K. Binks. "Mortality and cancer morbidity experience of female workers at the British Nuclear Fuels Sellafield plant, 1946-1998." American Journal of Industrial Medicine 44, no. 6 (November 14, 2003): 653–63. http://dx.doi.org/10.1002/ajim.10316.

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Hamilton, E. I. "The disposal of radioactive wastes into the marine environment: the presence of hot particles containing Pu and Am in the source term." Mineralogical Magazine 49, no. 351 (April 1985): 177–94. http://dx.doi.org/10.1180/minmag.1985.049.351.05.

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AbstractRadioactive particulate matter (identified as hot particles) is present in the effluent discharged by the British Nuclear Fuels Ltd (BNFL) uranium reprocessing plant at Sellafield, Cumbria, UK. There is very little information on the abundance or chemical and physical forms of solid matter in the effluent; even less is known of the significance of particulate debris in relation to the uptake of radionuclides for non-occupationally exposed people as a result of transfer along marine foodchains. Some observations on the occurrence and abundance of hot particles in the vicinity of Sellafield are reported, with special reference to those that contain transuranic radionuclides (Pu,Am,Cm). Some of the uncertainties are discussed in an evaluation of the significance of hot particles, albeit aggregates of colloids for the smallest particles, and exposure to man from ionizing radiation. There is no evidence that hot particles derived from BNFL and subsequently dispersed into the marine environment represent a hazard to man. However, further studies are required in order to determine whether or not the pathways followed by the particles are significant, or different to those of other radionuclides through which the radiation exposure of man within this region of Cumbria is assessed.
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Cook, G. T., F. H. Begg, Philip Naysmith, E. M. Scott, and Martin McCartney. "Anthropogenic 14C Marine Geochemistry in the Vicinity of a Nuclear Fuel Reprocessing Plant." Radiocarbon 37, no. 2 (1995): 459–67. http://dx.doi.org/10.1017/s0033822200030939.

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The British Nuclear Fuels plc reprocessing plant at Sellafield in Cumbria, Northwest England, discharges between 1 and 3 TBq of 14C per annum as low-level waste via a pipeline into the Eastern Irish Sea. Our results demonstrate 14C activities in excess of the current ambient level (i.e., ca. 260 Bq kg−1 carbon) in a range of both biotic and abiotic samples with evidence that a significant percentage of the discharges are in the form of dissolved inorganic carbon (DIC). There also appears to be a significant seasonal influence on the uptake of the DIC by the phytoplankton, most likely linked to their bloom periods. Results from different aspects of the research are integrated to provide an opportunity to consider the overall distribution and behavior of 14C in the Eastern Irish Sea. We also discuss the results in terms of existing sediment chronologies and sedimentation rates and consider the possible consequences of phytoplankton blooms on the cycling of the other radionuclides.
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Dissertations / Theses on the topic "British Nuclear Fuels. Sellafield"

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Harrison, Rebecca Jane. "Scientific evidence and the toxic tort : a socio-legal study of the issues, expert evidence and judgment in Reay and Hope v. British Nuclear Fuels plc." Thesis, London School of Economics and Political Science (University of London), 1999. http://etheses.lse.ac.uk/2002/.

