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Sample records for bnfl

  1. Fuelling doubts over BNFL

    International Nuclear Information System (INIS)

    Wyman, V.

    1989-01-01

    The House of Commons Select Committee on Energy has recently questioned the whole philosophy behind one of Britain's largest process plant operators, British Nuclear Fuels (BNFL). The committee's criticisms and recommendations are of significance to more than just BNFL, whose 1988 turnover of Pound 839 million produced a Pound 100 million pretax profit for its owner, the government. For BNFL's fortunes are linked intimately with those of its customers, the nuclear power station operators. The members of Parliament are especially critical of BNFL's right to pass most of its cost increases on to its customers, which will make the nuclear power stations less attractive to investors when they are privatised. The committee also voices other serious concerns about BNFL's operations. These include worry about the future ownership of plutonium produced by BNFL from its customers' spent nuclear fuel; whether resultant nuclear waste is sent back to overseas customers; and the fate of the vast sums being put aside for future decommissioning of BNFL plant. (author)

  2. BNFL's progress in addressing the findings of the ''Safety audit of BNFL Sellafield 1986''

    International Nuclear Information System (INIS)

    1994-01-01

    An audit of the British Nuclear Fuels Limited (BNFL) Sellafield site, and in particular the reprocessing plant, was carried out by the United Kingdom Nuclear Installations Inspectorate in the first half of 1986 following a series of incidents. The outcome was a set of requirements on BNFL to bring about significant improvements in many procedural and engineering aspects. Details of BNFL's response are given in this report. Areas where BNFL needs to continue to focus attention in the future are identified, but an overall satisfactory response to the audit findings is recorded. (UK)

  3. BNFL - Action in education

    International Nuclear Information System (INIS)

    Squire, C.

    1994-01-01

    The introduction of the National Curriculum in England and Wales gave the British Nuclear Fuels (BNFL) company the opportunity to develop a more structured involvement. Extensive research among teachers revealed how a high-tech company such as BNFL could make the best contribution, by funding the development of classroom materials which would encourage pupils to assess the advantages and disadvantages of technology. Five years later, BNFL's educational resources have gained substantial credibility

  4. BNFL Springfields Fuel Division

    International Nuclear Information System (INIS)

    Tarkiainen, S.; Plit, H.

    1998-01-01

    The Fuel Division of British Nuclear Fuels Ltd (BNFL) manufactures nuclear fuel elements for British Magnox and AGR power plants as well as for LWR plants. The new fuel factory - Oxide Fuel Complex (OFC), located in Springfields, is equipped with modern technology and the automation level of the factory is very high. With their quality products, BNFL aims for the new business areas. A recent example of this expansion was shown, when BNFL signed a contract to design and license new VVER-440 fuel for Finnish Loviisa and Hungarian Paks power plants. (author)

  5. BNFL and community relations

    International Nuclear Information System (INIS)

    Bolter, H.

    1982-01-01

    The contributions made by BNFL to community relations are described in an illustrated booklet under the headings: introduction (general policy); donations and sponsorships; BNFL talks service; brochures and public information; visits; local liaison committees; industrial training; sponsored students; apprentices. (U.K.)

  6. BNFL's nuclear future

    International Nuclear Information System (INIS)

    Collum, H.

    2001-01-01

    As the nuclear industry arrives at a crossroads, this paper looks at BNFL's nuclear future. It does this by addressing two key issues: the energy balance and regulation. The first issue takes in the problems of climate change and renewables, and the nuclear contribution. The second issue raises the possibility that, although safety is the top priority for BNFL, the cost of regulation may be becoming disproportionate to the advantages gained. The paper concludes that the balancing act between energy supply and CO 2 reduction can only be achieved successfully if nuclear is a significant part of the equation. (author)

  7. BNFL decommissioning strategy and techniques

    International Nuclear Information System (INIS)

    Taylor, D.

    2002-01-01

    This paper provides an overview of the range of reactor decommissioning projects being managed by BNFL, both on its own sites and for other client organizations in the UK and abroad. It also describes the decommissioning strategies and techniques that have been developed by BNFL and adopted in order to carry out this work

  8. Public relations activities in BNFL

    Energy Technology Data Exchange (ETDEWEB)

    Phillips, B. [British Nuclear Fuels plc, Cheshire (United Kingdom)

    1993-12-31

    British Nuclear Fuels plc (BNFL) is a major industrial company employing 15,000 people and supporting another 50,000 jobs in British industry through it`s isnvestment program. BNFL is frequently in the news, mainly because of the Sellafield reprocessing plant in West Cumbria. The company`s public relation policy is described in this report.

  9. Development of MOX manufacturing technology in BNFL

    International Nuclear Information System (INIS)

    Buchan, P.G.; Powell, D.J.; Edwards, J.

    1998-01-01

    BNFL is successfully operating a small scale MOX fuel fabrication facility at its Sellafield Site and is currently constructing an advanced, commercial scale MOX facility to complement its existing LWR UO 2 fabrication capability. BNFL's MOX fuel capability is fully supported by a comprehensive technology development programme aimed at providing a high quality product which is successfully competing in the market. Building on the experience gained over the last 30 years, is from the production of both thermal and fast reactor MOX fuels, BNFL's development team set a standard for its MOX product which is targeted at exceeding the performance of UO 2 fuel in reactor. In order to meet the stringent design requirements the product development team has introduced the Short Binderless Route (SBR) process that is now used routinely in BNFL's MOX Demonstration Facility (MDF) and which forms the basis for BNFL's large scale Sellafield MOX Plant. This plant not only uses the SBR process for MOX production but also incorporates the most advanced technology available anywhere in the world for nuclear fuel production. A detailed account of the technology developed by BNFL to support its MOX fuels business will be provided, together with an explanation of the processes and plants used for MOX fuel production by BNFL. The paper also looks at the future needs of the MOX business and how improvements in pellet design can assist the MOX fabrication production process to meet the user demand requirements of utilities around the world. (author)

  10. BNFL nuclear decommissioning liabilities management program

    International Nuclear Information System (INIS)

    Colquhoun, A.P.

    1995-01-01

    The objective of this paper is to describe BNFL's policy and strategy for decommissioning and also to summarize the overall scope of nuclear liabilities in the wider field of waste retrieval and storage, as well as the dismantling and demolition aspects of decommissioning. BNFL's recently established organisational arrangements for discharging all types of these liabilities are explained, together with a review of practical progress in dealing with them. Organisational changes in recent years have amalgamated decommissioning work with operations covering waste storage and retrieval operations. A strategy of minimising residual activity in shutdown plants is pursued, followed by dismantling and demolition on appropriate time scales to minimise risk and cost. Since April 1995, a new BNFL subsidiary, Nuclear Liabilities Management Company Limited has taken responsibility for discharge of BNFL's Waste Retrieval and Decommissioning liabilities on all BNFL sites. NLM has the objectives of optimal and lowest cost management of liabilities and much clearer segregation of physical operations from project specification and planning. The Ministry of Defense (MoD) policy, strategy, work programmes and progress for the Atomic Weapons Establishment (AWE) are also outlined. MoD/AEA has established an equivalent strategy for dealing with its liabilities. (J.S.). 5 refs., 2 figs., 4 appends

  11. Integrated engineering increases flexibility. [At BNFL

    Energy Technology Data Exchange (ETDEWEB)

    Smith, Ray [British Nuclear Fuels plc, London (UK)

    1991-05-01

    Integrated Engineering (IE) can be used to describe the best use of increasingly rare good engineering talent in an increasingly competive world. A number of organisations are now moving towards IE without any general agreement on a precise definition. The engineering division of British Nuclear Fuels (BNFL) is one such organisation. This feature covers the reasoning behind the decision, and our experience to date. BNFL engineering division is responsible primarily for the provision of major facilities on BNFL operational sites. This provision includes feasibility, front end and detailed design, procurement, installation and commissioning. Task force working has been used for some of the large projects. But the future workload is expected to comprise many more smaller projects. At the same time, equipment is becoming more complex and the need for mutual understanding and appreciation between disciplines is increasing. To meet this increasing need for flexibility, BNFL has decided to move to the matrix structure of project management and functional departments described in the article. (Author).

  12. BNFL Sellafield further public consultation

    International Nuclear Information System (INIS)

    1994-01-01

    The main issues raised during the further public consultation on the draft Sellafield authorisations for the discharge of radioactive wastes from the British Nuclear Fuel (BNFL) Sellafield site are outlined. An analysis of the categories and numbers of the 42,500 responses is made. The public consultation was based on five documents; a letter to consultees from the Department of the Environment and the Ministry of Agriculture, Fisheries and Food (MAFF); the report by Her Majesty's Inspectorate of Pollution and the Inspectorate of MAFF on their earlier consultation exercise; a paper by BNFL on the economic and commercial justification of the Thermal Oxide Reprocessing Plant (THORP); a statement of the Government's policy on reprocessing and THORP and a document prepared by BNFL on the environmental implication of THORP. (UK)

  13. BNFL/Siemens to merge?

    International Nuclear Information System (INIS)

    Anon.

    1997-01-01

    Negotiations are being conducted on the creation of a joint venture between British Nuclear Fuels Limited (BNFL) and the German company Siemens. The venture would merge Siemens' nuclear fuel, engineering and construction services businesses with BNFL's Magnox and AGR fuel fabrication business which is based at Springfields in Lancashire. It would incorporate Siemens' share of Nuclear Power International, a joint venture with the French company Framatone which is developing the European Pressurised Water Reactor project, and its US subsidiary Siemens' Power Corp. BNFL's mixed oxide (MOX) fuel fabrication business, its stake in the Dutch-German-UK uranium enrichment company Urenco and its nuclear waste reprocessing business would not be involved. There is already speculation that Siemens' greater input will lead to it taking a majority stake in what will be the world's second largest nuclear fuel manufacturer. Reaction to the news is reported. This has been muted in the United Kingdom, mixed in Germany and adverse in France because of the implications for the Siemens' Framatone collaboration. (UK)

  14. Commander manipulator scoops prestigious mulit-million pound BNFL contract

    International Nuclear Information System (INIS)

    Bailey, Andrew.

    1997-01-01

    Twenty-one Commander robotic arms are on order from INBIS (formerly Ricardo Hitec) and BNFL Engineering Limited (''BEL'', the engineering arm of parent company BNFL). The multi-million pound contract was won amid fierce competition from other well-known names in robotic engineering. The specially designed Commander manipulators will be engaged in remotely handling Intermediate Level Waste (ILW) in a suite of four BNFL ILW plants, which are currently either under construction or planned at Sellafield. The first Commander will delivered to BNFL's Sellafield Silo Emptying Project in January 1998. (Author)

  15. BNFL Sellafield: post audit progress, December 1987

    International Nuclear Information System (INIS)

    1987-12-01

    The report of the safety audit at the Sellafield site was published in December 1986. In this, the Health and Safety Executive required British Nuclear Fuels (BNFL) to make improvements to the site and safety cases have had to be produced. These have now to be assessed by the Nuclear Installations Inspectorate. BNFL has undertaken programmes of maintenance, refurbishment and replacement of equipment. Much of this work was done in the shut-down maintenance period in the spring and summer. However, more work is needed to bring plants up a condition suitable for operating for the next ten years. BNFL have also started to decontaminate and decommission disused, contaminated, plants. This will generate a large amount of radioactive waste. BNFL have to build plants to containerise and encapsulate the waste prior to disposal. Waste disposal sites to complete the clean-up process are needed. The improvements to the engineering plants, to written procedures and to training, are reported. Changed attitudes are also noted. (U.K.)

  16. The status of BNFL's MOX project

    International Nuclear Information System (INIS)

    Edwars, John; Cooch, Julian P.; Slater, Michel W.

    2002-01-01

    Full text: In the late 1980s BNFL decided to enter the MOX fuel fabrication business to support our reprocessing business and return the plutonium product to our customers in the useable form of MOX fuel. The first phase of the strategy was to gain some irradiation experience for MOX produced by our own Short Binderless Route (SBR) process. To achieve this the MOX Demonstration Facility (MDF) was built at Sellafield and 28 MOX fuel assemblies were produced up to 1998 that were loaded into PWRs in Europe. In 1994, BNFL started the construction of their large scale MOX production plant, SMP. The design and construction of the plant and supporting facilities was completed some years ago and the commissioning of the plant with uranium commenced around June 1999. In October 2001, the UK Government provided BNFL with the approval to operate SMP with plutonium. On 20 December 2001, the UK Regulators gave BNFL their approval to start plutonium operations. This paper summarises the approach used to commission SMP and describes some of the lessons learnt during the commissioning phase of the project and the start up of the plant with plutonium. An explanation of our experience obtaining a licence to operate the plant is provided together with a description of the changes we have made to ensure that the quality of the product from SMP can be guaranteed. Finally, the paper summarises the experience BNFL has gained during irradiating MOX fuel produced by the SBR process and explains how the data compares with that available for UO2 and supports the in reactor use of MOX fuel made in SMP. (author)

  17. The BNFL radiation-mortality study

    International Nuclear Information System (INIS)

    Clough, E.A.; Schofield, G.B.

    1982-01-01

    An overview of an epidemiological study of BNFL employees and pensioners is presented. Overall, mortality patterns are similar to those in the general population. Non-cancer deaths among serving staff are significantly below those expected from national statistics due to the healthy worker effect; pensioners are more comparable to the national population. A similar pattern is found for lung malignancy. Observed deaths due to other cancers among serving staff and pensioners approximate closely to expectation; most are due to leukaemia but there is no evidence of any increased incidence at Sellafield where radiation exposures are higher than at other BNFL sites. (U.K.)

  18. Meeting the challenge of BNFL's decommissioning programme

    International Nuclear Information System (INIS)

    Sheil, A.E.

    1997-01-01

    The paper reviews the co-ordinated and integrated programme, adopted by BNFL, in the decommissioning of its radioactive plants. It examines BNFL's approach to the challenges posed by the eventual decommissioning of its 120 plants, its overall strategies, the constraints and the progress achieved to date, drawing on real experience from the 22 completed projects and the 24 projects currently underway. (author)

  19. Approach to customer qualification of the BNFL Sellafield Mox Plant

    International Nuclear Information System (INIS)

    Sullivan, P.

    2003-01-01

    BNFL started plutonium commissioning of its Sellafield MOX Plant (SMP) in December 2001, with the first MOX pellets being produced in May 2002. SMP was designed to manufacture a range of both PWR and BWR fuel types for a number of different customers. During commissioning and early MOX fuel manufacturing BNFL has been demonstrating its ability to both automatically manufacture and inspect MOX fuel to meet the requirements of different customers' specifications and fuel types. The qualification project consisted of common and project specific qualification. Common qualification was carried out to demonstrate BNFL could meet several customers' requirements during the same qualification test. Project specific qualification was carried out for one customer only as the fabrication or inspection equipment was specific to their fuel type. An example is the fuel assembly process. The reasons for BNFL carrying out common qualification were: - Develop a common qualified process to meet different customer specifications. - Minimise future qualifications prior to starting future fuel campaigns. - Ensure BNFL understands and effectively manages different customer requirements in SMP. BNFL has approached qualification of SMP systematically. Firstly the inspection system was qualified, and once completed the inspection system was then used in the qualification of the manufacturing process. (orig.)

  20. Remote viewing system development in BNFL

    International Nuclear Information System (INIS)

    Case, D.R.; Garlick, D.R.; Crawford, G.; Montgomerie, J.

    1996-01-01

    The application of imaging systems to BNFL's plants is primarily provided by the Company's Engineering Group. Many systems have been developed for active service and several new developments are currently in an advanced stage of implementation. BNFL has acquired extensive experience of remote viewing from a series of projects undertaken for the Sellafield site in West Cumbria. Applications vary in size and complexity, from simple identification of bar-codes to more complex schemes for remotely storing UO 3 drums. Some are high speed and highly repetitive, whereas others are low speed but require high precision. In this paper the authors outline a selection of current applications. (UK)

  1. Remote viewing system development in BNFL

    International Nuclear Information System (INIS)

    Case, D.R.; Garlick, D.R.; Crawford, G.; Montgomerie, J.

    1996-01-01

    The application of imaging systems to BNFL's plants is primarily provided by the Company's Engineering Group. Many systems have been developed for active service and several new developments are currently in an advanced stage of implementation. BNFL has acquired extensive experience of remote viewing from a series of projects undertaken for the Sellafield site in West Cumbria. Applications vary in size and complexity, from simple identification of bar-codes to more complex schemes for remotely storing UO 3 drums. Some are high speed and highly repetitive, whereas others are low speed but require high precision. In this paper the authors shall outline a selection of current applications. (Author)

  2. Continuous improvement of the BNFL transport integrated management system

    International Nuclear Information System (INIS)

    Hale, J.A.

    1998-01-01

    The integrated Management System of BNFL Transport and Pacific Nuclear Transport Limited (PNTL) is subject to continuous improvement by the application of established improvement techniques adopted by BNFL. The technique currently being used is the application of a Total Quality Management (TQM) philosophy, involving the identification of key processes, benchmarking against existing measures, initiating various improvement projects and applying process changes within the Company. The measurement technique being used is based upon the European Foundation for Quality Management Model (EFQM). A major initiative was started in 1996 to include the requirements of the Environmental Management Systems standard ISO 14001 within the existing integrated management system. This resulted in additional activities added to the system, modification to some existing activities and additional training for personnel. The system was audited by a third party certification organisation, Lloyds Register Quality Assurance (LRQA), during 1997. This paper describes the arrangements to review and update the integrated management system of BNFL Transport and PNTL to include the requirements of the environmental standard ISO 14001 and it also discusses the continuous improvement process adopted by BNFL Transport. (authors)

  3. Thermal fuel research and development facilities in BNFL

    International Nuclear Information System (INIS)

    Roberts, V.A.; Vickers, J.

    1996-01-01

    BNFL is committed to providing high quality, cost effective nuclear fuel cycle services to customers on a National and International level. BNFL's services, products and expertise span the complete fuel cycle; from fuel manufacture through to fuel reprocessing, transport, waste management and decommissioning and the Company maintains its technical and commercial lead by investment in continued research and development (R and D). This paper discusses BNFL's involvement in R and D and gives an account of the current facilities available together with a description of the advanced R and D facilities constructed or planned at Springfields and Sellafield. It outlines the work being carried out to support the company fuel technology business, to (1) develop more cost effective routes to existing fuel products; (2) maximize the use of recycled uranium, plutonium and tails uranium and (3) support a successful MOX business

  4. BNFL's new spent fuel transport flask - Excellox 8

    International Nuclear Information System (INIS)

    McWilliam, D.S.

    2002-01-01

    Since British Nuclear Fuels plc (BNFL) was formed in 1971 its transport service has safely moved spent light water reactor fuel from many locations abroad to its fuel handling plants at Sellafield in the UK. To support this business a number of types of flasks have been designed and used. One of the types used has been the Excellox family of water-filled flasks. To support future business opportunities a new flask, designed to meet the requirements of the new IAEA transport regulations TS-R-1 (ST-1, Revised), has been developed. The flask will be a type B(U)F. This new flask design will maximise fuel carrying capacity to minimise transport costs. The design capacity of the new Excellox 8 flask is to be 12 pressurised water reactor or 32 boiling water reactor fuel assemblies. The objective of this BNFL project is to provide another economic spent nuclear fuel transport system, in support of BNFL transport business. (author)

  5. The evolution of waste management processes and technologies in BNFL

    International Nuclear Information System (INIS)

    Asquith, R.W.; Fairhall, G.A.