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Providing a socio-legal analysis of the issues, expert evidence and judgment in Reay and Hope v BNFL plc., the thesis offers an insight into the complexity of the toxic tort. Starting with an overview of the history of Sellafield, the thesis reflects on the scientific and epidemiological concerns surrounding the link between childhood cancer and nuclear installations. Drawing on scientific knowledge and epistemological considerations, the thesis moves on to the difficulties of verifying causation in science and the problems of establishing causation in law. Outlining the role of the expert witness and scientific expert evidence, the thesis proceeds with a case analysis, before broaching the thorny issue of judicial decision making and in particular, the difference between the 'discovery' and 'justification' process. Moving on to the Judgment in Reay and Hope, attention is given to the potential application of probability theory to the judicial decision making process. Lasting just short of one hundred days and including the testimony of numerous scientific experts, Reay and Hope marked new ground in a number of ways; it was the first personal injury claim to test the concept of genetic damage from radiation; the only time that a Queen's Bench Division Judge had been allocated a full-time judicial assistant; and one of the first trials to endorse a satellite video link for examination of international expert witnesses. As far as judicial management is concerned, the case was a forerunner in having Counsels' Opening Statements in writing in advance of the trial, as well as having written daily submissions of key issues from plaintiffs and defendants upon conclusion of oral evidence. The circumstances that led to the trial relate to events in excess of thirty to forty years ago when the fathers of Dorothy Reay and Viven Hope were employed by the Defendants and their predecessors (the United Kingdom Atomic Energy Authority) as fitters for the Sellafield Plant. Intrinsic to the litigation was whether paternal preconception irradiation caused or materially contributed to a predisposition to cancer leading to Dorothy's death from leukaemia and Vivien Hope's non-Hodgkin's lymphoma. As a consequence of the various statutory provisions, the Plaintiffs did not need to prove negligence on the part of the Defendants. In order to succeed the Plaintiffs had to prove on the balance of probabilities that radiation from Sellafield was a material contributory cause of the Plaintiffs' disease. The fundamental issue therefore was causation. In addition to the case analysis, two pieces of empirical research were conducted for the purposes of this thesis. The first, a Social Survey (consisting of thirty four questions) was circulated to 160 members of the Academy of Experts (quantitative research); the second, a letter, involved written communication with sixty five judges from the Queen's Bench Division of the High Court (qualitative research). Underlying this socio-legal case analysis are fundamental questions with regard to existing legal principles, liability and judicial decision making.
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Books on the topic "British Nuclear Fuels. Sellafield"

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Bolter, Harold. Inside Sellafield. London: Quartet Books, 1996.

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2

Davies, Hunter. Sellafield stories. London: Constable, 2012.

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Watts, Paul. "Unjustifiable exposures": Sellafield radioactive contamination of the rivers Lune and Wyre, Lancashire, UK : a report. London: Friends of the Earth, 1990.

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Fearing Sellafield: What it is and why the Irish want it shut. Dublin: Gill & Macmillan, 2003.

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5

Great Britain. Nuclear Installations Inspectorate. Safety of the storage of liquid high level waste at BNFL Sellafield: A report. (London): HSE Books, 1995.

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Saunders, C. P. R. A review of "The potential effects of release of Krypton-85". Bristol: Her Majesty's Inspectorate of Pollution, 1993.

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Great Britain. Parliament. House of Commons. Committee of Public Accounts. Monitoring and control of British Nuclear Fuels plc. London: H.M.S.O., 1989.

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Arnold, Lorna. Windscale, 1957: Anatomy of a nuclear accident. New York: St. Martin's Press, 1992.

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Windscale 1957: Anatomy of a nuclear accident. 2nd ed. Basingstoke: Macmillan, 1995.

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Windscale 1957: Anatomy of a nuclear accident. Basingstoke: Macmillan Academic and Professional, 1992.

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Conference papers on the topic "British Nuclear Fuels. Sellafield"

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Birch, M. J., R. Doig, J. Francis, D. Parker, and G. Zhang. "A Review of Vortex Amplifier Design in the Context of Sellafield Nuclear Operations." In ASME 2009 12th International Conference on Environmental Remediation and Radioactive Waste Management. ASMEDC, 2009. http://dx.doi.org/10.1115/icem2009-16063.

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Vortex amplifiers have for over 30 years been used to ensure containment of glove-box ventilation in the event of a barrier breach, the most likely such breach being damage to the glove itself. Containment is achieved using fluidic principles to control the glove-box depression and ventilation rate under both normal and emergency conditions; in the event of such a breach vortex amplifiers can switch quickly between these two states without recourse to electrical, pneumatic or manual intervention. This paper begins by summarising the developments in vortex amplifier design used at the Sellafield site by successive companies engaged in fuel technology, reprocessing and decommissioning (British Nuclear Fuels PLC (BNFL), BNFL Engineering Limited, British Nuclear Group and Sellafield Limited). The main reasons for design changes have been practical issues of set-up, cleaning, filter and waste minimisation, and space limitations. The development culminates in the use of a smaller version of the vortex amplifier (VXA) which is a nearly exact geometrical scaling of its predecessor and which has been standard design for over a decade. Initial use of this device, the mini–VXA, led to a substantial increase in the amount of inert gas needed to maintain the required oxygen-depletion conditions within the glove-box, implying some escape of oxygen into the glove-box. The use of the mini–VXA introduced practical issues relating to (i) its control characteristics and (ii) the reverse flow of air in the supply port. Comparison with the published design specification demonstrates that the geometrical scaling process has led to a slightly hysteric characteristic. Tests conducted by the authors indicate (i) that the origin of the escaping oxygen is the control air feeding back through the supply ports and (ii) that a prototype chamber and orifice plate arrangement between the glove-box and mini–VXA significantly reduces the inert gas demand in normal usage. This prototype arrangement introduced problems in maintaining a clean environment in the chamber, so the chamber and orifice was substituted by a detachable cowl that enabled the mini–VXA to be located within the glove-box and provided access for cleaning.
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Thorne, Simon. "The Misuse of Spreadsheets in the Nuclear Fuel Industry: The Falsification of Safety Critical Nuclear Fuel Data Using Spreadsheets at British Nuclear Fuels Limited (BNFL)." In 2012 45th Hawaii International Conference on System Sciences (HICSS). IEEE, 2012. http://dx.doi.org/10.1109/hicss.2012.579.