    1997-01-01

    The treatment of wastes arising from BNFL''s nuclear fuel cycle operations can be traced through a number of phases. The first was the development of vitrification and cementation for fresh arisings. Plants utilising these technologies are now in operation. To handle the mixed, heterogeneous intermediate level wastes, retrieval, segregation and robust treatment processes are at an advanced stage of development, with all plants to be operational from 2002. BNFL is focusing attention on reducing waste management lifetime costs including reducing waste volumes of source. Technologies aimed at significant reductions are now being developed. The final phase, now in progress, recognizes the need for an integrated approach to advanced fuel cycle processes which incorporates BNFL''s holistic concept. (author)

  6. The evolution of waste management processes and technologies in BNFL

    International Nuclear Information System (INIS)

    Asquith, R. W.; Fairhall, G. A.

    1997-01-01

    The treatment of wastes arising from BNFL's nuclear fuel cycle operations can be traced through a number of phases. The first was the development of vitrification and cementation for fresh arising and plants are now in operation. To handle the mixed, heterogeneous intermediate level wastes, retrieval, segregation and robust treatment processes are at an advanced stage of development, with all plants to be operational from 2002. BNFL is focusing attention on reducing waste management lifetime costs including reducing waste volumes of source. Technologies aimed at significant reductions are now being developed. The final phase, now in progress, recognizes the need for an integrated approach to advanced fuel cycle processes which incorporates BNFL holistic concept. (author) 6 refs., 1 fig

  7. EDRP public local inquiry, UKAEA/BNFL precognition on: UKAEA/BNFL policy in relation to EDRP

    International Nuclear Information System (INIS)

    Allardice, R.H.

    1986-01-01

    The policy of the UKAEA and BNFL, for the design and construction of a fast reactor fuel reprocessing plant, and how it relates to UK Government policy for the development of the fast reactor system in collaboration with other European countries, is described. ((U.K.)

  8. BNFL and environmental care

    International Nuclear Information System (INIS)

    1992-01-01

    British Nuclear Fuel plc (BNFL) acknowledge a duty of care for the environment and aims to reduce the effects of its activities on the environment to as low as reasonably practicable. Its environmental policy statement is presented and its approach, investment policies and activities to implement this policy are outlined. The activities include energy efficiency, recycling, surveillance and research, conservation and open information. (UK)

  9. Progress on BNFL's response to three reports issued by HSE on 18 February 2000. February 2001

    International Nuclear Information System (INIS)

    2001-02-01

    On 18 February 2000 the Health and Safety Executive (HSE) published three reports Refs 1,2 and 3 relating to the work of its Nuclear Installations Inspectorate (NII) in the regulation of the BNFL Sellafield site. These reports were: An investigation into the falsification of pellet diameter data in the MOX demonstration facility (MDF) at the BNFL Sellafield site and the effect of this on the safety of MOX fuel in use; HSE team inspection of the control and supervision of operations at BNFL's Sellafield site; The Storage of Liquid High Level Waste at BNFL Sellafield - an updated review of safety. The publication of the reports created significant interest and led to major changes in the management of the company. This report provides an update on the position reached by the Nil in its consideration of BNFL's responses to the recommendations from the three reports one year on from their publication. Overall we are encouraged by the vigour and commitment that BNFL has given to addressing issues raised by all three reports. (i) MDF Data Falsification Report: All recommendations associated with the MDF Data Falsification Report have been satisfactorily addressed and ''closed out''. We will regulate the restart of MDF, now a development facility, in the same manner as any other plant on the Sellafield site and we have required BNFL to submit a re-commissioning safety report. (ii) Control and Supervision Report: The company has taken significant action to address the concerns identified in our report on the Team Inspection into the control and supervision at Sellafield. The BNFL Board has been restructured, and the Sellafield site management reorganised to provide a single individual who is responsible for operations and safety of the site. Greater clarity of roles and responsibilities have been identified and staffing at Sellafield has increased. A programme to ensure a ''conscious compliance'' culture has started and independent inspectors within BNFL and compliance

  10. Implementing knowledge management in BNFL - A case study

    International Nuclear Information System (INIS)

    Grant, G.E.

    2004-01-01

    This paper describes the work that has been done within BNFL Environmental Services over the past 18 months to develop and implement a Knowledge Management framework within the business. The paper provides an overview of the approach used, lessons learnt and achievements to date. The conclusion is that the approach has delivered a framework that is scaleable and repeatable in alignment with the business strategy and that the required change in behaviour has started. The BNFL Environmental Services KM Team is now focussing its efforts on revising the framework for application in the new British Nuclear Group Project Services business. The short term goals are to embed Knowledge Management in business processes and to facilitate the creation of dynamic communities that will support the formation of the new business. (author)

  11. How BNFL develops business in the States

    International Nuclear Information System (INIS)

    Langley, R.A.

    1991-01-01

    The US environmental restoration and waste management business is an expanding market. BNFL has developed a strategy designed to build a US-based business while taking into account the many barriers to market entry and participation. The elements of this strategy (market understanding, communications, flexibility, niche market, selectivity, teaming and cost recovery) are briefly explained

  12. The reasons behind BNFL's corporate plan

    International Nuclear Information System (INIS)

    Holthorp, J.

    1981-01-01

    BNFL's Pound3000 million investment programme over the next ten years is described and explained. Major projects are the thermal oxide reprocessing plant (THORP), and renovation and improvement of the Magnox reprocessing plant and its associated highly active storage tanks. Other developments include a site ion exchange effluent plant (SIXEP), a vitrification plant, expansion of the centrifuge plant and upgrading of the fuel element fabrication facilities. (U.K.)

  13. Safety audit of BNFL Sellafield 1986

    International Nuclear Information System (INIS)

    1986-01-01

    The BNFL Sellafield site involved is the complex of buildings concerned with reprocessing spent nuclear fuel from the UK Magnox reactors. It includes facilities for the receipt and storage underwater of spent fuel from the power stations, the subsequent chemical separation of re-usable elements of uranium and plutonium from the radioactive waste, storage of the more radioactive of these wastes on the site and discharge to sea or atmosphere, or disposal at the nearby Drigg site of those wastes which are of very low-radioactive content. The audit (conducted in 1986) was undertaken to establish the physical state of the plant, to investigate the management policies and priorities and the supporting advisory structure and to determine the cause and severity of incidents (eg leaks) by a comprehensive study of those occuring since 1979. Some buildings have been studied in more detail than others. Volume 1 of the audit report covers details of how the audit was planned and carried out, the engineering audit, a review of procedures, an analysis of incidents, the findings as to the actions that need to be taken by BNFL, a general summary and the conclusions. Volume 2 contains more technical and detailed papers relating to the inspection on which the judgements presented in Volume 1 are based. (U.K.)

  14. BNFL's experience in the sea transport of irradiated research reactor fuel to the USA

    International Nuclear Information System (INIS)

    Hudson, I.A.; Porter, I.

    2000-01-01

    BNFL provides worldwide transport for a wide range of nuclear materials. BNFL Transport manages an unique fleet of vessels, designed, built, and operated to the highest safety standards, including the highest rating within the INF Code recommended by the International Maritime Organisation. The company has some 20 years of experience of transporting irradiated research reactor fuel in support of the United States' programme for returning US obligated fuel from around the world. Between 1977 and 1988 BNFL performed 11 shipments of irradiated research reactor fuel from the Japan Atomic Energy Research Institute to the US. Since 1997, a further 3 shipments have been performed as part of an ongoing programme for Japanese research reactor operators. Where possible, shipments of fuel from European countries such as Sweden and Spain have been combined with those from Japan for delivery to the US. (author)

  15. Application of the double-contingency principle within BNFL

    International Nuclear Information System (INIS)

    Strafford, P.I.D.

    1995-01-01

    Historically, the double-contingency principle has been used for criticality assessment within British Nuclear Fuels plc (BNFL). This paper outlines what is understood by the double-contingency principle to illustrate how it is applied in criticality safety assessments and to highlight various problem areas that are encountered and, where possible, how they might be solved

  16. Joint BNFL/DoE ILW development programme

    International Nuclear Information System (INIS)

    Page, R.J.; James, R.A.; Higson, S.G.

    1985-01-01

    It is proposed by BNFL that ILWs resulting from reprocessing operations at Sellafield will be incorporated in a matrix which will produce a waste product suitable for transport, storage and disposal. The broad objective of the programme is therefore to evaluate potential waste products arising from treatment of ILWs and to develop appropriate techniques which could be used to check the quality of the finished waste product. (author)

  17. Flexibility of the BNFL dry storage systems

    International Nuclear Information System (INIS)

    Dickson, R.M.

    1999-01-01

    To widen its range of spent fuel management services, BNFL entered the fuel storage market in 1995; entry was by acquisition rather than internal product development. The need for a transportable product was identified very early, but represents only the first phase of a philosophy of continuous improvement. Strong synergy exists between the new business area and existing fuel handling and transportation expertise, which has been of considerable assistance to the new business. (author)

  18. Waste disposal developments within BNFL

    International Nuclear Information System (INIS)

    Johnson, L.F.

    1989-01-01

    British Nuclear Fuels plc has broad involvement in topics of radioactive waste generation, treatment, storage and disposal. The Company's site at Drigg has been used since 1959 for the disposal of low level waste and its facilities are now being upgraded and extended for that purpose. Since September 1987, BNFL on behalf of UK Nirex Limited has been managing an investigation of the Sellafield area to assess its suitability for deep underground emplacement of low and intermediate level radioactive wastes. An approach will be described to establish a partnership with the local community to work towards a concept of monitored, underground emplacement appropriate for each waste category. (author)

  19. BNFL annual report: review of the year

    International Nuclear Information System (INIS)

    Hill, J.

    1977-01-01

    This includes a review by Sir John Hill, chairman of the activities of British Nuclear Fuels Ltd. (BNFL) during the year 1977, as taken from its sixth annual report published in July 1977. Headings include: Financial results; Powers of the Nuclear Industry (Finance) Act 1977; Inflation accounting; Commissioning of the first full scale centrifuge enrichment plant at Capenhurst; Fuel manufacture and associated services; Fuel reprocessing; Electricity generation from Calder and Chapelcross; Public interest; and Staff. (U.K.)

  20. It tells you where we want to go and not where we've been[Future of BNFL marketing and advertising activities

    Energy Technology Data Exchange (ETDEWEB)

    Whittaker, Louise M [Corporate Affairs Manager, BNFL (United Kingdom)

    1995-07-01

    In summary, up to now, BNFL's current visual identity was, amongst other things, dated, fragmented, inconsistent and poorly maintained. Quite simply, the existing identity did NOT say where we were going - only where we had been. The research also revealed three interesting conclusions regarding BNFL as a company name. It was clearly a very strong brand but there was distinct confusion over the acronym BNFL and the full registered company name of British Nuclear Fuels plc. In addition, 'British' was felt to be too restrictive for a company focused upon a broad international marketplace and the word fuel implied we concentrate purely on the fuel cycle, dismissing our unrivalled achievements in areas, such as engineering, fluorochemicals and environmental clean-up. The solution was to promote the company as BNFL and de-emphasise the use of the full company name during all promotional activity. So, where did we go from here? We developed three options for testing. Firstly the existing BNFL logo, secondly a refined and more modem version of the existing BNFL logo and finally a complete change of logo. We were also keen to establish the strength of the three options in relation to other well known and respected identities.

  1. BNFL's application of computer aided engineering to 'THORP' thermal oxide reprocessing plant

    International Nuclear Information System (INIS)

    Hall-Wilton, M.J.

    1990-01-01

    BNFL are currently constructing facilities at Sellafield, Cumbria to reprocess thermal oxide fuel for U.K., European and Japanese utilities. Faced with a 3.5bn pound capital program to provide new facilities at Sellafield, BNFL took the opportunity to embrace the new computer aided engineering technologies then emerging in 1981. To give some idea of the commitment made by BNFL to the above many millions of pounds has been invested in hardware, and more on software and people. The 'THORP' (Head End and Chemical Separation Plant) project represents 1.5bn pounds. The introduction of computer aided engineering has provided a clash free design with full assurance that all materials and components used are compatible. Planning in the design offices in conjunction with an experienced construction management team enables the sequence of piping installation to be determined long before the construction teams enter the work area. This planning aspect has been significantly improved by using EVS (Enhanced Visualisation System). The use of supercomputing graphics facilities is stimulating demands from areas of engineering who have previously not sought to use magnetic data from a variety of sources. The result is mainly due to the data being easily accessible to users who have very little computing experience. (N.K.)

  2. Review of BNFL's operational experience of wet type flasks

    International Nuclear Information System (INIS)

    McWilliam, D.S.

    2004-01-01

    BNFL International Transport's operational experience includes shipping 6000te of spent fuel from Japan to Sellafield, through its dedicated terminal at Barrow, and to Cogema La Hague. This fuel was shipped under the PNTL (Pacific Nuclear Transport Ltd) banner for which BNFL is responsible. PNTL owned and operated a fleet of 5 ships for Japanese business and a fleet of 80 wet and 58 dry flasks, for the transport of Light Water Reactor (LWR) spent fuel, from both Pressurised Water Reactors (PWR) and Boiling Water Reactors (BWR). ''Wet'' or ''dry'' flask is the common terminology used to distinguish between spent fuel flasks transporting fuel where the fuel is immersed in water, or spent fuel flasks that have been drained of water and dried. This paper concentrates on the wet type of flask utilised to transport fuel to Sellafield, that is the Excellox type (including similar type NTL derivatives). It aims to provide a summary of operational experience during handling at power stations, shipment, unloading at reprocessors and from scheduled maintenance

  3. BNFL and environmental care. An introduction to our policy

    Energy Technology Data Exchange (ETDEWEB)

    1992-12-31

    British Nuclear Fuel plc (BNFL) acknowledge a duty of care for the environment and aims to reduce the effects of its activities on the environment to as low as reasonably practicable. Its environmental policy statement is presented and its approach, investment policies and activities to implement this policy are outlined. The activities include energy efficiency, recycling, surveillance and research, conservation and open information. (UK).

  4. Implementation and operational experience of an integrated fuel information service at the BNFL THORP facility

    International Nuclear Information System (INIS)

    Robson, D.N.; Ramsden, P.N.

    1995-01-01

    BNFL's THORP Plant, which started active operations early in 1994, has contracts to reprocess 7000t(U) of fuel belonging to 33 customers in 9 countries in the UK, Europe and Japan during its first 10 years of operation. Contracts are in place or being negotiated, and further business sought after, with the expectation of extending THORP's operations well beyond the initial 10 years. An integrated data management service, for the fuel storage areas of BNFL's THORP Division, is being implemented to replace several, independent, systems. This Fuel Information Service (FIS) will bring the Nuclear Materials Accountancy and Safeguards Records together with the Operating Records into one database from which all Safeguards Reports will be made. BNFL's contractual and commercial data and technical data on the stored fuel, required to support the reprocessing business, will also be brought into the common database. FIS is the first stage in a project to integrate the Materials Management systems throughout the THORP nuclear recycling business including irradiated fuel receipt and storage, reprocessing and storage of products, mixed oxide fuel manufacture and the conditioning and storage of wastes

  5. The Environmental Agency's Assessment of the Post-Closure Safety Case for the BNFL DRIGG Low Level Radioactive Waste Disposal Facility

    International Nuclear Information System (INIS)

    Streatfield, I. J.; Duerden, S. L.; Yearsley, R. A.

    2002-01-01

    The Environment Agency is responsible, in England and Wales, for authorization of radioactive waste disposal under the Radioactive Substances Act 1993. British Nuclear Fuels plc (BNFL) is currently authorized by the Environment Agency to dispose of solid low level radioactive waste at its site at Drigg, near Sellafield, NW England. As part of a planned review of this authorization, the Environment Agency is currently undertaking an assessment of BNFL's Post-Closure Safety Case Development Programme for the Drigg disposal facility. This paper presents an outline of the review methodology developed and implemented by the Environment Agency specifically for the planned review of BNFL's Post-Closure Safety Case. The paper also provides an overview of the Environment Agency's progress in its on-going assessment programme

  6. The transport of radioactive materials - a BNFL viewpoint

    International Nuclear Information System (INIS)

    Miller, M.L.

    1993-01-01

    Following a brief review of the international regulatory framework and its historical development, the principal priorities for the design and operation of a reliable transport system are defined and commented upon. The paper examines the reasons for the increased pressures upon international nuclear transport. It is argued that a key factor is the gap between 'actual' and 'publicly perceived' safety. BNFL's approach to achieving and demonstrating acceptable safety standards is described and proposals for broader international initiatives, with regard both to internal industry issues and external responses, are presented. (Author)

  7. Actinide chemistry: From test tube to billion dollar plant--A BNFL perspective

    International Nuclear Information System (INIS)

    Parkes, Peter

    2000-01-01

    British Nuclear Fuels (BNFL) is currently operating its third generation of nuclear plant for the management of irradiated nuclear fuel. Development for the fourth generation plant must meet requirements for processing higher burn-up fuel with lower unit costs, lower environmental impact, better process control, and more flexible control of actinides

  8. Research and technology programmes supporting waste management in BNFL

    International Nuclear Information System (INIS)

    Fairhall, G.A.; Horner, A.M.

    2000-01-01

    Waste Management is a major activity of BNFL in the UK and at various locations internationally. To support these activities extensive programmes of Research and Technology have been undertaken for many years. This involves practical studies involving active and non-active work at laboratory and pilot plant scale. Extensive use is also made of theoretical and modelling techniques. Current work is aimed at underpinning and improving current operations supporting the design and safety cases of new plant and addressing waste management activities of the future including decommissioning. (authors)

  9. BNFL Report Glass Formers Characterization

    Energy Technology Data Exchange (ETDEWEB)

    Schumacher, R.F.

    2000-07-27

    The objective of this task was to obtain powder property data on candidate glass former materials, sufficient to guide conceptual design and estimate the cost of glass former handling facilities as requested under Part B1 of BNFL Technical and Development Support. Twenty-nine glass forming materials were selected and obtained from vendors for the characterization of their physical properties, durability in caustic solution, and powder flow characteristics. A glass former was selected based on the characterization for each of the ten oxide classes required for Envelope A, B, and C mixtures. Three blends (A, B, and C) were prepared based on formulations provided by Vitreous State Laboratory and evaluated with the same methods employed for the glass formers. The properties obtained are presented in a series of attached Tables. It was determined that five of the ten glass formers, (kyanite, iron oxide, titania, zircon, and zinc oxide) have the potential to cause some level of solids f low problems. The problems might include arching or ratholing in the silo/hopper. In addition, all of the blends may require consideration for their handling.

  10. BNFL Report Glass Formers Characterization

    International Nuclear Information System (INIS)

    Schumacher, R.F.

    2000-01-01

    The objective of this task was to obtain powder property data on candidate glass former materials, sufficient to guide conceptual design and estimate the cost of glass former handling facilities as requested under Part B1 of BNFL Technical and Development Support. Twenty-nine glass forming materials were selected and obtained from vendors for the characterization of their physical properties, durability in caustic solution, and powder flow characteristics. A glass former was selected based on the characterization for each of the ten oxide classes required for Envelope A, B, and C mixtures. Three blends (A, B, and C) were prepared based on formulations provided by Vitreous State Laboratory and evaluated with the same methods employed for the glass formers. The properties obtained are presented in a series of attached Tables. It was determined that five of the ten glass formers, (kyanite, iron oxide, titania, zircon, and zinc oxide) have the potential to cause some level of solids f low problems. The problems might include arching or ratholing in the silo/hopper. In addition, all of the blends may require consideration for their handling

  11. Types of organic materials present in BNFL intermediate level waste streams

    International Nuclear Information System (INIS)

    Barlow, P.

    1988-01-01

    This presentation lists the constituents present in BNFL intermediate-level radioactive wastes. The inorganic and organic components are listed and there is a detailed analysis of the plutonium contaminated materials in terms of proportion of combustible and non-combustible content, up to the year 2000. A description of the Waste Treatment Complex at Sellafield is presented. The research programme for leach testing, sorption and solubility testing and decomposition of organic matter was outlined. (U.K.)

  12. BNFL's experience in preparing and implementing radiation protection programmes for the control of exposure to workers involved with the international transport of nuclear cargoes

    International Nuclear Information System (INIS)

    Billing, D.

    2004-01-01

    BNFL International Transport have successfully developed appropriate Radiation Protection Programmes for their business. The business supports BNFL's worldwide Nuclear Fuel Services with key customer bases in Europe, Japan and the UK, utilising marine, rail and road modal transports. Experience in the business spans over 4 decades. The preparation of RPP's for each aspect of its operations has been made relatively straight forward in that the key elements within the internationally recognised model RPP (by WNTI) were already in place in BNFL's procedures to satisfy current National UK and International Regulations. Arrangements are supported by Management systems which comply with International Standards for Quality Assurance. Exposure to key worker groups continues to be within Category 1 (less than 1mSv/y) of the IAEA Transport Regulations TS-R-1 (ST-1 revised)

  13. Seismic technology of nuclear fuel cycle facilities: A view of BNFL's approach and methods

    International Nuclear Information System (INIS)

    Morris, I.R.

    2001-01-01

    The approach BNFL employs in the seismic qualification of its nuclear fuel cycle facilities is described in this paper. The overall seismic qualification process from design to installation and commissioning is considered. The approach for new facilities, such as the Sellafield Mixed Oxide Fuel Plant and Windscale Vitrification Plant Line 3 currently under construction, is examined. (author)

  14. Refurbishment of the BNFL Magnox reprocessing plant

    International Nuclear Information System (INIS)

    Carr, V.M.; Edgar, R.

    1998-01-01

    The Magnox Reprocessing Plant was commissioned in 1964. Since then it has reprocessed more than 35,000 t of irradiated uranium metal fuel. The plant is subject to routine shutdowns to allow maintenance and project work to be undertaken. During the 1997 shutdown the opportunity was taken to replace several life limiting parts of the plant to ensure Magnox reprocessing capability well beyond the year 2010. This shutdown was the largest and most complex undertaken by Magnox Reprocessing, with a total committed value of 130 million UK pounds, 17.5 million UK pounds committed in the shutdown itself and the balance on installation, design and procurement preparing for the shutdown. The work was completed within safety targets, to programme and within budget. The lessons learned and experience gained have been fed into the methodologies and procedures for planning future project and shutdown work within BNFL. This report is part of the output from this process of continually improving performance. (author)

  15. The development of quality assurance systems for radioactive waste at BNFL Sellafield

    International Nuclear Information System (INIS)

    Lake, M.W.

    1989-01-01

    BNFL reprocesses spent fuel as Sellafield, in West Cumbria, where it is a site licence requirement for formal QA arrangements to be established in respect of nuclear safety related plant. The forms of radioactive waste which are generated on site: HLW, ILW and LLW are made up of arisings which can be solid, liquid or gaseous. This paper discusses how implementation of the company's QA policy has been achieved by formally documenting and establishing the controls needed to manage plant, processes and people

  16. The storage of liquid high level waste at BNFL, Sellafield. Addendum to February 2000 report

    International Nuclear Information System (INIS)

    2001-08-01

    On 18 February 2000 the Health and Safety Executive (HSE) published a report on the work of its Nuclear Installations Inspectorate (NIl) in regulating the storage of liquid high level waste at the BNFL Sellafield site. Within the report NIl gave two undertakings. One was to publish an addendum around 1 year later covering its assessment of the new safety case for the storage plant and the second was to publish a further addendum when progress had been made with options studies for reducing the stocks of liquid high level waste (HLW), also referred to as highly active liquor (HAL), to a buffer level. A progress report was published in February 2001 which included a summary of the assessment of the new safety case and NIl's regulatory action to enforce liquid HLW stock reductions. This addendum provides a more detailed update on the position reached based on consideration of BNFL's responses to the recommendations from the February 2000 HLW report since its publication. It embodies the two addenda referred to above integrated into a single document for publication

  17. Internationalisation of the BNFL fuel and waste treatment plant designs the challenges and benefits

    International Nuclear Information System (INIS)

    Hall, M.; Lomax, J. D.

    1995-01-01

    Since the late 1970's BNFL has considerably expanded its range of fuel cycle plants, involving an investment of over US$7.5bn (55bn Won). This has included significant development of its Sellafield site with a wide variety of plants and processes to deal with spent fuel and development of its fuel fabrication facilities at the Spring fields Site. In contrast to reactors, fuel plants are constructed infrequently and it is therefore crucial to 'get it right first time'. The achievement of high levels of safety has been an important factor in the development of these facilities. BNFL has applied safety criteria which are as stringent as any other international safety criteria in terms of the extent to which radiation doses to plant workers and people off-site are minimised from both routine operations and possible fault conditions. Because the plant designs are established and supported by robust safety cases they are capable of being licensed overseas. The benefits of this are lower financial risk and shorter project timescales, due to avoiding the high design and safety case development costs (typically of the order of 20% of project cost) which are incurred in the production of a 'first of a kind' design. This paper briefly discusses the role of safety cases in the UK licensing process and the principle safety standards which are applied to BNFL plants and shows how they achieve high levels of safety by comparing them with equivalent IAEA and US based standards. It illustrates how the plants meet or exceed these safety standards by using specific data from existing safety cases supported by operational data where applicable. It discusses some of the important features of the UK approach to safety and licensing and emphasises the need to examine safety provisions on a case by case basis rather than adopting a prescriptive approach to implementing design provisions if cost effectiveness is to be achieved

  18. Alpha-emitting 'hot particles' in the vicinity of BNFL Sellafield, Cumbria

    International Nuclear Information System (INIS)

    Whittall, A.J.; Tossell, P.J.

    2000-01-01

    In a survey of environmental samples in the vicinity of BNFL Sellafield, two alpha-emitting radioactive particles were found in samples of grass. One particle appears to be of mineral origin, the other was not definitively identified, but may be a fragment of fuel cladding. Conservative estimates of the activities of these particles are very low. The abundance of radioactive particles in the terrestrial food chain appears to be low, with no evidence for any alpha-emitting hot particles in foodstuffs for consumption by humans. Results suggest that there is no significant dose to man through inhalation or ingestion pathways. (author)

  19. BNFL Report Glass Formers Characterization

    Energy Technology Data Exchange (ETDEWEB)

    Schumacher, R.F.

    2000-07-27

    The objective of this task was to obtain powder property data on candidate glass former materials, sufficient to guide conceptual design and estimate the cost of glass former handling facilities as requested under Part B1 of BNFL Technical and Development Support. Twenty-nine glass forming materials were selected and obtained from vendors for the characterization of their physical properties, durability in caustic solution, and powder flow characteristics. A glass former was selected based on the characterization for each of the ten oxide classes required for Envelope A, B, and C mixtures. Three blends (A, B, and C) were prepared based on formulations provided by Vitreous State Laboratory and evaluated with the same methods employed for the glass formers. The properties obtained are presented in a series of attached Tables. It was determined that five of the ten glass formers, (kyanite, iron oxide, titania, zircon, and zinc oxide) have the potential to cause some level of solids f low problems. In addition, all of the blends may require consideration for their handling. A number of engineering considerations and recommendations were prepared based on the experimental findings, experience, and other process considerations. Recommendations for future testing are included. In conjunction with future work, it is recommended that a professional consultant be engaged to guide and assist with testing and design input.

  20. BNFL Report Glass Formers Characterization

    International Nuclear Information System (INIS)

    Schumacher, R.F.

    2000-01-01

    The objective of this task was to obtain powder property data on candidate glass former materials, sufficient to guide conceptual design and estimate the cost of glass former handling facilities as requested under Part B1 of BNFL Technical and Development Support. Twenty-nine glass forming materials were selected and obtained from vendors for the characterization of their physical properties, durability in caustic solution, and powder flow characteristics. A glass former was selected based on the characterization for each of the ten oxide classes required for Envelope A, B, and C mixtures. Three blends (A, B, and C) were prepared based on formulations provided by Vitreous State Laboratory and evaluated with the same methods employed for the glass formers. The properties obtained are presented in a series of attached Tables. It was determined that five of the ten glass formers, (kyanite, iron oxide, titania, zircon, and zinc oxide) have the potential to cause some level of solids f low problems. In addition, all of the blends may require consideration for their handling. A number of engineering considerations and recommendations were prepared based on the experimental findings, experience, and other process considerations. Recommendations for future testing are included. In conjunction with future work, it is recommended that a professional consultant be engaged to guide and assist with testing and design input

  1. The evolution of a LIMS (laboratory information management system). [Chemical analyses at BNFL

    Energy Technology Data Exchange (ETDEWEB)

    Anon.

    1992-04-01

    Changes in the world and United Kingdom markets for nuclear fuels during the 1990s have prompted British Nuclear Fuels (BNFL) to maximise cost effectiveness in its Chemical and Metallurgical Services department. A laboratory information management system (LIMS) was introduced in order to keep records of analytical techniques and equipment up to date by coordinating various computer systems. Wherever possible automated systems have replaced traditional, labour intensive techniques. So successful has the LIMS system been, that the team now hopes to expand into expert systems. (UK).

  2. An overview of the QA principles and practices applied to the design, construction, commissioning and bringing into service of an intermediate-level waste encapsulation plant at BNFL Sellafield

    International Nuclear Information System (INIS)

    Lake, M.W.

    1989-01-01

    This paper describes the arrangements adopted by BNFL to ensure that a new ILW Encapsulation Plant Project is brought from project conception through to commercial operation within a QA system which complies with the appropriate standards and includes the following: the role of the QA function within BNFL Engineering; the organization of the commissioning process into a formal QA system to satisfy the requirements of the Nuclear Site License; and the preparatory work carried out by the Site's QA organization in the management of R and D, the selection and evaluation of raw material suppliers, and the bringing together of large numbers of particularly complex activities and differing organizations to provide assurance of quality of the ultimate product. The author presents an explanation of the arrangements adopted by BNFL to monitor the achievements of quality objectives and to ensure a comprehensive audit programme is maintained

  3. BNFL Sellafield assessment of public radiation exposure due to liquid effluents from fuel reprocessing

    International Nuclear Information System (INIS)

    Hunt, G.J.

    1982-01-01

    Individual (critical group) doses resulting from liquid discharges from the British Nuclear Fuels Limited (BNFL) Sellafield Works have been derived in a form normalised to unit radionuclide discharge rates. This has been done for the purpose of providing a basis for predicting doses in the event of nuclear fuel from a future Sizewell 'B' power station being reprocessed. These doses would have to be reviewed in the light of prevailing circumstances at the time when the actual discharges are known. (author)

  4. Monitoring of beach contamination following an incident at BNFL, Sellafield, Cumbria in November 1983

    International Nuclear Information System (INIS)

    1985-01-01

    This report jointly produced by RCI/DOE and MAFF presents for the period from November 1983 to July 1984: 1) the monitoring programmes and techniques used by BNFL, DOE and MAFF; 2) the results of the monitoring programmes; 3) actions taken as a consequence of the monitoring results; 4) an outline of the position at the end of July 1984 when the Secretary of State for Environment announced, after consultation with MAFF, the DHSS and NRPB, withdrawal of advice to avoid unnecessary use of the beaches. (UK)

  5. Demonstration and Optimization of BNFL's Pulsed Jet Mixing and RFD Sampling Systems Using NCAW Simulant

    International Nuclear Information System (INIS)

    Bontha, J.R.; Golcar, G.R.; Hannigan, N.

    2000-01-01

    The BNFL Inc. flowsheet for the pretreatment and vitrification of the Hanford High Level Tank waste includes the use of several hundred Reverse Flow Diverters (RFDs) for sampling and transferring the radioactive slurries and Pulsed Jet mixers to homogenize or suspend the tank contents. The Pulsed Jet mixing and the RFD sampling devices represent very simple and efficient methods to mix and sample slurries, respectively, using compressed air to achieve the desired operation. The equipment has no moving parts, which makes them very suitable for mixing and sampling highly radioactive wastes. However, the effectiveness of the mixing and sampling systems are yet to be demonstrated when dealing with Hanford slurries, which exhibit a wide range of physical and theological properties. This report describes the results of the testing of BNFL's Pulsed Jet mixing and RFD sampling systems in a 13-ft ID and 15-ft height dish-bottomed tank at Battelle's 336 building high-bay facility using AZ-101/102 simulants containing up to 36-wt% insoluble solids. The specific objectives of the work were to: Demonstrate the effectiveness of the Pulsed Jet mixing system to thoroughly homogenize Hanford-type slurries over a range of solids loading; Minimize/optimize air usage by changing sequencing of the Pulsed Jet mixers or by altering cycle times; and Demonstrate that the RFD sampler can obtain representative samples of the slurry up to the maximum RPP-WTP baseline concentration of 25-wt%

  6. BNFL experience of public engagement: expectations for risk policies

    International Nuclear Information System (INIS)

    Coates, R.

    2002-01-01

    BNFL operates a range of nuclear facilities covering fuel fabrication, power plants, reprocessing operations and decommissioning activities. The paper explores the company's experiences in public communication and stakeholder involvement relating to nuclear and radiation issues. These range from the early establishment of Local Liaison Committees linked to each of the sites, through the introduction of public visitor centres at sites, the extensive involvement in formal consultation exercises, to the more recent involvement of a wide range of stakeholders in a process of dialogue to aid the decision making of the company on environmental affairs. In these activities there are some common themes which the company and the wider nuclear industry believes should be consistently brought to the attention of stakeholders and decision makers in order to support a balanced consideration of these issues. How, and indeed whether (and to what extent) these aspects are then factored into the overall decision process is subject to a changing dynamic within the developing expectations of society for a more transparent involvement in technological issues. (author)

  7. BNFL's advertising phase II: 'We understand that you are a successful scientific company, but what do you actually do?'

    International Nuclear Information System (INIS)

    Haskins, Louise

    1998-01-01

    Full text: Last year, I presented a case study about the development of BNFL's advertising strategy and the challenges which we overcame since its launch in 1995. The case study this year will follow the progress of the strategy's second phase. It will begin by reiterating the role of advertising in the communications mix and the distinct part we believe it plays in building and retaining a strong corporate reputation amongst influential audiences within the UK. Our advertising to date has aimed to define BNFL's role in the nuclear sector and so detach the company from the contentious debate which surrounds the nuclear industry in general. The case study will briefly summarise how effective we have been in achieving this objective through the first phase of television and press advertising. The presentation will concentrate, in particular, on the development of the second phase which has involved the production of a new television advertisement and a press and poster advertisement. Having introduced the key characteristics of the company to the UK population during the first phase through describing key scientific achievements, phase two concentrates on BNFL's core activity - recycling nuclear fuel. The presentation will outline the various development phases including concept research, our tough negotiations with the UK's advertising regulatory bodies (the Broadcast Advertising Clearance Centre (BACC) and the Independent Television Commission (ITC) through to final production, testing and media scheduling. Generating positive attribution amongst the UK population is obviously the key success indicator. Equally, we believe that it is imperative to share such communications activity with another key stakeholder - our own employees. The case study will outline the phase of internal negotiations and substantiation through to the methods we adopted to ensure that employees saw the television advertisement before the UK population at large. The campaign was launched on

  8. BNFL pushes fuel production into the 21st century

    International Nuclear Information System (INIS)

    Odell, Mark.

    1992-01-01

    When the New Oxide Fuels Complex (NOFC) begins commercial production in May 1995, its operators will have one of the world's most advanced fuel production facilities, designed to compete on international markets by using the latest technology and exploiting economies of scale. British Nuclear Fuels (BNFL's) multi-million pound investment in its Springfields fuel operation is a bold move, aimed at gaining a greater share of the oxide fuel business worldwide. The complex is designed to achieve fuel cost savings and increase the site's manufacturing capacity. The building itself will bring all current fuel production operations at Springfields under one roof, merging five plants into one. Automation will ensure further economies through the use of automated guided vehicles (AGVs) for product transfer, walking beam furnaces for pellet sintering and on-line inspection and handling of pellets and pins. The use of a binderless route for AGR (advanced gas-cooled reactor) fuel means much of the manufacturing process for both AGR and PWR (pressurised water reactor) fuels will proceed on a single line, thereby reducing the fixed costs of both fuels. Two other features which contribute to cost savings are production flexibility which allows both non-irradiated and oxide reprocessed materials to follow the same route and longer kilns which increase the throughput. It is estimated that overall NOFC will reduce fuel manufacturing costs by some 40%. (author)

  9. Developments in safety and operations culture in BNFL's thorp reprocessing plant, Sellafield, Cumbria

    International Nuclear Information System (INIS)

    Kett, P.J.

    2000-01-01

    One of the best descriptions of Culture is 'how we do things around here'. In a stable organisation it is extremely difficult to change any type of culture, whether it is an operations, customer service or safety culture. To change culture one of two elements are essential. There must be either a significant external pressure felt by all in the organisation or a change in senior management, with authority to set a new direction for the organisation. BNFL had a unique opportunity through the commissioning and operation of the Thorp Reprocessing Plant at Sellafield to shape a new Safety and Operations Culture. Both the key elements for change were present. Thorp was a high profile flagship plant that had attracted multinational investment. It incorporated new technology. The workforce had volunteered to operate the plant. A strong senior management team was specially selected. The plant was being commissioned in an environment where there was significant opposition by 'anti nuclear' groups. It was essential to both BNFL and the wider international nuclear community that Thorp was commissioned and operated safely. A strong operating culture was developed with safety as the corner stone. The culture comprises three key components. Rigorous plant safety case and risk assessments before work commences and modifications to the plant occur; A high level of involvement by all levels of the workforce in both operations and safety matters; Strong supportive leadership which does not allow safety standards to be compromised and encourages open debate on how to improve. During commissioning and early operation of Thorp the robustness of the Safety and Operations Culture was demonstrated. On several occasions, despite intense commercial pressure, operations were halted until the situation was resolved both technically and procedurally. This paper describes how the Safety and Operations Culture was developed. The key factors for success include recruitment, team selection

  10. Doses to Terrestrial Biota in the Vicinity of BNFL Sellafield, Cumbria, UK (invited paper)

    Energy Technology Data Exchange (ETDEWEB)

    Copplestone, D.; Johnson, M.S.; Jackson, D.; Jones, S.R

    2000-07-01

    Source terms and corresponding radionuclide activity concentrations in biota for {sup 134}Cs, {sup 137}Cs, {sup 238}Pu, {sup 239+240}Pu and {sup 241}Am have been assessed for three semi-natural ecosystems in the vicinity of BNFL Sellafield, Cumbria, UK. Estimates of absorbed doses (mGy.d{sup -1}) have been calculated. Doses to key indicator species, Oniscus asellus (detritivorous invertebrate), Carabus violaceous (predatory invertebrate) and Apodemus sylvaticus (granivorous wood mouse) are discussed with reference to the 1 mGy.d{sup -1} level, below which it is postulated that no observable effects on populations in a terrestrial ecosystem occur. Implications for the 'critical group' and 'reference model' approaches for a framework of radiological environmental protection are discussed. The need to assess the most highly exposed species is advanced. New research focused on the application of biomarker techniques as a mechanism for determining the interactions and effects of environmental contaminants on ecosystem structure and functioning is presented. (author)

  11. The management of change in BNFL's UK group with particular reference to the restructuring of the health and safety functions

    International Nuclear Information System (INIS)

    Brandwood, A.R.