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Reeve, Phil, and Katherine Eilbeck. "Contaminated Land and Groundwater Management at Sellafield: A Large Operational Site With Significant Legacy and Contaminated Land Challenges." In The 11th International Conference on Environmental Remediation and Radioactive Waste Management. ASMEDC, 2007. http://dx.doi.org/10.1115/icem2007-7051.

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Sellafield is a former Royal Ordnance Factory used since the 1940’s for the production and reprocessing of fissile materials. Leaks and spills from these plants and their associated waste facilities has led to radioactive contaminated ground legacy of up to 20 million m3. Consideration of land contamination at Sellafield began in 1976, following discovery of a major leak from a waste storage silo. Over the past three decades there has been a programme of environmental monitoring and several phases of characterization. The latest phase of characterization is a £10million contract to develop second generation conceptual and numeric models. The Site Licence Company that operates the site has been subject to structural changes due to reorganizations within the British nuclear industry. There has also been a change in emphasis to place an increased importance on accelerated decommissioning. To address these challenges a new contaminated land team and contaminated land and groundwater management plan have been established. Setting and measuring performance against challenging objectives is important. The management plan has to be cognizant of the long timescales (ca. 80 years) for final remediation. Data review, collation, acquisition, analysis, and storage is critical for success. It is equally important to seize opportunities for early environmental gains. It is possible to accelerate the development and delivery of a contaminated land and groundwater management plan by using international experts.
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Gleason, Eugene, and Gerard Holden. "Packaging and Transportaion of Radioactively Contaminated Lead." In The 11th International Conference on Environmental Remediation and Radioactive Waste Management. ASMEDC, 2007. http://dx.doi.org/10.1115/icem2007-7182.

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Under the management of the Nuclear Decommissioning Authority (NDA) the government of the United Kingdom has launched an ambitious program to remediate the nation’s nuclear waste legacy. Over a twenty-five year period NDA plans to decommission several first generation nuclear power plants and other radioactive facilities. The use innovative, safe “fit for purpose” technologies will be a major part of this complex program. This paper will present a case study of a recently completed project undertaken in support of the nuclear decommissioning activities at the Sellafield site in the United Kingdom. The focus is on an innovative application of new packaging technology developed for the safe transportation of radioactively contaminated lead objects. Several companies collaborated on the project and contributed to its safe and successful conclusion. These companies include British Nuclear Group, Gravatom Engineering, W. F. Bowker Transport, Atlantic Container Lines, MHF Logistical Solutions and Energy Solutions. New containers and a new innovative intermodal packaging system to transport the radioactive lead were developed and demonstrated during the project. The project also demonstrated the potential contribution of international nuclear recycling activities as a safe, economic and feasible technical option for nuclear decommissioning in the United Kingdom. Eugene J. Gleason is Vice President for Government Affairs and International Initiatives at MHF Logistical Solutions. Gerard Holden is Director for Waste packaging at Gravatom Engineering Limited.
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Morris, Jenny, Stephen Wickham, Phil Richardson, Colin Rhodes, and Mike Newland. "Contingency Options for the Dry Storage of Magnox Spent Fuel in the UK." In ASME 2009 12th International Conference on Environmental Remediation and Radioactive Waste Management. ASMEDC, 2009. http://dx.doi.org/10.1115/icem2009-16330.