    1996-01-01

    BNFL's UK group business involves reprocessing of uranium metal (Magnox) fuel, storage and dismantling of advanced gas rector (ceramic UO 2 ) fuel, waste treatment and storage, decommissioning and electricity generation. These activities are carried out at three sites in the North West corner of England and Southern Scotland: Sellafield - all activities, Chapelcross -electricity generation, Drigg - waste storage. Achieving fundamental change in a well established nuclear business which is highly regulated is possible and can bring large benefits. The keys to success are leadership and commitment from all senior managers, involvement of all stakeholders and communication. It is essential to involve the regulator as a stakeholder. (author)

  12. A new approach to the criticality safety assessment of PCM at BNFL Sellafield

    International Nuclear Information System (INIS)

    Darby, Sam; Kirkwood, Dave

    2003-01-01

    Plutonium Contaminated Material (PCM) arises as a solid waste on the Sellafield Site and is packaged into 200 litre drums which are placed into interim surface storage arrays. These wastes may also contain 235 U. The traditional approach to criticality safety has been based on ''worst-case'' reactivity modelling. This has recently led to a number of difficulties by implying that the 230 g (Pu + 235 U) drum limit is very important for criticality safety and the assay instruments used to demonstrate compliance with the limit need a high level of safety reliability. Also, the reliability and accuracy of the assay results of historical or legacy PCM became an issue. The new focus on substantiation of safety related equipment in BNFL has highlighted reliability shortfalls for the assay instruments. To overcome these shortfalls, additional operational practices on the PCM handling regimes were introduced to give increased confidence in the fissile assay results. These practices significantly delayed processing PCM waste stocks and resulted in significant additional operator dose uptake. Thus there were strong reasons to improve the existing approach. This paper describes a new approach to the criticality modelling of PCM. (author)

  13. Reactor decommissioning strategy: a new start for BNFL

    International Nuclear Information System (INIS)

    Woollam, P.; Nurden, P.

    2001-01-01

    The key points of BNFL Magnox Electric's revised waste management and reactor decommissioning strategy for the reactor sites are enlisted. Reactors will be defuelled as soon as practicable after shutdown. Predominantly Caesium contaminated plant will be dismantled when it is no longer needed. Cobalt contaminated plant such as boilers will remain in position until the reactors are dismantled, but appropriate decontamination technology will be regularly reviewed. All buildings except the reactor buildings will be dismantled as soon as practicable after they are no longer needed. Operational ILW, except some activated components, will be retrieved and packaged during the Care and Maintenance preparation period. All wastes will be stored on site, and handled in the long term in accordance with Government policy. Reactor buildings and their residual contents will be placed in a passive safe storage Care and Maintenance condition in a manner appropriate for the site. Contaminated land will be managed to maintain public safety. The reactors will be finally dismantled in a sequenced programme with a start date and duration to be decided at the appropriate time in the light of circumstances prevalent at that time. Currently, the Company is considering a sequenced programme across all sites, notionally beginning around 100 years from station shutdown, leading to a range of deferral periods. For provisioning purposes, the Company has costed a strategy involving reactor dismantling deferrals ranging from 85 to about 105 years in order to demonstrate prudent provisioning to meet its liabilities. A risk provision to reflect the potential for shorter deferral periods is included in the cost estimates. The end point for reactor decommissioning is site clearance and delicensing, based on the assumption that a reasonably practicable interpretation of the 'no danger' clause in the Nuclear Installations Act 1965 (as amended) can be developed. In line with Government policy, and taking

  14. The evolving UK strategy for the management of intermediate level waste to enable disposal to a deep geological repository - a UKAEA/BNFL/NIREX perspective

    International Nuclear Information System (INIS)

    Wratten, A.J.; Allan, D.F.; Palmer, J.D.

    1996-01-01

    The objective of this paper is to describe the development of BNFL's and UKAEA's strategies for managing Intermediate Level Waste (ILW) against the background of the evolving national strategy. The impact of the loss of the sea disposal route is addressed together with the challenge of designing waste conditioning plants in parallel with the evolving technical specification for the Nirex deep repository. What has been achieved and is Planned in terms of plant provisioning is described, together with the lessons that have been learned in striving to achieve optimum design solutions. (author)

  15. Analysis of the BFS-62 critical experiment. A report produced for BNFL (Joint European contribution)

    International Nuclear Information System (INIS)

    Newton, T.D.; Hosking, J.G.; Smith, P.J.

    2004-01-01

    A benchmark analysis for a hybrid UOX/MOX fuelled core of the BN-600 reactor was proposed during the first Research Co-ordination Meeting of the IAEA Co-ordinated Research Project 'Updated Codes and Methods to Reduce Calculational Uncertainties of LMFR Reactivity Effects'. Phase 5 of the benchmark focuses on validation of calculated sodium void coefficient distributions and integral reactivity coefficients by comparison with experimental measurements made in the critical facility BFS-62. The European. participation in Phase 5 of the benchmark analyses consists of a joint contribution from France (CEA Cadarache) and the UK (Serco Assurance Winfrith - sponsored by BNFL). Calculations have been performed using the ERANOS code and data system, which has been developed in the framework of the European collaboration on fast reactors. Results are presented in this paper for the sodium void reactivity effect based on calculated values of the absolute core reactivity. The spatial distribution of the void effect, determined using first order perturbation theory with the diffusion theory approximation, is also presented

  16. Changes in UO2 powder properties during processing via BNFL's binderless route

    International Nuclear Information System (INIS)

    Bromely, A.P.; Logsdon, R.; Roberts, V.A.

    1997-01-01

    The Short Binderless Route (SBR) has been developed for Mixed Oxide fuel production in BNFL's MOX Demonstration Facility (MDF) and the Sellafield MOX Plant (SMP). It is a compact process which enables good homogenisation of the Pu/U mixture and production of free flowing press feed materials. The equipment used to achieve this consists of an attritor mill to provide homogenization and a spheroidiser to provide press feed granules. As for other powder processes, the physical properties of the UO 2 powder can affect the different process stages and consequently a study of some of these effects has been carried out. The aim of the work were to gain a better understanding of the process, to consequently optimize press feed material quality and to also maintain powder hold-up levels in the equipment at a minimum. The paper considers the effects of milling processes on powder morphology and powder surface effects, on the granulation process and also on powder and granule bulk properties such as pour, tap and compaction densities. Results are discussed in terms of powder properties such as powder cohesivity, morphology and particle size. UO 2 powder derived from both the Integrated Dry Route (IDR) and the Ammonium Di-Uranate (ADU) Route are considered. Small (1 kg) scale work has been carried out which has been confirmed by larger (25 kg) scale trials. The work shows that IDR powder with differing morphologies and ADU powder can be successfully processed via the SBR route. (author). 4 figs, 4 tabs

  17. Aerial and liquid effluent treatment in BNFL's Thermal Oxide Reprocessing Plant (THORP)

    International Nuclear Information System (INIS)

    Hudson, P.I.; Buckley, C.P.

    1996-01-01

    British Nuclear Fuels plc (BNFL) completed construction of its Thermal Oxide Reprocessing Plant (THORP) at Sellafield in 1992, at a cost of pound 1,850M. After Government and Regulatory approval, active commissioning was initiated in January 1994. Since then, the whole of the plant has been progressively commissioned and moved towards full operational status. From the outset, the need to protect the workforce, the public and the environment in general from the plant's discharges was clearly recognised. The design intent was to limit radiation exposure of members of the general public to 'As Low as Reasonably Practicable' (ALARP). Furthermore no member of the most highly exposed (critical) group should receive an annual dose exceeding 50 microsieverts from either the aerial or marine discharge routes. This paper describes how the design intent has been met, concentrating mainly on aerial discharges. It describes the sub-division of the plant's ventilation system into a number of separate systems, according to the volume and source of the arising and the complexity of the treatment process. The dissolver off-gas, central off-gas, cell and building ventilation systems are described, together with the development programme which was undertaken to address the more demanding aspects of the performance specification. This ranged from small-scale experiments with irradiated fuel to inactive pilot plant trials and full-scale plant measurements. In addition wind tunnel tests were employed to assist dispersion modelling of the gases as they are discharged from the THORP stack. All the resulting information was then used, with the aid of mathematical models, in the design of an off-gas treatment system which could achieve the overall goal. (J.P.N.)

  18. A new model validation database for evaluating AERMOD, NRPB R91 and ADMS using krypton-85 data from BNFL Sellafield

    International Nuclear Information System (INIS)

    Hill, R.; Taylor, J.; Lowles, I.; Emmerson, K.; Parker, T.

    2004-01-01

    The emission of krypton-85 ( 85 Kr) from nuclear fuel reprocessing operations provide a classical passive tracer for the study of atmospheric dispersion. This is because of the persistence of this radioisotope in the atmosphere, due to its long radioactive halflife and inert chemistry; and the low background levels that result due to the limited number of anthropogenic sources globally. The BNFL Sellafield site in Cumbria (UK) is one of the most significant point sources of 85 Kr in the northern hemisphere, with 85 Kr being discharged from two stacks on the site, MAGNOX and THORP. Field experiments have been conducted since October 1996 using a cryogenic distillation technique (Janssens et al., 1986) to quantify the ground level concentration of 85 Kr. This paper reports on the construction of a model validation database to allow evaluation of regulatory atmospheric dispersion models using the measured 85 Kr concentrations as a tracer. The results of the database for local and regional scale dispersion are presented. (orig.)

  19. Metal recycling technology and related issues in the United States, a BNFL perspective

    International Nuclear Information System (INIS)

    Bradbury, P.; Dam, S.; Starke, W.

    1995-01-01

    Radioactively contaminated metallic materials comprise a large part of the potential waste products which result from nuclear facility repair, refurbishment, and decommissioning. United States Government (Departments of Energy and Defense) facilities, U.S. nuclear power plants, and other commercial nuclear fuel cycle facilities have large inventories of radioactive scrap metal which could be decontaminated and recycled into useful radioactive and non-radioactive products. Residual radioactivity and recycling criteria is needed to avoid the high cost of disposal and the waste of natural resources. In the United Kingdom, BNFL has decommissioned the gaseous diffusion plant at Capenhurst and has recycled a large fraction of the metallic scrap into the metals market. Other structural materials have also been released as uncontaminated scrap. U.K. release criteria for residual radionuclide contamination have been applied to these operations. A variety of techniques were utilized to size reduce large components, to remove radioactivity, and to survey and release these materials. These methods and the application of release criteria has a direct relationship to methods which would be applicable in the U.S. and in other countries. This paper will describe the specific U.K. technology and experience in the decontamination, recycle, and release of scrap metal. It will also describe the U.S. environment for metal recycle, including the volumes and levels of contamination, and the current and proposed release criteria. Comparisons will be presented between the U.S. and U.K., both in technology and methodology for recycle and in regulatory criteria for residual radioactivity and material release and for ultimate decommissioning. The paper will then provide suggested approaches and criteria for U.S. recycling and decommissioning. (author)

  20. UK regulatory perspective on the application of burn-up credit to the BNFL thorp head end plant

    International Nuclear Information System (INIS)

    Simister, D.N.; Clemson, P.D.

    2003-01-01

    In the UK the Health and Safety Executive, which incorporates the Nuclear Installations Inspectorate (NII), is responsible for regulation of safety on nuclear sites. This paper reports progress made in the application and development of a UK regulatory position for assessing licensee's plant safety caes which invoke the use of Burn-up Credit for criticality applications. The NII's principles and strategy for the assessment of this technical area have been developed over a period of time following expressions of interest from UK industry and subsequent involvement in the international collaborations and debate in this area. This experience has now been applied to the first main plant safety case application claiming Burn-up Credit. This case covers the BNFL Thermal Oxide Reprocessing Plant (THORP) dissolver at Sellafield, where dissolved gadolinium neutron poison is used as a criticality control. The case argues for a reduction in gadolinium content by taking credit for the burn-up of input fuel. The UK regulatory process, assessment principles and criteria are briefly outlined, showing the regulatory framework used to review the case. These issues include the fundamental requirement in UK Health and Safety law to demonstrate that risks have been reduced to as low as reasonably practicable (ALARP), the impact on safety margins, compliance and operability procedures, and the need for continuing review. Novel features of methodology, using a ''Residual Enrichment'' and ''Domain Boundary'' approach, were considered and accepted. The underlying validation, both of criticality methodology and isotopic determination, was also reviewed. Compliance was seen to rely heavily on local in-situ measurements of spent fuel used to determine ''Residual Enrichment'' and other parameters, requiring review of the development and basis of the correlations used to underpin the measurement process. Overall, it was concluded that the case as presented was adequate. Gadolinium reduction

  1. British Nuclear Fuels (Warrington)

    International Nuclear Information System (INIS)

    Hoyle, D.; Cryer, B.; Bellotti, D.

    1992-01-01

    This adjournment debate is about British Nuclear Fuels plc and the 750 redundancies due to take place by the mid-1990s at BNFL, Risley. The debate was instigated by the Member of Parliament for Warrington, the constituency in which BNFL, Risley is situated. Other members pointed out that other industries, such as the textile industry are also suffering job losses due to the recession. However the MP for Warrington argued that the recent restructuring of BNFL restricted the financial flexibility of BNFL so that the benefits of contracts won for THORP at Sellafield could not help BNFL, Risley. The debate became more generally about training, apprentices and employment opportunities. The Parliamentary Under-Secretary of State for Energy explained the position as he saw it and said BNFL may be able to offer more help to its apprentices. Long- term employment prospects at BNFL are dependent on the future of the nuclear industry in general. The debate lasted about half an hour and is reported verbatim. (U.K)

  2. Health and safety annual report 1988

    International Nuclear Information System (INIS)

    1989-01-01

    This report on health and safety provides a review of the impact of the Comapny's activities on its workforce, the public and the environment. New sections include safety auditing, emergency planning and health and safety research. BNFL operates five sites in north west England and southern Scotland. The head office and Engineering Design Centre is at Risley, near Warrington. Fuel is manufactured at Springfields near Preston, uranium is enriched for modern nuclear power stations at Capenhurst near Chester and spent fuel is reprocessed at Sellafield. BNFL also operate Calder Hall (Sellafield) and Chapelcross (Scotland) power stations and a disposal site for low-level radioactive wastes at Drigg near Sellafield. Radiation sources and BNFL's radioactive discharge are first explained generally and then specifically for each BNFL site. Industrial and radiological safety within BNFL are described. (UK)

  3. Sellafield - the achievements and lessons of 40 years experience

    International Nuclear Information System (INIS)

    Heafield, W.; Hexter, B.C.; Livesley, G.

    1996-01-01

    BNFL's operations, which support a global nuclear fuel cycle business and serve many companies in Pacific Basin countries, have been the subject of refinement from 40 years of experience. Many of the Company's operating philosophies are consistent with the principles of sustainable development. The paper acknowledges the important role that the nuclear industry can play in satisfying energy demands within economies of diminishing natural resources and societies which are becoming increasingly concerned about their impact on the environment. It explains how reprocessing can meet many of the criteria of sustainable development through recycling and the optimization of resources. It describes how BNFL have reduced the impact of its operations on the environment through the treatment of discharges and the minimization and stabilization of wastes requiring disposal. The establishment of BNFL Engineering Ltd as an outlet to the world markets for BNFL's engineering expertise and technology is covered. The paper looks at the responsible approach that BNFL is taking to liabilities management ensuring that no surprises are left for future generations. BNFL's commitment to the present and future of nuclear electricity generation is illustrated in the extent to which it is committed to making it operations safer and more cost effective through investment in research and development. The paper describes BNFL's commitment to the development of its employees and to the development of the communities in which it operates. The paper considers how BNFL has met its many challenges and draws out examples of sustainable development in practice. (author)

  4. Developments in fuel manufacturing

    International Nuclear Information System (INIS)

    Williams, T.

    1997-01-01

    BNFL has a long tradition of willingness to embrace technological challenge and a dedication to quality. This paper describes advances in the overall manufacturing philosophy at BNFL's Fuel Business Group and then covers how some new technologies are currently being employed in BNFL Fuel Business Group's flagship oxide complex (OFC), which is currently in its final stages of commissioning. This plant represents a total investment of some Pound 200 million. This paper also describes how these technologies are also being deployed in BNFL's MOX plant now being built at Sellafield and, finally, covers some new processes being developed for advanced fuel manufacture. (author)

  5. Gas centrifuge bibliography 1983-1986

    International Nuclear Information System (INIS)

    Lowe, G.E.; McLeod, D.F.; Roberts, P.

    1987-03-01

    A bibliography is presented of the gas centrifuge literature published from 1983-1986 inclusive. It supplements PG Information Series 25(CA), BNFL Information Series 15(CA), BNFL Information Series 23 (CA), and BNFL Information Series 27(CA), which together cover the period 1895-1982. The main arrangement is chronological and there are author, report number, and subject indexes. (U.K.)

  6. Office of River Protection (DOE-ORP) Hanford Tank Waste Treatment Alternatives March 2000

    International Nuclear Information System (INIS)

    WODRICH, D.D.

    2000-01-01

    The U.S. Department of Energy (DOE) is currently planning to retrieve, pretreat, immobilize and safely dispose of 53 million gallons of highly radioactive waste currently stored in underground tanks at Hanford Site. The DOE plan is a two-phased approach to privatizing the processing of hazardous and radioactive waste. Phase 1 is a proof-of-concept/commercial demonstration-scale effort whose objectives are to: demonstrate, the technical and business viability of using privatized facilities to treat Hanford tank waste; define and maintain required levels of radiological, nuclear, process and occupational safety; maintain environmental protection and compliance; and substantially reduce life-cycle costs and time required to treat Hanford tank waste. The Phase 1 effort consists of Part A and Part B. On September 25, 1996 (Reference 1), DOE signed a contract with BNFL, Inc. (BNFL) to commence with Phase 1, Part A. In August 1998, BNFL was authorized to proceed with Phase I, Part 6-1, a 24-month design phase that will-provide sufficient engineering and financial maturity to establish fixed-unit prices and financing terms for tank waste processing services in privately-owned and -operated facilities. By August 2000, DOE will decide whether to authorize BNFL to proceed with construction and operation of the proposed processing facilities, or pursue a different path. To support of the decision, DOE is evaluating alternatives to potentially enhance the BNFL tank waste processing contract, as well as, developing an alternate path forward should DOE decide to not continue the BNFL contract. The decision on whether to continue with the current privatization strategy (BNFL contract) or to pursue an alternate can not be made until the evaluation process leading up to the decision on whether to authorize BNFL to proceed with construction and operation (known as the Part 8-2 decision) is completed. The evaluation process includes reviewing and evaluating the information BNFL is

  7. Studies of environmental radioactivity in Cumbria. Part 6. The chronology of discharges of caesium-137, plutonium and americium-241 from BNFL Sellafield, as recorded in lake sediments

    Energy Technology Data Exchange (ETDEWEB)

    Eakins, J D; Cambray, R S

    1985-04-01

    A study has been made of the radionuclide content of lake sediments from Cumbria in order to determine the history of discharges of /sup 137/Cs and actinides from the Sellafield works of British Nuclear Fuels plc (BNFL). Sediment cores have been taken from Ullswater and Grasmere, which are remote from Sellafield, in order to establish the behaviour of nuclear weapon fallout nuclides. Cores have also been taken from Barfield Tarn, which is 19 km SE of Sellafield but close to the sea, and from Ponsonby and Harnsey Moss Tarns, close to Sellafield. All sediments were analysed for /sup 137/Cs and sup(239+240)Pu. Additional measurements of /sup 238/Pu and /sup 241/Am were made on samples from the closer tarns. The sediment cores were dated by the /sup 210/Pb method and, where appropriate, by the /sup 137/Cs technique also. The amounts of /sup 137/Cs and sup(239+240)Pu in sediments from Barfield Tarn could be accounted for by fallout from nuclear weapons, although the levels of /sup 241/Am were marginally greater. However in Harnsey Moss Tarn the levels of actinides indicated that they were derived mainly from material originally discharged to sea from Sellafield. Sediment from Ponsonby Tarn contained material derived mainly from discharges to atmosphere.

  8. Annual report and accounts 1988/89

    International Nuclear Information System (INIS)

    1989-01-01

    British Nuclear Fuel's (plc) (BNFL) operations over the year 1988/9 are reviewed. The financial position is presented and the accounts explained. These show that the year was one of growth. BNFL manufactures nuclear fuel and fuel products at Springfields near Preston, enriches uranium by a centrifuge process at Capenhurst near Chester, reprocesses and manages waste at Sellafield in West Cumbria and has a headquarters and engineering design facility at Risley near Warrington. BNFL also owns and operates two nuclear power stations at Calder Hall on the Sellafield site and at Chapelcross in Southern Scotland. Each aspect of the company's activities is reviewed briefly and an overview given in reports of the Chairman and Chief Executive. Over 90% of BNFL's turnover is associated with the production of electricity by nuclear power. The government's decision to withdraw the nuclear power stations from the privatisation of the electricity supply industry has created uncertainty over the long-term position of BNFL. (UK)

  9. Annual report and accounts 1990/91

    International Nuclear Information System (INIS)

    1991-01-01

    In this Annual Report for 1990/91, British Nuclear Fuels Limited (BNFL) considers the year's results financially and in terms of scientific innovation. BNFL produces nuclear fuel for all United Kingdom (UK) power stations and is thus, indirectly responsible for the 20% of electricity generated by nuclear power. Since the privatization of the electricity generating industry in the United Kingdom, nuclear power has had an unresolved financial and commercial status. BNFL has still not considered negotiations with their two UK customers, Nuclear Electric and Scottish Nuclear so accounts presented include assumptions about fixed price contracts. Public relations has become a major issue for BNFL and the work of the Sellafield Visitors Centre is described in detail. (UK)

  10. R. v. H.M. Inspectorate of Pollution and Ministry of Agriculture, Fisheries and Food, ex parte Greenpeace

    International Nuclear Information System (INIS)

    Otton, J.

    1994-01-01

    The British Nuclear Fuel plc (BNFL) Thermal Oxide Reprocessing Plant, THORP, has been constructed to reprocess spent nuclear fuel at Sellafield. BNFL have existing authorisations for the emissions of liquid and gaseous radioactive wastes relating to its existing operations. In April 1993, BNFL applied to vary the authorisations to start testing operation of THORP. As the emissions were expected to be covered by existing authorisations BNFL wanted to start tests before formal authorisations were granted. Her Majesty's Inspectorate of Pollution (HMIP) stressed the need for formal application and for public consultation. Greenpeace challenged the granting by HMIP of variations so THORP could be operated on several grounds. Greenpeace's application for a judicial review was dismissed. (UK)

  11. It tells you where we want to go and not where we've been

    International Nuclear Information System (INIS)

    Whittaker, Louise M

    1995-01-01

    In summary, up to now, BNFL's current visual identity was, amongst other things, dated, fragmented, inconsistent and poorly maintained. Quite simply, the existing identity did NOT say where we were going - only where we had been. The research also revealed three interesting conclusions regarding BNFL as a company name. It was clearly a very strong brand but there was distinct confusion over the acronym BNFL and the full registered company name of British Nuclear Fuels plc. In addition, 'British' was felt to be too restrictive for a company focused upon a broad international marketplace and the word fuel implied we concentrate purely on the fuel cycle, dismissing our unrivalled achievements in areas, such as engineering, fluorochemicals and environmental clean-up. The solution was to promote the company as BNFL and de-emphasise the use of the full company name during all promotional activity. So, where did we go from here? We developed three options for testing. Firstly the existing BNFL logo, secondly a refined and more modem version of the existing BNFL logo and finally a complete change of logo. We were also keen to establish the strength of the three options in relation to other well known and respected identities

  12. Annual report and accounts 1984/85

    International Nuclear Information System (INIS)

    1985-01-01

    All aspects of British Nuclear Fuels (BNFL) work are covered in this report. The company offers a complete fuel cycle service from fuel fabrication to spent fuel reprocessing. Each of the operations undertaken by BNFL (on five sites in northern England and southern Scotland) is explained and illustrated with photographs and drawings. The accounts show that in 1985 BNFL employed over 15,000 people and had a turnover of Pound545 million. (UK)

  13. Safety and health annual report 1996

    International Nuclear Information System (INIS)

    1997-01-01

    The 1996 report on the Health and Safety performance of the nuclear fuel cycle company BNFL at its sites in the United Kingdom demonstrates a continuing improvement. The site locations and developments are briefly described and international developments in subsidiary organisations noted. Other sections of the report cover health and safety policy, radiological and industrial safety, emergency planning, incidents, occupational health services, compensation scheme developments, transport, putting radiation in perspective, and safety and health research. Data are provided on: radioactive discharges; industrial safety of BNFL and contractors' employees; radiation dose summaries for BNFL and contractors' employees. There is evidence of the expected plateauing out of doses to BNFL employees at a level less than or similar to background radiation. (UK)

  14. An example of the practical application of ALARP in planning, implementation and review at BNFL's Bradwell Power Station

    International Nuclear Information System (INIS)

    Devine, I.R.; James, C.

    2000-01-01

    The paper will describe three examples of the practical application of ALARP principles as applied to some major projects associated with enhancement of the safety cases for heat exchanger or reactor core support structures at some Magnox Power Stations operated by BNFL Magnox Generation. It will summarise and discuss some of the issues encountered during the pre-planning, engineering development/implementation, work in progress and post completion review phases. The first example is the response to minor defects discovered during an inspection of a sample of some welds in an upper restraint beam inside the concrete reactor pressure vessel at Oldbury Power Station. These inspections were carried out to enhance the existing safety case to justify a proposed increase in the period between statutory inspections from two to three years. The presence or absence of similar defects in the other welds was not sufficiently well characterised nor could be sufficiently accurately predicted without extensive additional NDT inspection. This would in itself have incurred a significant dose commitment. The engineering/ALARP assessment was required address the justification of the work and even determine what should be proposed. Available options included: extensive inspection to determine the status of load bearing welds to enable a subsequent assessment of the required remedial work (if any) which may include weld dressing, repair or reinforcement; pre-emptive reinforcement on a 'worst case scenario', or pre-emptive complete or partial weld repair. The second and third case studies relate to the response to minor defects in welds associated with support beams inside heat exchangers at Bradwell and Hinkley Point Power Stations. In these cases, pre-emptive repair or reinforcement was clearly justified and optimal. The engineering/ALARP assessments were required to address the optimisation of the required repair or reinforcement strategy and tasks associated with its implementation

  15. Application of model based predictive control to a solvent extraction plant

    International Nuclear Information System (INIS)

    Harper, W.J.

    1995-01-01

    British Nuclear Fuels plc. (BNFL) is the most experienced nuclear fuel company in the world, having supplied nuclear fuel cycle services in the UK and overseas for over forty years. BNFL is one of only two companies in the world that is able to offer nuclear fuel manufacture, enrichment, reprocessing and waste management services. In addition to its work for the UK Nuclear Power Programme, BNFL has developed a substantial export business with nuclear power plant operators in Western Europe, Japan and North America, which now accounts for 18% of the annual turnover. BNFL's plants re situated in North West England and Southern Scotland. Nuclear fuel and fuel products are manufactured at Springfields near Preston; uranium enrichment by the centrifuge process is carried out at Capenhurst, near Chester; reprocessing and waste management services are provided at Sellafield, West Cumbria. The Company's headquarters and engineering design facilities are based at Risley, near Warrington. BNFL also owns and operates two (MAGNOX) nuclear power stations-Calder Hall, on the Sellafield site, the Chapelcross, near Dumfries in Southern Scotland

  16. Department of Energy: monitoring and control of British Nuclear Fuels plc

    International Nuclear Information System (INIS)

    1989-01-01

    British Nuclear Fuels plc (BNFL) was set up in 1971 to take over the nuclear fuel production and reprocessing activities of the United Kingdom Atomic Energy Authority with the Department of Energy (as majority shareholder) being responsible for the monitoring and control of BNFL's activities. BNFL's activities include the production of nuclear fuel, uranium enrichment, and the transportation and reprocessing of spent fuel. Its major capital investment includes the construction of the Thermal Oxide Reprocessing Plant (THORP) due for completion in 1992. This study examined the effectiveness of the Department's arrangements for monitoring and control and for safeguarding the Government's investment in the company, the arrangements for examining BNFL's capital investment programme and the extent to which the Department's main aims have been achieved. The examination was restricted to the financial performance. The National Audit Office found evidence to suggest that BNFL's financial performance has not kept pace with the general performance level of British Industry. Future success and performance will depend on the success of the THORP plant. (U.K.)

  17. Department of Energy: monitoring and control of British Nuclear Fuels plc. Report by the Comptroller and Auditor General

    Energy Technology Data Exchange (ETDEWEB)

    1989-01-01

    British Nuclear Fuels plc (BNFL) was set up in 1971 to take over the nuclear fuel production and reprocessing activities of the United Kingdom Atomic Energy Authority with the Department of Energy (as majority shareholder) being responsible for the monitoring and control of BNFL's activities. BNFL's activities include the production of nuclear fuel, uranium enrichment, and the transportation and reprocessing of spent fuel. Its major capital investment includes the construction of the Thermal Oxide Reprocessing Plant (THORP) due for completion in 1992. This study examined the effectiveness of the Department's arrangements for monitoring and control and for safeguarding the Government's investment in the company, the arrangements for examining BNFL's capital investment programme and the extent to which the Department's main aims have been achieved. The examination was restricted to the financial performance. The National Audit Office found evidence to suggest that BNFL's financial performance has not kept pace with the general performance level of British Industry. Future success and performance will depend on the success of the THORP plant. (U.K.).

  18. The treatment of uranyl nitrate from the AMOR process for VKTA Rossendorf

    International Nuclear Information System (INIS)

    Boessert, W.; Krempl, R.; Miller, J.W.

    2003-01-01

    The blending of uranyl nitrate solutions at VKTA and its subsequent treatment at BNFL-Sellafield is a significant step towards the safe and effective treatment of these enriched uranyl nitrate solutions. Overall the integration of the expertise of the international company BNFL/Westinghouse will lead to the achievement of a successful solution. This success has involved the integration of the project management and operational facilities of BNFL Sellafield with the local planning, design and manufacture capacities of Westinghouse Reaktor GmbH. (orig.)

  19. AW-101 entrained solids - Solubility versus temperature

    International Nuclear Information System (INIS)

    GJ Lumetta; RC Lettau; GF Piepel

    2000-01-01

    This report describes the results of a test conducted by Battelle to assess the solubility of the solids entrained in the diluted AW-101 low-activity waste (LAW) sample. BNFL requested Battelle to dilute the AW-1-1 sample using de-ionized water to mimic expected plant operating conditions. BNFL further requested Battelle to assess the solubility of the solids present in the diluted AW-101 sample versus temperature conditions of 30, 40, and 50 C. BNFL requested these tests to assess the composition of the LAW supernatant and solids versus expected plant-operating conditions. The work was conducted according to test plan BNFL-TP-29953-7, Rev. 0, Determination of the Solubility of LAW Entrained Solids. The test went according to plan, with no deviations from the test plan

  20. British Nuclear Fuels PLC: report and accounts 1989-90

    International Nuclear Information System (INIS)

    1991-01-01

    Members of the Energy Select Committee put questions to representatives of British Nuclear Fuels PLC (BNFL) about the annual report and accounts 1989-90. Questions concerned the late publication of the accounts, BNFLs role in the downfall of the nuclear privatisation, government assistance to the nuclear industry, the price BNFL charges for fuel reprocessing and the process of laser isotope separation of uranium. The committee also asked about the rate of return in BNFL's assets as a percentage, Sellafield's potential as a site for a deep repository for radioactive wastes and the 6000 boreholes that MREX will drill at Sellafield. The commercial case for reprocessing is made. Feasibility studies for possible new reactions at Sellafield and Chapel Cross have been carried out. On the whole the Energy Committee were satisfied with the replies from BNFL. (UK)

  1. Internet - Workshop contribution proposal

    International Nuclear Information System (INIS)

    Doran, Janine

    1998-01-01

    BNFL first launched itself on the World Wide Web (WWW) in 1995 to give free access to information on the company and our activities to interested parties and to try and counteract some of the misleading claims being put onto the web by various anti-nuclear organisations. Whilst fit for purpose 2 years ago the current site has not been developed further and as a result does not reflect the image of BNFL as a world class international company. The current site has however enabled us to ascertain how popular and useful a BNFL web site is for all our audiences. We are now using this knowledge to redevelop BNFL's web site and are aiming to re-launch in September 1997 with a whole new look and style which will set a precedent for further developments in the near future

  2. Health and safety annual report 1992

    International Nuclear Information System (INIS)

    1993-01-01

    BNFL operates 6 sites in the United Kingdom concerned with the nuclear fuel cycle. The annual report on occupational health and safety gives information on all aspects of health and safety within BNFL with special reference to radiation doses received by the workforce and radiation protection measures taken by the company. BNFL's safety policy is set out. Radiation doses to all workers have remained low. Other industrial accidents are also listed and its safety measures for transport, radioactive effluents and in the event of an incident, are mentioned briefly. (UK)

  3. Recent UK Experience of Involving the Public in Decisions on Radioactive Discharges

    International Nuclear Information System (INIS)

    Smith, R.E.; Weedon, C.J.; McGoff, A.; Bower, M.

    2001-01-01

    In January 1998 BNFL applied to the Agency for authorisations to dispose of gaseous, liquid, combustible and solid radioactive wastes in respect of each of Magnox Electric's power stations. The Agency is currently considering BNFL's applications. This is the first time that authorisations for radioactive waste disposal have been considered for all these stations together as a package. It has been a major task for BNFL to assemble all the relevant information and for the Agency to drive the process forward through public consultation to the decision-making stage. As part of its role of protecting and improving the environment, the Agency is committed to progressive reductions in radioactive discharges where practicable, seeking to achieve this through the limits and conditions of any authorisation it issues. It aims to review nuclear site authorisations on a four-yearly cycle and has used BNFL's applications as the basis for its review of the Magnox power station sites. The Agency carefully scrutinised the applications and obtained additional detailed information and clarification from BNFL in response to six rounds of questions. The applications and responses from the company to Agency questions were made publicly available. They include information on: the benefits and detriments of continued operation/decommissioning (as appropriate); the sources and amounts of radioactive waste associated with continued operation/decommissioning; the current levels of discharge of radioactive waste to the environment; and the application of best practicable means (BPM) to minimise discharges. The Agency is considering all the application information and must decide, separately for each power station, whether an authorisation should be issued to BNFL. It has consulted publicly to assist its decision making, the objective being to enable people and organisations to draw to the Agency's attention any matters they would wish it to consider when reaching its decisions on the

  4. Privatization and culture change: British Nuclear Fuels case study

    International Nuclear Information System (INIS)

    Salama, A.

    1997-01-01

    This paper describes and explains the process of organizational change experienced by British Nuclear Fuels (BNFL) during the late 1980s. BNFL went through a major transformation in management values and practices to survive in the new business environment characterized by government deregulation and fiercer global market competition. The paper describes both the historical and the prevailing management behaviour as well as the strategy utilized by BNFL's top management in their change process. The key factor in the process of change seems to lie in top management commitment and a fully integrated set of actions involving different sub-systems of the organization. (author)

  5. The development and implementation of a waste management strategy

    International Nuclear Information System (INIS)

    Fairhall, G.A.; Vickery, P.; Edmiston, L.