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The UK Nuclear Decommissioning Authority (NDA) is responsible for safe and secure management of spent nuclear fuel. Magnox fuel is held at some Magnox reactor sites and at Sellafield where it is reprocessed using a number of facilities. It is intended that all Magnox fuel will be reprocessed as described in the published Magnox Operating Programme (MOP) [1]. In the event, however, that a failure occurs within the reprocessing plant, the NDA has initiated a programme of activities to explore alternative contingency options for the management of wetted Magnox spent fuel. Magnox fuel comprises metallic uranium bar clad in a magnesium alloy, both of which corrode if exposed to oxygen or water. Consequently, contingency options are required to consider how best to manage the issues associated with the reactivity of the metals. Questions such as whether Magnox spent fuel needs to be dried, how it might be conditioned, how it might be packaged and held in temporary storage until a disposal facility becomes available, all require attention. During storage in the presence of water, the corrosion of Magnox fuel produces hydrogen (H2) gas, which requires careful management. When uranium reacts with hydrogen in a reducing environment, the formation of uranium hydride (UH3) may occur, which under some circumstances can be pyrophoric, and might create hazards which may affect subsequent retrieval and/or repackaging (e.g. for disposal). Other factors that may affect the choice of a viable contingency option include criticality safety, environmental impacts, security and Safeguards and economic considerations. Magnox fuel has been successfully dry-stored as intact fuel elements in CO2- and air-filled primary and secondary cells at Wylfa Power Station, UK. Storage of some fuel elements in the Wylfa secondary cells has been carried out successfully for over 25 years. Other relevant experience includes the French UNGG (Uranium Naturel Graphite Gaz) and U.S. Hanford N-Reactor spent fuels, both of which have been retrieved and dried after decades of wet storage. The dried fuels are respectively stored in sealed canisters in modular vault stores at Cadarache (CASCAD) and Hanford (Canister Storage Building). The applicability of these and other potential store designs, such as concrete and metal casks and silos, to the storage of Magnox spent fuel is discussed.
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Stewart, M. W. A., S. A. Moricca, B. D. Begg, R. A. Day, C. R. Scales, E. R. Maddrell, and A. B. Eilbeck. "Flexible Process Options for the Immobilisation of Residues and Wastes Containing Plutonium." In The 11th International Conference on Environmental Remediation and Radioactive Waste Management. ASMEDC, 2007. http://dx.doi.org/10.1115/icem2007-7246.

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Residues and waste streams containing plutonium present unique technical, safety, regulatory, security, and sociopolitical challenges. In the UK these streams range from lightly plutonium contaminated materials (PCM) through to residues resulting directly from Pu processing operations. In addition there are potentially stocks of Pu oxide powders whose future designation may be either a waste or an asset, due to their levels of contamination making their reuse uneconomic, or to changes in nuclear policy. While waste management routes exist for PCM, an immobilisation process is required for streams containing higher levels of Pu. Such a process is being developed by Nexia Solutions and ANSTO to treat and immobilise Pu waste and residues currently stored on the Sellafield site. The characteristics of these Pu waste streams are highly variable. The physical form of the Pu waste ranges from liquids, sludges, powders/granules, to solid components (e.g., test fuels), with the Pu present as an ion in solution, as a salt, metal, oxide or other compound. The chemistry of the Pu waste streams also varies considerably with a variety of impurities present in many waste streams. Furthermore, with fissile isotopes present, criticality is an issue during operations and in the store or repository. Safeguards and security concerns must be assessed and controlled. The process under development, by using a combination of tailored waste form chemistry combined with flexible process technology aims to develop a process line to handle a broad range of Pu waste streams. It aims to be capable of dealing with not only current arisings but those anticipated to arise as a result of future operations or policy changes.
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Morris, Jenny, Stephen Wickham, Phil Richardson, Colin Rhodes, and Mike Newland. "Contingency Options for the Drying, Conditioning and Packaging of Magnox Spent Fuel in the UK." In ASME 2009 12th International Conference on Environmental Remediation and Radioactive Waste Management. ASMEDC, 2009. http://dx.doi.org/10.1115/icem2009-16331.