    1999-01-01

    Over the past forty years BNFL has operated 4 nuclear sites in the UK. Commercial operations on these sites span the full nuclear fuel cycle from enrichment, fuel fabrication, electricity generation, reprocessing, waste management, and decommissioning. Through the recent merger with Magnox Electric BNFL has acquired a further 8 Magnox reactor sites in the UK. Prior to 1980 BNFL adopted a policy of storing wastes generated by its activities in an unconditioned state in purpose built stores. This paper shows how BNFL's waste management strategy has developed to ensure how volume reduction technologies have been implemented for low level waste. Whilst immobilisation technologies have been implemented for high and intermediate level wastes. The paper describes how continual review of the strategy ensures waste management processes are continually monitored against progress and optimised to ensure all waste arisings are conditioned for final disposal. Finally the paper will show how the strategy can be used to develop waste management plans for customer sites. (author)

  6. Integrated engineering increases flexibility

    International Nuclear Information System (INIS)

    Smith, Ray

    1991-01-01

    Integrated Engineering (IE) can be used to describe the best use of increasingly rare good engineering talent in an increasingly competive world. A number of organisations are now moving towards IE without any general agreement on a precise definition. The engineering division of British Nuclear Fuels (BNFL) is one such organisation. This feature covers the reasoning behind the decision, and our experience to date. BNFL engineering division is responsible primarily for the provision of major facilities on BNFL operational sites. This provision includes feasibility, front end and detailed design, procurement, installation and commissioning. Task force working has been used for some of the large projects. But the future workload is expected to comprise many more smaller projects. At the same time, equipment is becoming more complex and the need for mutual understanding and appreciation between disciplines is increasing. To meet this increasing need for flexibility, BNFL has decided to move to the matrix structure of project management and functional departments described in the article. (Author)

  7. Recent UK Experience of Involving the Public in Decisions on Radioactive Discharges

    Energy Technology Data Exchange (ETDEWEB)

    Smith, R.E. [Environment Agency, London (United Kingdom); Weedon, C.J. [Environment Agency, Penrith (United Kingdom); McGoff, A.; Bower, M. [Environment Agency, Bedford (United Kingdom)

    2001-07-01

    In January 1998 BNFL applied to the Agency for authorisations to dispose of gaseous, liquid, combustible and solid radioactive wastes in respect of each of Magnox Electric's power stations. The Agency is currently considering BNFL's applications. This is the first time that authorisations for radioactive waste disposal have been considered for all these stations together as a package. It has been a major task for BNFL to assemble all the relevant information and for the Agency to drive the process forward through public consultation to the decision-making stage. As part of its role of protecting and improving the environment, the Agency is committed to progressive reductions in radioactive discharges where practicable, seeking to achieve this through the limits and conditions of any authorisation it issues. It aims to review nuclear site authorisations on a four-yearly cycle and has used BNFL's applications as the basis for its review of the Magnox power station sites. The Agency carefully scrutinised the applications and obtained additional detailed information and clarification from BNFL in response to six rounds of questions. The applications and responses from the company to Agency questions were made publicly available. They include information on: the benefits and detriments of continued operation/decommissioning (as appropriate); the sources and amounts of radioactive waste associated with continued operation/decommissioning; the current levels of discharge of radioactive waste to the environment; and the application of best practicable means (BPM) to minimise discharges. The Agency is considering all the application information and must decide, separately for each power station, whether an authorisation should be issued to BNFL. It has consulted publicly to assist its decision making, the objective being to enable people and organisations to draw to the Agency's attention any matters they would wish it to consider when reaching its

  8. Health, safety and the environment

    International Nuclear Information System (INIS)

    1991-01-01

    The central theme of this 1990 Annual Report from British Nuclear Fuels Limited (BNFL) is that the health and safety of the public and protection of the environment are of primary concern. The report describes the fuel cycle for the production of radioactive materials used by the United Kingdom nuclear industry. Radiation protection measures undertaken by BNFL are explained as is their environmental research programme. Detailed attention is paid to the monitoring of effluent discharges into the environment and arrangements for radioactive waste disposal. The work of each BNFL site is described. The report finishes with a description of its occupational safety measures. (UK)

  9. Experience within international transport and direct rail services in meeting the IAEA requirement for a radiation protection programme(s)

    International Nuclear Information System (INIS)

    Billing, D.

    2003-01-01

    BNFL International Transport and Direct Rail Services have successfully developed appropriate Radiation Protection Programmes for their business. The business supports BNFL's worldwide Nuclear Fuel Services with key customer bases in Europe, Japan and the UK, utilising marine, rail and road modal transports. Experience in this business spans over 4 decades. The preparation of RPP's for each aspect of its operations has been made relatively straight forward in that the key elements within the internationally recognised model RPP (by WNTI) were already in place in BNFL's procedures to satisfy current National UK and International Regulations and supported by Management systems which comply with International Standards for Quality Assurance. (author)

  10. Emergency response arrangements for the transport of irradiated nuclear fuel from Japan to Europe in Japanese territorial waters

    International Nuclear Information System (INIS)

    Ikeda, T.; Inada, T.; Narahara, S.; Cheshire, R.D.; Lee, G.

    1993-01-01

    About 90 % of nuclear fuel irradiated in Japanese nuclear power stations is transported to UK and France for reprocessing. Pacific Nuclear Transport Ltd (PNTL), a subsidiary of British Nuclear Fuels plc (BNFL), owns and operates its own fleet of 5 purpose built ships specially designed for the transport of flasks containing irradiated fuel from Japan to Europe. These vessels sail to Japan on 8 to 10 voyages per year from the BNFL's Marine Terminal at Barrow in UK via Cherbourg Port in France. On arrival in Japan empty flasks are delivered to Japanese nuclear power stations, and full flasks are collected for the return journey to Europe. Whilst the probability of a serious flask incident involving the release of radioactivity is very small, it is nevertheless important to plan for such an emergency. In the case of an incident BNFL will provide an emergency response. If an incident occurs in Japanese territorial waters, the initial response will be provided by Nuclear Services Company (NSC), who are based in Japan (the head office in Tokyo, Tokai Office in Ibaraki Prefecture and Tsuruga Office in Fukui Prefecture) and contracted to BNFL to provide a similar response to that available from UK. This paper describes the communication links which have been established between UK and Japan and the internal communication within Japan. It also describes the emergency equipent held in Japan, the training of teams and the results of exercises jointly carried out with BNFL. (J.P.N.)

  11. Office of River Protection, plan for Developing Hanford Tank Waste Processing Alternatives, Revision 1, December 15, 1999

    International Nuclear Information System (INIS)

    WODRICH, D.D.

    2000-01-01

    In August 2000, The Department of Energy (DOE) must decide whether to authorize BNFL Inc. (BNFL) to construct and operate tank waste processing facilities as proposed or to take another path. This will be a multi-billion dollar commitment, requiring that the best path forward be chosen. The plan for reaching this decision is described in reference 1. The alternative evaluations in this plan are directed toward acquiring information needed for the August 2000 decision and for preparing an alternate path plan, should an acceptable agreement with BNFL not be reached. Many of the alternatives considered may still be applicable for failures that could occur after the year 2000, however, depending on the cause of later failures, others alternatives may need to be developed

  12. Use of Formal Procedures in Developing Dialogue Between Operator and Regulator on Radioactive Waste Disposal

    International Nuclear Information System (INIS)

    Yearsley, Roger; Duerden, Susan; Bennett, David

    2001-01-01

    The Environment Agency (the Agency) is responsible, in England and Wales, for authorisation of radioactive waste disposal under the Radioactive Substances Act 1993. British Nuclear Fuels plc (BNFL) is currently authorised to dispose of solid low level radioactive waste at its Drigg site near Sellafield in Cumbria. Drigg is the primary site for the disposal of solid low level radioactive waste generated by the UK nuclear industry. A small facility operated by United Kingdom Atomic Energy Authority (UKAEA) at Dounreay on the north coast of Scotland is used solely for wastes arising on the UKAEA site. Drigg also offers a disposal route for smaller users of radioactive substances, such as hospitals and universities. Significant benefits have been derived from implementing a formal Issue Resolution Procedure as part of a soundly based process for dialogue between the Agency and BNFL. Benefits include improved understanding of the Agency's expectations, which has in turn led to improvements in BNFL's documentation and technical approach. The Agency considers the use of a formal Issue Resolution Procedure has placed the dialogue with BNFL on firm foundations for the planned assessment of the PostClosure Safety Case for Drigg when it is submitted in September 2002

  13. Providing solutions to engineering problems

    International Nuclear Information System (INIS)

    Connop, R.P.P.

    1991-01-01

    BNFL has acquired unique experience over a period of 40 years in specifying, designing and constructing spent fuel reprocessing and associated waste management plant. This experience is currently used to support a pound 5.5 billion capital investment programme. This paper reviews a number of engineering problems and their solutions to highlight BNFL experience in providing comprehensive specification, design and engineering and project management services. (author)

  14. Applications of Molecular and Materials Modeling

    Science.gov (United States)

    2002-01-01

    Chimica Industriale Molecular modeling of solvation Prof. Jacopo Tomasi http://www.dcci.unipi.it/attivita /attivita.html; http://www.dcci.unipi.it...solutions/ cases/notes/scale.html BNFL Sorption of gases in zeolites Dr. Scott L. Owens http://www.bnfl.co.uk/ BAE (British Aerospace Engineering) Rare...permeation of gases ; adhesion and interfacial interactions of siloxane networks; chemical reactivity and catalysis; environmental and cosmetics

  15. Annual report on occupational safety 1983

    International Nuclear Information System (INIS)

    1984-08-01

    The 1983 Annual Report on occupational safety at BNFL is presented. Data for whole-body radiation doses and skin and extremity doses are given for BNFL employees together with 1982 data for comparison. Similarly, accidental deaths and major injuries are recorded. Finally information on the frequency of both nuclear and non-nuclear incidents reported to the Health and Safety Executive is given. (U.K.)

  16. Research reactor back-end options - decommissioning: a necessary consideration

    International Nuclear Information System (INIS)

    England, M.R.; Parry, D.R.; Smith, C.

    1998-01-01

    Decommissioning is a challenge, which all radioactive site licensees eventually need to face and research reactors are no exception. BNFL has completed numerous major decommissioning projects at its own operational sites and has undertaken similar works at customers' sites including the decommissioning of the Universities Research Reactor (URR), Risley and the ICI TRIGA 1-Mk I Reactor at Billingham. Based on the execution of such projects BNFL has gained an understanding of the variety of customer requirements and the effectiveness of specific decommissioning techniques for research reactors. This paper addresses factors to be considered when reviewing the way forward following shut down and how these affect the final decisions for fuel management and the extent of decommissioning. Case studies are described from BNFL's recent experience decommissioning both the URR and ICI TRIGA reactors. (author)

  17. Steel construction in the nuclear reprocessing industry

    International Nuclear Information System (INIS)

    Jordan, G.W.

    1990-01-01

    Over the past decade British Nuclear Fuels plc (BNFL) has pursued a large capital expenditure programme at Sellafield in Cumbria. This has used large quantities of structural steelwork. For example, Thorp plant for reprocessing spend AGR and LWR fuels, due for completion in 1992, has 20,000 tonnes. The design of these plants has been entrusted to BNFL Engineering based at Risley near Warrington, England. These safety-related structures are designed, as required by the Nuclear Installations Inspectorate, to withstand the effects of environmental hazards such as extremes of earthquake, wind, temperature, ice, snow, flooding, and lightning strikes. In some cases they may be subjected to impact loading from possible mishandling of lifted loads such as fuel transportation flasks. Design criteria for these structures have been developed by BNFL Engineering. Some examples are mentioned. (author)

  18. Solid waste - the long term strategy

    International Nuclear Information System (INIS)

    Johnson, L.F.

    1990-01-01

    Until deep underground repository sites for low-and intermediate-level radioactive wastes can be identified and prepared by Nirex Limited, these products are being encapsulated into solid concrete form by British Nuclear Fuels Limited (BNFL), and stored in 500- litre drums. Low-level solid waste is dealt with at BNFL's Drigg plant where it is buried in trenches. Recent improvements in rainwater leaching are outlined. Concrete-lined vaults and compactification devices are now operational as well. High-level waste which contains 97% of the radioactivity from irradiated fuel reprocessing, is converted into a vitrified glass product at the new Windscale Vitrification Plant. Together these form BNFL's comprehensive strategy for the treatment, interim storage and disposal of nuclear waste arising from its operations. Progress in the provision of waste management and of disposal facilities has been substantial. U.K

  19. Annual report and accounts 1995

    International Nuclear Information System (INIS)

    1995-01-01

    This item consists of the Annual Report and Accounts of British Nuclear Fuels Limited (BNFL) for 1995 and a public relations document explaining the company's work in the United Kingdom nuclear power industry. BNFL has many years' experience in nuclear fuel manufacturing, reprocessing, waste management, decommissioning and transport of nuclear materials, and provides services to other organizations worldwide based on this expertise, making it an important export earner for the United Kingdom. (UK)

  20. British Nuclear Fuels plc: report and accounts 1987-88

    International Nuclear Information System (INIS)

    1989-01-01

    The Energy Committee has considered the report and accounts of BNFL (British Nuclear Fuels PLC) for the year 1987-88. The report looks at BNFL as a government owned PLC - its activities and financial performance. Various questions are raised about the underlying financial position justifying the optimism portrayed in the report and accounts. The impact of cost-plus contracts on UK customers is examined. The economics of THORP (Thermal Oxide Reprocessing Plant) are also examined especially as the escalation in the cost of constructing THORP means that a substantial loss will be made in the reprocessing of waste for which contracts were signed in the late 1960s or early 1970s. The main conclusions of the report are summarized. One of these is that the UK must be cautious about becoming a repository of foreign nuclear waste. Other specific recommendations are made - some about the decommissioning of BNFL plant. (UK)

  1. Commercialism - the growth prospect

    International Nuclear Information System (INIS)

    Phillips, D.K.R.

    1990-01-01

    In an attempt to ensure good business proposals for the future British Nuclear Fuels Limited (BNFL) is making a number of international initiatives. Likely markets for expansion include the United States, Japan and Western Europe, to whom the company can offer activities such as oxide fuel reprocessing, uranium hexafluoride conversion, fabrication of oxide and mixed oxide fuels, uranium enrichment and the safe transport of nuclear materials. The creation of International Nuclear Fuels Limited will expand overseas business and ensure security of fuel supply for the international nuclear industry. Working jointly with AEA Technology, BNFL will seek to market their combined decommissioning experience on the international market. The author concludes the BNFL is in a strong position to supply an increasing world-wide need for nuclear waste management and increased commercial awareness within the company will ensure a good section of the market is secured. U.K

  2. The development of B.N.F.L.'S MOX fuel supply business

    International Nuclear Information System (INIS)

    Edwards, J.; Brown, C.; Marshall, S.J.; Connell, M.; Thompson, H.

    1998-01-01

    In 1990 BNFL developed a strategy to become one of the world leading MOX fuel suppliers. This strategy involved the design, construction and operation of a small scale demonstration plant known as the MOX Demonstration Facility (MDF) and a large scale facility known as the Sellafield MOX Plant (SMP). To support the development of these facilities, BNFL developed a new MOX fuel fabrication process known as the Short Binderless Route (SBR). Since the 1990 decision was made, the company has successfully built, commissioned and operated the MDF, and has designed, built and is in the process of commissioning the 120 t(HM)/year SMP. The scale of the business has thus developed significantly and the direction and prospects for the future of the business are clear and well understood, with the focus being on the use of BNFL technology to produce quality MOX fuel to meet customers' requirements. This paper reviews the development of BNFL's MOX business and describes the technology being used in the state of the art SMP. The paper also explains the approach taken to commission the plant and how key safety features have been incorporated into the design. Up to date information on the performance of Short Binderless Route fuel is provided, and the future development of the business is discussed. (author)

  3. LLW disposal wasteform preparation in the UK: the role of high force compaction

    Energy Technology Data Exchange (ETDEWEB)

    Johnson, L. F.; Fearnley, I. G. [British Nuclear Fuels Ltd., Sellafield (United Kingdom)

    1991-07-01

    British Nuclear Fuels plc (BNFL) owns and operates the principal UK solid low level radioactive waste (LLW) disposal site. The site is located at Drigg in West Cumbria some 6 km to the south east of BNFL's Sellafield reprocessing complex. Sellafield is the major UK generator of LLW, accounting for about 85% of estimated future arisings of raw (untreated, unpackaged) waste. Non-Sellafield consignors to the Drigg site include other BNFL production establishments, nuclear power stations, sites of UKAEA, Ministry of Defence facilities, hospitals, universities, radioisotope production sites and various other industrial organisations. In September 1987, BNFL announced a major upgrade of operations at the Drigg site aimed at improving management practices, the efficiency of space utilisation and enhancing the visual impact of disposal operations. During 1989 a review of plans for compaction and containerisation of Sellafield waste identified that residual voidage in ISO freight containers could be significant even after the introduction of compaction. Subsequent studies which examined a range of compaction and packaging options concluded that the preferred scheme centred on the use of high force compaction (HFC) of compactable waste, and grouting to take up readily accessible voidage in the wasteform. The paper describes the emergence of high force compaction as the preferred scheme for wasteform preparation and subsequent benefits against the background of the overall development of Low Level Waste disposal operations at Drigg.

  4. LLW disposal wasteform preparation in the UK: the role of high force compaction

    International Nuclear Information System (INIS)

    Johnson, L. F.; Fearnley, I. G.

    1991-01-01

    British Nuclear Fuels plc (BNFL) owns and operates the principal UK solid low level radioactive waste (LLW) disposal site. The site is located at Drigg in West Cumbria some 6 km to the south east of BNFL's Sellafield reprocessing complex. Sellafield is the major UK generator of LLW, accounting for about 85% of estimated future arisings of raw (untreated, unpackaged) waste. Non-Sellafield consignors to the Drigg site include other BNFL production establishments, nuclear power stations, sites of UKAEA, Ministry of Defence facilities, hospitals, universities, radioisotope production sites and various other industrial organisations. In September 1987, BNFL announced a major upgrade of operations at the Drigg site aimed at improving management practices, the efficiency of space utilisation and enhancing the visual impact of disposal operations. During 1989 a review of plans for compaction and containerisation of Sellafield waste identified that residual voidage in ISO freight containers could be significant even after the introduction of compaction. Subsequent studies which examined a range of compaction and packaging options concluded that the preferred scheme centred on the use of high force compaction (HFC) of compactable waste, and grouting to take up readily accessible voidage in the wasteform. The paper describes the emergence of high force compaction as the preferred scheme for wasteform preparation and subsequent benefits against the background of the overall development of Low Level Waste disposal operations at Drigg

  5. Application of new technology to the fabrication and installation of stainless steel pipework

    International Nuclear Information System (INIS)

    Halford, P.; Carrick, L.

    1989-01-01

    BNFL has been constructing new reprocessing plant on a continuous basis since the late seventies. Initially the productivity achieved when fabricating and welding stainless steel to nuclear standards was poor. In order to complete projects to programme and cost BNFL developed a Total Fabrication System that is now applied to all of their construction projects and has resulted in overall productivity increases by a factor of 2.4 with major quality and cost benefits. The development of the Total Fabrication System is described

  6. The Nuclear Industry (Finance) Citation Act 1977. Chapter 7

    International Nuclear Information System (INIS)

    1977-01-01

    This Act makes further financial provision for and in respect of British Nuclear Fuels Limited (BNFL), the Radiochemical Centre Limited (TRCL) and the National Nuclear Corporation Limited (NNCL). The Secretary of State for Energy may, with the Treasury's consent guarantee repayments of any loan made to BNFL or TRCL and the guarantee may extend to the payment of loan interest and any other payments falling. Immediately after giving the guarantee the Secretary of State must lay before Parliament a statement showing the extent character and circumstances of such guarantee. If an amount is paid in fulfillment of the guarantee the company concerned shall be indebted to that amount with interest at the rate the Treasury specifies. The financial limits applicable to BNFL range from Pound 300 million to Pound 500 million and Pound 5 million to Pound 15 million to TRCL. The Secretary of State may, after authorisation from the Treasury, acquire shares in or securities of the NNCL. (NEA) [fr

  7. Planning developments in British Nuclear Fuels Ltd

    Energy Technology Data Exchange (ETDEWEB)

    Roper, D A [British Nuclear Fuels Ltd., Risley

    1978-10-01

    The state of the corporate planning art in British Nuclear Fuels Ltd. was described by N.R.Geary (Long Range Planning, September (1973)) just 2 years after Company formation. This article discusses more recent planning developments over the period to date during which the Company adopted a Divisionalized structure (from October 1974) and has been required to submit an annual Company plan to the Department of Energy (from November 1975). Background information on the origin and nature of the BNFL and its business, and the particular features of the Company which reflect into the nature and method of its planning were given in the 1973 article and only a brief introductory updating of the Company position is included here. Subsequently the features and problems of BNFL's operating and development planning system are described. Finally, messages arising from BNFL's planning experience to date which may be of general application and therefore of value to other practitioners of planning are listed.

  8. Preliminary level 2 specification for the nested, fixed-depth sampling system

    International Nuclear Information System (INIS)

    BOGER, R.M.