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The UK Nuclear Decommissioning Authority (NDA) is responsible for safe and secure management of spent nuclear fuel. Magnox spent fuel is held at some Magnox reactor sites and at Sellafield where it is reprocessed using a number of facilities. It is intended that all Magnox fuel will be reprocessed, as described in the published Magnox Operating Plan (MOP) [1]. In the event, however, that a failure occurs within the reprocessing plant, the NDA has initiated a programme of activities to explore alternative contingency options for the management of wetted Magnox spent fuel. Magnox fuel comprises metallic uranium bar clad in a magnesium alloy, both of which corrode if exposed to oxygen or water. Consequently, contingency options are required to consider how best to manage the issues associated with the reactivity of the metals. Questions of whether Magnox spent fuel needs to be dried, how it might be conditioned, how it might be packaged, and held in temporary storage until a disposal facility becomes available, all require attention. A review of potential contingency options for Magnox fuel was conducted by Galson Sciences Ltd, UKAEA and the NDA. During storage in the presence of water, the corrosion of Magnox fuel produces hydrogen (H2) gas, which requires careful management. When uranium reacts with hydrogen in a reducing environment, the formation of uranium hydride (UH3) may occur, which under some circumstances can be pyrophoric, and might create hazards which may affect subsequent retrieval and/or repackaging (e.g. for disposal). Other factors that may affect the choice of a viable contingency option include criticality safety, environmental impacts, security and Safeguards and economic considerations. At post-irradiation examination (PIE) facilities in the UK, Magnox spent fuel is dried as a result of storage in air at ambient temperatures. Early French UNGG (Uranium Naturel Graphite Gaz) fuel was retrieved from pond storage at Cadarache, dried using a hot gas drying technique, oxidised and packaged in sealed canisters and placed in interim storage at the CASCAD (CASemate CADarache) facility. In the US, spent fuels including the Zircaloy clad Hanford N-Reactor fuels were cold vacuum dried and Idaho legacy aluminium clad metallic uranium fuels were hot vacuum dried; the dried fuel was then packaged in sealed and vented canisters (at Hanford and Idaho, respectively) for interim storage. With regard to conditioning and packaging, several different approaches have been reviewed, including encapsulation in cementitious grout or polymer, high-temperature vitrification or ceramicisation, and solution in acid or alkali solution followed by cementation or vitrification (without reprocessing). All of these approaches require further research in order to be evaluated and developed further for application to formerly wetted Magnox fuel. A variety of containers have been developed for the transport, storage and/or disposal of spent fuel in radioactive waste management programmes worldwide. Wetted Magnox spent fuel could be packaged in a container, with reservations about the potential formation of UH3 in a sealed environment where reducing conditions may develop. The applicability of different combinations of drying, conditioning and packaging techniques to the preparation of Magnox spent fuel for long-term storage and eventual disposal are discussed.
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Ambrosek, Richard G., and Debbie J. Utterbeck. "Comparison of Predictive and Experimental Data From Graphite Irradiations in the Advanced Test Reactor Irradiation Test Vehicle." In ASME 2003 Heat Transfer Summer Conference. ASMEDC, 2003. http://dx.doi.org/10.1115/ht2003-47396.

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In 2000, British Nuclear Fuels Limited (BNFL) commissioned an irradiation program at the United States Department of Energy’s Idaho National Engineering and Environmental Laboratory (INEEL) to assess the effects of extended operating scenarios upon the integrity of Magnox reactor cores. In this program, predictions of thermal and physical effects on these graphite cores were developed using analytical computer models. To benchmark results, experimental graphite assemblies representative of the Magnox graphite were irradiated in the Advanced Test Reactor (ATR). This paper analyzes and contrasts the thermal predictions with those experimental results. These investigations were conducted to extend existing graphite physical property databases for higher radiolytic weight loss (35–50% density reduction) than occur during the economic planning life of these reactors. These data then can be used to make extended life projections regarding the suitable function of the graphite in its various roles of providing the physical structure for the fuel, neutron moderator, medium for instrumentation, and coolant channels. Extended irradiation effects will be obtained with samples of archived, pre-characterized graphite used in the Magnox type reactors. The new Irradiation Test Vehicle (ITV) facility in the ATR contained the experiments and provided the desired irradiation conditions as well as on-line temperature control. The capability to provide both oxidizing and inert gas atmospheres for the graphite specimens was added to the ITV to enable assessment of the individual and combined effects of oxidation and neutron damage to the specimens. In this paper the thermal evaluations (performed to size the control gaps to obtain the desired thermal performance) are contrasted to actual experimental results.
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