    1999-01-01

    This preliminary Level 2 Component Specification establishes the performance, design, development, and test requirements for the in-tank sampling system which will support the BNFL contract in the final disposal of Hanford's High Level Wastes (HLW) and Low Activity Wastes (LAW). The PHMC will provide Low Activity Wastes (LAW) tank wastes for final treatment by BNFL from double-shell feed tanks. Concerns about the inability of the baseline ''grab'' sampling to provide large volume samples within time constraints has led to the development of a nested, fixed-depth sampling system. This sampling system will provide large volume? representative samples without the environmental, radiation exposure, and sample volume Impacts of the current base-line ''grab'' sampling method. This preliminary Level 2 Component Specification is not a general specification for tank sampling, but is based on a ''record of decision'', AGA (HNF-SD-TWR-AGA-001 ), the System Specification for the Double Shell Tank System (HNF-SD-WM-TRD-O07), and the BNFL privatization contract

  9. Fuel reprocessing at THORP: profitability and public liabilities

    International Nuclear Information System (INIS)

    Berkhout, F.

    1992-01-01

    Since the economics of British Nuclear Fuels Limited's (BNFL) Thermal Oxide Reprocessing Plant (THORP) were analysed in an earlier report, a number of domestic and international developments have affected the prospects for THORP. The present report outlines these changes, and analyses their implications for the profits and public liabilities associated with the project. Timing is of some significance because once THORP becomes radioactive (planned to occur in March 1993) the bill for decommissioning the plant will rise from a trivial sum to a very large one - Pound 900 million (1992 prices) in BNFL's own estimates. The report begins with a brief outline of reprocessing and the THORP project. It then examines the market prospects for reprocessing beyond THORP's first ten years and revises BNFL's own projections. It then considers the potential profitability of THORP in relation to various possible cost increases and finally outlines the possible implications of different THORP scenarios for the public purse. (author)

  10. Selling Sellafield

    International Nuclear Information System (INIS)

    Milne, Kirsty.

    1987-01-01

    The article describes a trip to the Sellafield reprocessing plant arranged by BNFL for journalists. The train journey from London and the actual tour round the Sellafield site and visitor centre are described briefly. Several protest groups were encountered on the way but the point made is that in encouraging visitors to the site and explaining what is going on there BNFL is trying to be more open in its dealings with the public in an effort to inform, reassure and lessen mistrust. (UK)

  11. Britain's nervous nuclear reaction

    International Nuclear Information System (INIS)

    Foster, G.

    1988-01-01

    The paper concerns the nuclear energy business in the United Kingdom, with emphasis on the management of the industry. A brief history is given of the development of the nuclear power programme and the creation of UKAEA and BNFL. BNFL is responsible for reprocessing at Sellafield, fuel element manufacture at Springfields, fuel reprocessing at Thorp, and uranium enrichment at Caperhurst. The development and management of these projects are discussed with respect to export markets, competition in international markets, commercial skills, and public opinion. (U.K.)

  12. Relations with local communities: 'a lot of happy faces and a lot of hard work'

    International Nuclear Information System (INIS)

    Williams, B.

    1995-01-01

    The public relations programme of British Nuclear Fuels (BNFL) is described. It includes: involvement in the economic regeneration of the regions in which its sites are located; providing resource materials to schools; funding of university posts, contract research and studentships; community involvement through such things as support of organisations/charities concerned with community and welfare, health issues, renewal and cultural activities, sponsorship. Branding and attribution in its community and sponsorship programmes is aimed at achieving recognition for BNFL as a quality, caring and responsible company. (UK)

  13. Proof of evidence [BNFL 2

    International Nuclear Information System (INIS)

    Avery, D.G.

    1982-01-01

    It is shown that the fuel cycle requirements of the proposed Sizewell B nuclear power station could be supplied by British Nuclear Fuels Limited. It is demonstrated that any facilities which may be required in the future could be provided from established technology. Evidence is presented in support of the responses which the Company has made to requests from the CEGB for guidance on the charges it should assume for some fuel cycle services in a variety of circumstances. Reference is made throughout to the fuel cycle needs of other possible future nuclear power stations as postulated by CEGB in its Statement of Case. (U.K.)

  14. BNFL Magnox - Upgrades and enhancements

    International Nuclear Information System (INIS)

    Udbinac, M.J.

    2006-01-01

    In the past, generic models, restrictive budgets,and general shortages of resources have limited the scope of the UK's older Magnox simulators. Nevertheless, the simulators evolved slowly over time, becoming more like their reference plants, as resources became available. Three years ago, the Training and Development Branch of Magnox Electric plc took a giant leap, investing significant resources into the modernization of their training simulators. New hardware was built, including a new simulator room. The simulator software was ported from Unix running on outdated servers to new servers running Microsoft Windows NT. Perhaps most significantly, major model enhancements were made to key plant systems to significantly increase the likeness of each simulator to its reference plant. The upgrade to NT, the addition of state-of-the-art instructor stations, and some of the model enhancements were achieved with SimPort, an all-inclusive simulation package provided by DS and S. This paper will provide a more detailed view of the Magnox modular simulators, including how they are used and how they have benefited from the enhancements and upgrades implemented during the project. (author)

  15. Regulations and classification advice: transport safety

    International Nuclear Information System (INIS)

    Davies, M.; Owen, K.

    1990-01-01

    The packaging of radioactive material for transport must conform with the regulations of the International Atomic Energy Agency (IAEA). These regulations are extensive and complex and require specialist interpretation. Packaging must be designed to contain the material, to limit radiation to safe levels, and to maintain the material in a safe state under both normal and accident conditions. British Nuclear Fuels Ltd. (BNFL) developed the TRANAID expert system to provide automated expert advice on the subject. It is used at BNFL and by other users internationally. The system was produced to meet an internal BNFL emphasis on accurate consistent and reliable interpretation of the complex IAEA regulations; and to provide a commercial product which would meet an external need. TRANAID provides reliable and consistent advice on safe transport procedures which reduce the workload on scarce skilled personnel, and allows them to concentrate on their primary task of packaging design. TRANAID also avoids overclassifying radioactive shipments, which would lead to the use of more expensive packaging than strictly is required. The IAEA regulations are applied internationally, and so there is a large potential worldwide market. The indications from the initial response are that future sales and use are expected to more than cover the investment. Other non-quantifiable benefits include the provision of consistent advice within a uniform approach, the safe-guarding of knowledge of the IAEA regulations, training and improvement in the expertise of users, improved management control, and enhancement of the professional image of BNFL. (author)

  16. Safety management systems and their role in achieving high standards of operational safety

    International Nuclear Information System (INIS)

    Coulston, D.J.; Baylis, C.C.

    2000-01-01

    Achieving high standards of operational safety requires a robust management framework that is visible to all personnel with responsibility for its implementation. The structure of the management framework must ensure that all processes used to manage safety interlink in a logical and coherent manner, that is, they form a management system that leads to continuous improvement in safety performance. This Paper describes BNFL's safety management system (SMS). The SMS has management processes grouped within 5 main elements: 1. Policy, 2. Organisation, 3. Planning and Implementation, 4. Measuring and Reviewing Performance, 5. Audit. These elements reflect the overall process of setting safety objective (from Policy), measuring success and reviewing the performance. Effective implementation of the SMS requires senior managers to demonstrate leadership through their commitment and accountability. However, the SMS as a whole reflects that every employee at every level within BNFL is responsible for safety of operations under their control. The SMS therefore promotes a proactive safety culture and safe operations. The system is formally documented in the Company's Environmental, Health and Safety (EHS) Manual. Within in BNFL Group, the Company structures enables the Manual to provide overall SMS guidance and co-ordination to its range of nuclear businesses. Each business develops the SMS to be appropriate at all levels of its organisation, but ensuring that each level is consistent with the higher level. The Paper concludes with a summary of BNFL's safety performance. (author)

  17. Radioactive waste disposal by UKAEA establishments during 1980 and associated environmental monitoring results

    International Nuclear Information System (INIS)

    Flew, E.M.

    1981-09-01

    This report gives details of the amounts of solid and liquid radioactive waste disposed of by the principal establishments of the UKAEA during 1980. Waste arising at the UKAEA Nuclear Power Development Laboratories at Windscale and Springfields, which are both situated on British Nuclear Fuels Ltd. (BNFL)-sites, is disposed of by BNFL and included in their authorisations. Discharges to atmosphere of airborne radioactive waste are also included in the report. A summary of the results of the environmental monitoring programmes carried out in connection with the radioactive waste discharges is given. (author)

  18. Magnox waste storage complex

    International Nuclear Information System (INIS)

    Anon.

    1990-01-01

    This article looks at the design and construction of British Nuclear Fuel Limited's (BNFL) Magnox waste storage complex by Costain Engineering Limited. Magnox swarf from fuel decanning is stored underwater in specially designed silos. Gas processing capabilities from Costain Engineering Limited and the experience of BNFL combined in this project to provide the necessary problem-solving skills necessary for this waste storage upgrading and extension project. A retrofitted inerting facility was fitted to an existing building and a new storage extension was fitted, both without interrupting reprocessing operations at Sellafield. (UK)

  19. Radioactive waste disposal by UKAEA establishments during 1978 and associated environmental monitoring results

    International Nuclear Information System (INIS)

    Flew, E.M.

    1979-05-01

    This report gives details of the amounts of solid and liquid radioactive waste disposed of by the principal establishments of the UKAEA during 1978. Waste arising at the UKAEA Nuclear Power Development Laboratories at Windscale and Springfields, which are both situated on British Nuclear Fuels Ltd. (BNFL) sites, is disposed of by BNFL and included in their authorisations. Discharges to atmosphere of airborne radioactive waste are also included in the report. A summary of the results of the environmental monitoring programmes carried out in connection with the radioactive waste discharges is given. (author)

  20. Tank Farm Contractor Waste Remediation System and Utilization Plan

    International Nuclear Information System (INIS)

    KIRKBRIDE, R.A.

    1999-01-01

    The Tank Waste Remediation System Operation and Utilization Plan updates the operating scenario and plans for the delivery of feed to BNFL Inc., retrieval of waste from single-shell tanks, and the overall process flowsheets for Phases I and II of the privatization of the Tank Waste Remediation System. The plans and flowsheets are updated with the most recent tank-by-tank inventory and sludge washing data. Sensitivity cases were run to evaluate the impact or benefits of proposed changes to the BNFL Inc. contract and to evaluate a risk-based SST retrieval strategy

  1. Tank Farm Contractor Operation and Utilization Plan [SEC 1 Thru 3

    Energy Technology Data Exchange (ETDEWEB)

    KIRKBRIDE, R.A.

    1999-05-04

    The Tank Waste Remediation System Operation and Utilization Plan updates the operating scenario and plans for the delivery of feed to BNFL Inc., retrieval of waste from single-shell tanks, and the overall process flowsheets for Phases I and II of the privatization of the Tank Waste Remediation System. The plans and flowsheets are updated with the most recent tank-by-tank inventory and sludge washing data. Sensitivity cases were run to evaluate the impact or benefits of proposed changes to the BNFL Inc. contract and to evaluate a risk-based SST retrieval strategy.

  2. Performance assessment for low-level waste disposal in the UK

    Energy Technology Data Exchange (ETDEWEB)

    Ashworth, A.B. [UK Dept. of the Environment, London (United Kingdom)

    1995-12-31

    British Nuclear Fuels plc (BNFL) operate a site for the disposal of Low Level Radioactive Waste at Drigg in West Cumbria, in North-West England. HMIP are responsible for the regulation of the site with regard to environmental discharges of radioactive materials, both operational and post-closure. This paper is concerned with post-closure matters only. Two post-closure performance assessments have been carried out for this site: one by the National Radiological Protection Board (NRPB) in 1987; and a subsequent one carried out on behalf of HMIP, completed in 1991. Currently, BNFL are preparing a Safety Case for continued operation of the Drigg site, and it expected that the core of this Case will comprise BNFL`s own analysis of post-closure performance. HMIP has developed procedures for the assessment of this Case, based upon experience of the previous Drigg assessments, and also upon the experience of similar work carried out in the assessment of Intermediate Level Waste (ILW) disposal at both deep and shallow potential sites. This paper describes the more important features of these procedures.

  3. Probabilistic risk assessment for back-end facilities: Improving the treatment of fire and explosion scenarios

    International Nuclear Information System (INIS)

    Sunman, C.R.J.; Campbell, R.J.; Wakem, M.J.

    1996-01-01

    The nuclear reprocessing facilities at Sellafield are a key component of the International business of BNFL. The operations carried out at the site extend from the receipt and storage of irradiated fuel, chemical reprocessing, plutonium and uranium finishing, through mixed oxide fuel production. Additionally there are a wide range of supporting processes including solid waste encapsulation, vitrification, liquid waste evaporation and treatment. Decommissioning of the site's older facilities is also proceeding. The comprehensive range of these activities requires that the safety assessment team keeps up to date with developments in the field, as well as conducting and sponsoring appropriate research into methodologies and modelling in order to deliver a cost effective, timely service. This paper will review the role of Probabilistic Risk Assessment (PRA) in safety cases for operations at Sellafield and go on to describe some areas of PRA methodology development in the UK and in which BNFL is a contributor. Finally the paper will summarise some specific areas of methodology development associated with improving the modelling of fire and explosion hazards which are specific to BNFL. (author)

  4. Development and validation of the ENIGMA code for MOX fuel performance modelling

    International Nuclear Information System (INIS)

    Palmer, I.; Rossiter, G.; White, R.J.

    2000-01-01

    The ENIGMA fuel performance code has been under development in the UK since the mid-1980s with contributions made by both the fuel vendor (BNFL) and the utility (British Energy). In recent years it has become the principal code for UO 2 fuel licensing for both PWR and AGR reactor systems in the UK and has also been used by BNFL in support of overseas UO 2 and MOX fuel business. A significant new programme of work has recently been initiated by BNFL to further develop the code specifically for MOX fuel application. Model development is proceeding hand in hand with a major programme of MOX fuel testing and PIE studies, with the objective of producing a fuel modelling code suitable for mechanistic analysis, as well as for licensing applications. This paper gives an overview of the model developments being undertaken and of the experimental data being used to underpin and to validate the code. The paper provides a summary of the code development programme together with specific examples of new models produced. (author)

  5. 'Material unaccounted for' (MUF)

    International Nuclear Information System (INIS)

    1977-01-01

    MUF is an item of importance in materials accounting measures now embodied in international safeguard arrangements, and in recent public debates requests have been made that the figures for MUF appearing in the Atomic Energy Authority and British Nuclear Fuels Ltd. records should be published. Joint statements issued by the UKAEA and BNFL in July 1977 are here published. These statements describe the procedures for nuclear materials accounting at AEA and BNFL sites and the nature of the inventory differences (MUF) that arise in all nuclear materials accounting operations. Figures for highly enriched U and Pu are included. (U.K.)

  6. Fuel reprocessing and waste management in the UK

    International Nuclear Information System (INIS)

    Heafield, W.; Griffin, N.L.

    1994-01-01

    The currently preferred route for the management of irradiated fuel in the UK is reprocessing. This paper, therefore, concentrates on outlining the policies, practices and achievement of British Nuclear Fuels plc (BNFL) associated with the management of its irradiated fuel facilities at Sellafield. The paper covers reprocessing and how the safe management of each of the major waste categories is achieved. BNFL's overall waste management policy is to develop, in close consultation with the regulatory authorities, a strategy to minimize effluent discharges and provide a safe, cost effective method of treating and preparing for disposal all wastes arising on the site

  7. Gas centrifuge bibliography 1980-1982

    International Nuclear Information System (INIS)

    Lowe, G.E.; Morrison, M.

    1983-06-01

    A bibliography, with abstract, is presented of the gas centrifuge literature published from 1980 to 1982 inclusive. It supplements PG Information Series 25 (CA), BNFL Information Series 15 (CA) and BNFL Information Series 23 (CA), which covered the periods 1895 to 1970, 1970 to 1974, and 1975 to 1979 respectively. After bibliographies and books and pamphlets, the main list is arranged chronologically under the headings, Reports, Journal articles, and Conference papers. Items omitted from the earlier bibliographies or received too late for inclusion in this, have been listed separately. There are author, report number and subject indexes. (U.K.)

  8. The commercial role for centrifuge enrichment

    International Nuclear Information System (INIS)

    Readle, P.H.; Wilcox, P.

    1987-01-01

    The enrichment market is extremely competitive and capacity greatly exceeds demand. BNFL [British Nuclear Fuels Ltd.] is in a unique position in having commercial experience of the two enrichment technologies currently used industrially: diffusion, and centrifuge enrichment through its associate company Urenco. In addition, BNFL is developing laser enrichment techniques as part of a UK development programme. The paper describes the enrichment market, briefly discusses the relative merits of the various methods of uranium enrichment and concludes that the gas centrifuge will be best able to respond to market needs for at least the remainder of the century. (author)

  9. Korea prospects

    International Nuclear Information System (INIS)

    Wyman, V.

    1990-01-01

    Contacts between the South Korean nuclear industry and a combined United Kingdom mission representing AEA Technology and British Nuclear Fuels Limited (BNFL) are reported. Prospects for entering the Korean market in two areas are perceived. The first is waste management and the second is the Safe Integral Reactor (SIR), an advanced pressurized water reactor design. AEA Technology and three collaborators have been promoting SIR as an inherently safe reactor design. Korean interest could be expressed in financial backing for the building of SIR stations in Korea and the opportunity could arise for BNFL to win fuel supply contracts. (UK)

  10. Evaluation of the safety of vitrified high level waste shipments from UK to continental Europe by sea

    International Nuclear Information System (INIS)

    Lange, F.; Fett, H.; Hormann, E.; Rowekamp, M.; Elston, B.; Slawson, G.; Cheshire, R.; Schneider, T.; Raffestin, D.

    1998-10-01

    This document, prepared in the framework of a study for the European Commission in collaboration with the GRS (Germany and BNFL (United Kingdom), relates to the evaluation of the safety associated to the maritime transport of vitrified wastes from the United Kingdom towards Europe. With this intention, a travel of 1000 nautical miles (1852 km) was considered and a detailed analysis of the boat used by BNFL has been realized in order to elaborate a fault tree, for scenarios able to generate mechanical and thermal stresses significant on the transport packages (type B-packages). (A.L.B.)

  11. Implications for providers of nuclear power plants, materials and services

    International Nuclear Information System (INIS)

    May, D.

    2000-01-01

    BNFL does not agree with the IEA business prediction showing a decline in the share of electricity generated by nuclear power over the next 20 years. On the contrary BNFL believes that lifetime extension and continued new build will help maintain or even increase the share of electricity generated by nuclear power. One reason why new nuclear build programmes have been reduced is because existing reactors are operating for longer and at higher performance than ever before. As reactor lifetimes are extended new business opportunities will emerge concerning the upgrading of different systems from nuclear control systems to steam turbines. (A.C.)

  12. M4/12 package project - development of a package for transport of new MOX fuel in Europe

    Energy Technology Data Exchange (ETDEWEB)

    Kaye, B.R.; Porter, I.; Ashley, P. [BNFL, Warrington, Cheshire (United Kingdom)

    2004-07-01

    BNFL has a requirement to deliver new MOX fuel from the Sellafield MOX Plant (SMP) to its customers in mainland Europe. To satisfy this requirement, a transport system has been developed which complies with national and international regulations and conventions relating to the transport of Category 1 materials. Fundamental to this system is the transport package. BNFL has designed, developed, and is manufacturing a new transport package, the M4/12, This paper gives a brief overview of the overall transport system and then goes on to describe the development of the M4/12 package with particular emphasis on the novel features of the design.

  13. Results of the recent investigations of the accuracy of C-PORCA code

    International Nuclear Information System (INIS)

    Pos, I.

    2001-01-01

    During the last year it was an essential demand to establish the C-PORCA code accuracy concerning the newly developed BNFL fuel. As it is well known the BNFL fuel assembly developed for the NPP Paks contains fuel pins with gadolinium. These pins are situated near the central tube so their unusual effects to be investigated. At the present investigation the C-PORCA code and the APA-H Westinghouse code system results were compared. During this comparison the differences between node and pin wise power distributions have been calculated as well. The fulfilled test have reinforced the applicability and capability of the C-PORCA code for WWER-440 core analysis (Authors)

  14. The Drigg low-level waste site

    International Nuclear Information System (INIS)

    1992-01-01

    Safe disposal of waste is a vital aspect of any industrial operation whether it be production of plastics, steel or chemicals or handling of radioactive materials. Appropriate methods must be used in every case. Radioactive waste falls into three distinct categories - high, intermediate and low-level. It is the solid low-level waste making up over 90% of the total which this booklet discusses. British Nuclear Fuels plc (BNFL) operates a site for the disposal of solid low-level waste at Driggs, some six kilometres south of Sellafield in West Cumbria. The daily operations and control of the site, the responsibility of the BNFL Waste Management Unit is described. (author)

  15. M4/12 package project - development of a package for transport of new MOX fuel in Europe

    International Nuclear Information System (INIS)

    Kaye, B.R.; Porter, I.; Ashley, P.

    2004-01-01

    BNFL has a requirement to deliver new MOX fuel from the Sellafield MOX Plant (SMP) to its customers in mainland Europe. To satisfy this requirement, a transport system has been developed which complies with national and international regulations and conventions relating to the transport of Category 1 materials. Fundamental to this system is the transport package. BNFL has designed, developed, and is manufacturing a new transport package, the M4/12, This paper gives a brief overview of the overall transport system and then goes on to describe the development of the M4/12 package with particular emphasis on the novel features of the design

  16. Advertising is magic

    International Nuclear Information System (INIS)

    Haskins, Louise

    1999-01-01

    Full text: Now in its fourth year, BNFL's advertising strategy continues to evolve and build upon the communication achievements of previous years. The case study this year will reflect upon progress so far and will concentrate specifically on the 1998 campaign development. It will begin by briefly reiterating the role we believe advertising plays in the communications mix and by recapping on the theoretical framework upon which the strategy continues to be based. Last year, I presented a case study on the development of BNFL's second television advertisement and supporting media. This year, I will present opinion research data which indicates that BNFL has, indeed, begun to detach itself from the contentious debate which surrounds the nuclear industry in general. Verbatim comments from respondents demonstrate that BNFL is now being perceived more widely within the UK as a successful corporate entity. The presentation will concentrate on the decision-making and research process which led us to select the content of our third advertising campaign. One key consideration being the impact of BNR:s merger with Magnox Electric plc and how their activity was incorporated into the overall advertising strategy. Having established key image characteristics through describing BNFL's scientific achievements and, more recently, BNFL's fuel recycling capabilities, the presentation will outline why this time we have opted for a total capability' advertisement whilst endeavouring to retain the five key image criteria which are at the heart of the strategy. Specific areas covered will include our clearance of the advertisement through the UK's advertising regulatory bodies (the Broadcast Advertising Clearance Centre (BACC) and the Independent Television Commission (ITQ). This in itself will demonstrate the importance of gaining detailed substantiation and legal clearance of the advertising claims made. Finally, we will share our experiences of each production phase, not least, the

  17. Click - nuclear energy

    International Nuclear Information System (INIS)

    1986-01-01

    The activities of British Nuclear Fuels are listed, explained and illustrated. It offers a complete cycle from uranium enrichment, fuel manufacture and transport, to fuel reprocessing and radioactive waste management. The uranium fission process is explained as are the basic principles of Magnox and Advanced Gas Cooled Reactors. BNFL's head office is at Risley in Cheshire and it has sites at Capenhurst (uranium enrichment plant), Springfields (fuel manufacturing plant) and Sellafield (fuel reprocessing plant). It owns Calder Hall and Chapelcross nuclear power stations. Safety is a major consideration and strict safety regulations are observed at all sites. BNFL also encourages public interest in its activities. This booklet is part of its public information effort. (U.K.)

  18. Radioactive lobsters put squeeze on Sellafield

    Energy Technology Data Exchange (ETDEWEB)

    Anon.

    1996-11-01

    British Nuclear Fuels is facing a new controversy over its Sellafield Works in Cumbria. Levels of the radioactive isotope technetium-99 in lobsters close to the works have risen 40-fold since 1993 -and now far exceed EC standards for contamination of food after a nuclear accident. Radioactive doses to local seafood consumers have been rising steeply since BNFL commissioned a new enhanced actinide removal plant (EARP) in 1994. The Environment Agency has now asked BNFL to consider ways of reducing technetium-99 discharges from the plant - but the company is also under pressure to maintain throughput to meet the safety concerns of the Nuclear Installations Inspectorate (NII) and avoid disrupting the reprocessing of spent Magnox reactor fuel. (UK).

  19. Radioactive lobsters put squeeze on Sellafield

    International Nuclear Information System (INIS)

    Anon.

    1996-01-01

    British Nuclear Fuels is facing a new controversy over its Sellafield Works in Cumbria. Levels of the radioactive isotope technetium-99 in lobsters close to the works have risen 40-fold since 1993 -and now far exceed EC standards for contamination of food after a nuclear accident. Radioactive doses to local seafood consumers have been rising steeply since BNFL commissioned a new enhanced actinide removal plant (EARP) in 1994. The Environment Agency has now asked BNFL to consider ways of reducing technetium-99 discharges from the plant - but the company is also under pressure to maintain throughput to meet the safety concerns of the Nuclear Installations Inspectorate (NII) and avoid disrupting the reprocessing of spent Magnox reactor fuel. (UK)

  20. Development of a virtual training simulator for a challenging refurbishment task

    International Nuclear Information System (INIS)

    Mort, P.E.

    1996-01-01

    The development by British Nuclear Fuels plc BNFL of a training simulator for a plant modification task, the Raffinate Project, is described. The Project involves the remote removal of a section of a vertical process pipeline, welding a new pipe to the upper part and installing a new cap on the lower part. The equipment required to carry out this task comprises a number of work heads, a carriage mounted manipulator system and ancillary equipment including 22 closed-circuit television cameras. The technology put together to create the training simulator for this operation incorporates virtual reality and graphic simulation techniques researched by BNFL's Remote Handling and Robotics Programme over the past five years. (UK)

  1. Utilising the emergency planning cycle for the transport of radioactive material

    International Nuclear Information System (INIS)

    Fox, M.

    2004-01-01

    As a world leader in the transport of radioactive material (RAM) British Nuclear Fuels plc (BNFL) and its subsidiary Pacific Nuclear Transport Limited (PNTL) recognise the importance of adopting the emergency planning cycle. The emergency response arrangements prepared and maintained in support of the International Transport business have been developed through this cycle to ensure that their emergency response section may achieve its aim and that the business unit is able to respond to any International Transport related incident in a swift, combined and co-ordinated manner. This paper outlines the eight key stages of the planning cycle and the experience that BNFL has gained in respect of its emergency response activities

  2. Reprocessing in Europe

    Energy Technology Data Exchange (ETDEWEB)

    Rossney, G [United Reprocessors G.m.b.H., Karlsruhe (F.R. Germany)

    1976-04-01

    The status of reprocessing activities within the member organizations of United Reprocessors is reviewed. The U.K. government has approved overseas deals by BNFL which will help to pay for their planned plant of 1000 te U p.a. at Windscale. In Germany KEWA has selected a site at Aschenburg as a fuel cycle centre where they plan to build a utility financed reprocessing plant of 1500 te U p.a. France has formed a new fuel cycle corporation, Cogema, which hopes to participate in the large volume of Japanese business negotiated by BNFL. United Reprocessors have agreed to pool their technology which may be available to organisations wishing to construct reprocessing plants in their own countries.

  3. The management of solid radioactive waste at Sellafield and Drigg. V. 1

    International Nuclear Information System (INIS)

    1996-01-01

    Waste management at British Nuclear Fuel's (BNFL) Sellafield and Drigg sites has been assessed using an audit of solid low level and intermediate level radioactive waste, undertaken by a joint inspection team from the Nuclear Installations Inspectorate and the Inspectorate of Pollution. The conditions of waste storage and record keeping observed by the team are reported for each solid waste facility. Radioactive waste management was found to be variable, with a number of storage facilities less than satisfactory. BNFL were shown to be making strenuous efforts to rectify this. Record keeping was found to be satisfactory for all current and recent waste storage. Historic waste accumulations, however, have yet to be quantified and characterised. (UK)

  4. Introduction to Papers 3-5. The UK industry's strategy for radioactive waste management

    International Nuclear Information System (INIS)

    Passant, F.H.

    1989-01-01

    The waste management policies and strategies of the main radioactive waste producers in the UK, namely the CEGB, BNFL and the UKAEA are summarised. Three papers will be published in the Proceedings of this Conference, giving details, for the CEGB, BNFL and the UKAEA of individual policies and strategies outlining how they have developed and are being implemented. An overview of the strategy for each type of waste with some examples of the approach being followed, is given. The key elements of radioactive waste management policy and strategy are set down by the Government, in various White Papers, and the detailed Industry strategy is consistent with these, indeed it is determined largely by them. (author)

  5. A lot of happy faces and a lot of hard work

    International Nuclear Information System (INIS)

    Williams, Bob

    1995-01-01

    Business is selling in ever more competitive markets, under continuous pressure to innovate, improve quality, reduce costs. The nuclear industry is of course no exception to this change. During 1994, BNFL continued to demonstrate this support and commitment to the community through a range of corporate, divisional and site initiatives, amounting to a spend of some 5 million pounds. This funding was spread across education and university links, employee secondment, community involvement and sponsorship and urban regeneration. The commercial activities of BNFL support jobs and generate income which benefits both local and national communities. However, the Company acknowledges that in order to play its full part as a good corporate citizen, it should put something back into the communities from which it draws its workforce and licence to operate. Thriving local, regional and national communities are good for BNFL, in terms of long-term survival, short-term income generation, general well-being and for staff recruitment retention and motivation. Community involvement activities should, therefore, be viewed as 'enlightened self interest'. Against this background, the first action from our strategy review is that the prime area for community involvement will be the North West of England as a whole, with the areas in which we operate as a major employer targeted for specific action

  6. Uses of biotechnology in waste treatment

    International Nuclear Information System (INIS)

    Holmes, R.G.G.; Benson, J.

    1996-01-01

    BNFL have invested in a Biotechnology programme to address waste treatment problems. The use of biotechnology to destroy organic pollutants is well known and has been successfully employed both in-situ and ex-situ. The BNFL approach has been to concentrate on the interaction of microbial systems with inorganic materials. This study has resulted in two major programmes of work that show every indication of being suitable for large scale application. The first programme of work investigated using, to decontaminate concrete surfaces, the phenomena of concrete degradation by sulphur oxidizing bacteria. Laboratory tests proved encouraging and have resulted in a Co-operative Research and Development Agreement (CRADA), between BNFL and Lockheed Martin Idaho Technologies Company for the INEL site. The CRADA will lead to a demonstration of the technology. The second major area of investigation is the development of an integrated bioremediation process for the removal and recovery of toxic heavy metals from contaminated land. The two stage process, which can be employed in an in-situ or ex-situ mode, involves the use of indigenous micro-organisms to generate sulphuric acid and environmental consortia to generate hydrogen sulphide. This project has reached the point of field trials. Results from both programmes will be presented and their applications at nuclear sites detailed

  7. Advanced enrichment techniques

    International Nuclear Information System (INIS)

    Johnson, A.

    1988-01-01

    BNFL is in a unique position in that it has commercial experience of diffusion enrichment, and of centrifuge enrichment through its associate company Urenco. In addition BNFL is developing laser enrichment techniques as part of a UK development programme in this area. The paper describes the development programme which led to the introduction of competitive centrifuge enrichment technology by Urenco and discusses the areas where improvements have and will continue to be made in the centrifuge process. It also describes the laser development programme currently being undertaken in the UK. The paper concludes by discussing the relative merits of the various methods of uranium enrichment, with particular reference to the enrichment market likely to obtain over the rest of the century

  8. Annual report and accounts 1985-86

    International Nuclear Information System (INIS)

    1986-01-01

    British Nuclear Fuels plc (BNFL) provides a complete nuclear fuel cycle service at its five sites in N.W. England and southern Scotland. This covers fuel manufacture (at Springfields), uranium enrichment (at Capenhurst), reprocessing (at Sellafield), reprocessing engineering (at Risley) and the operation of two nuclear power stations (at Chapelcross and Calder Hall). BNFL employs over 16,000 people and had a turnover of over Pound600 million in 1986. The report covers all aspects of the Company's work and is illustrated with photographs and diagrams. It highlights the work of some individuals who work in a variety of areas for the company. Safety and environmental protection are emphasised. The accounts are set out in detail with notes of explanation on the balance sheet. (UK)

  9. Thermal Analysis of the SAFKEG Package for Long Term Storage

    International Nuclear Information System (INIS)

    NARENDRA, GUPTA

    2005-01-01

    Interim plutonium storage for up to 10 years in the K-reactor building is currently being planned at Savannah River Site (SRS). SAFKEG package could be used to store Pu metal and oxide (PuO2) in the K-reactor complex with other packagings like 9975. The SAFKEG is designed for carrying Type-B materials across the DOE complex and meets the 10CFR71 requirements. Thermal analyses were performed to ensure that the temperatures of the SAFKEG components will not exceed their temperature limits under the K-reactor storage conditions. Thermal analyses of the SAFKEG packaging with three content configurations using BNFL 3013 outer container (Rocky Flats, SRS bagless transfer cans, and BNFL inner containers) were performed for storage of PuO2 and plutonium metal

  10. Advanced enrichment techniques

    International Nuclear Information System (INIS)

    Johnson, A.

    1987-01-01

    BNFL is in a unique position in that it has commercial experience of diffusion enrichment, and of centrifuge enrichment through its associate company Urenco. In addition BNFL is developing laser enrichment techniques as part of a UK development programme in this area. The paper describes the development programme which led to the introduction of competitive centrifuge enrichment technology by Urenco and discusses the areas where improvements have and will continue to be made in the centrifuge process. It also describes the laser development programme currently being undertaken in the UK. The paper concludes by discussing the relative merits of the various methods of uranium enrichment, with particular reference to the enrichment market likely to obtain over the rest of the century. (author)

  11. Annual report on radioactive discharges and monitoring of the environment 1988

    International Nuclear Information System (INIS)

    1989-01-01

    This report supplements BNFL's Health and Safety Annual Report and lists 1988 discharges and environmental monitoring for the following sites: Sellafield, Chapelcross, Drigg Storage and Disposal Site, Springfields Works, Capenhurst Works. (UK)

  12. Radionuclides in house dust

    Energy Technology Data Exchange (ETDEWEB)

    Fry, F A; Green, N; Dodd, N J; Hammond, D J

    1985-04-01

    Discharges of radionuclides from the British Nuclear Fuel plc (BNFL) reprocessing plant at Sellafield in Cumbria have led to elevated concentrations radionuclides in the local environment. The major routes of exposure of the public are kept under review by the appropriate authorising Government departments and monitoring is carried out both by the departments and by BNFL itself. Recently, there has been increasing public concern about general environmental contamination resulting from the discharges and, in particular, about possible exposure of members of the public by routes not previously investigated in detail. One such postulated route of exposure that has attracted the interest of the public, the press and Parliament arises from the presence of radionuclides within houses. In view of this obvious and widespread concern, the Board has undertaken a sampling programme in a few communities in Cumbria to assess the radiological significance of this source of exposure. From the results of our study, we conclude that, although radionuclides originating rom the BNFL site can be detected in house dust, this source of contamination is a negligible route of exposure for members of the public in West Cumbria. This report presents the results of the Board's study of house dust in twenty homes in Cumbria during the spring and summer of 1984. A more intensive investigation is being carried out by Imperial College. (author)

  13. Resource consequences of reducing disposal of radioactive waste to the environment

    International Nuclear Information System (INIS)

    Johnson, L.F.

    1988-01-01

    This paper considers some of the terms and definitions used in the optimisation of radioactive waste processing and looks at the background regulatory requirements and BNFL's own policy on waste management. It considers recent plants brought into operation and the impact that they have had on the discharge of low level radioactive effluent to the Irish Sea, and notes future plants to be installed at Sellafield. Plant improvements aimed at making further reductions of operator or public exposure will then be considered and the possible impact of the recent NRPB guidelines will be looked at against BNFL's overall policy on waste management. Finally, to bring the environmental impact of the Sellafield discharges into some perspective, consideration will be given to collective doses from other sources of radiation in the UK. (author)

  14. Lifetime management of Magnox power stations

    International Nuclear Information System (INIS)

    Smitton, C.

    1998-01-01

    Magnox Electric, which is, a subsidiary of BNFL, operates six nuclear power plants that have an average age of about 33 years. The procedures developed to maintain the plants and ensure nuclear safety in longer-term operation are reviewed. The technical limit on station lifetimes is expected to be determined by the effect of ageing on major reactor structures where replacement is impractical. Examination of the effect of ageing confirms that the stations are capable of operating to a life of at least 40 years. The economic factors affecting operation are reviewed, recognising the need to sell electricity in a competitive market. Recently Magnox Electric and BNFL have merged and all plant supporting Magnox operations are now within a single integrated company that will provide further opportunities for improved efficiency. (author)

  15. Safety assessment and licensing issues of low level radioactive waste disposal facilities in the United Kingdom

    Energy Technology Data Exchange (ETDEWEB)

    Fearnley, I. G. [British Nuclear Fuels Ltd., Sellafield (United Kingdom)

    1997-12-31

    More than 90% of radioactive waste generated in the United Kingdom is classified as low level and is disposed of in near surface repositories. BNFL owns and operates the principal facility for the disposal of this material at Drigg in West Cumbria. In order to fully optimise the use of the site and effectively manage this `national` resource a full understanding and assessment of the risks associated with the performance of the repository to safely contain the disposed waste must be achieved to support the application for the site authorization for disposal. This paper describes the approaches adopted by BNFL to reviewing these risks by the use of systematic Safety and Engineering Assessments supported in turn by experimental programmes and computations models. (author). 6 refs., 1 tab., 4 figs.

  16. Safety assessment and licensing issues of low level radioactive waste disposal facilities in the United Kingdom

    International Nuclear Information System (INIS)

    Fearnley, I. G.

    1997-01-01

    More than 90% of radioactive waste generated in the United Kingdom is classified as low level and is disposed of in near surface repositories. BNFL owns and operates the principal facility for the disposal of this material at Drigg in West Cumbria. In order to fully optimise the use of the site and effectively manage this 'national' resource a full understanding and assessment of the risks associated with the performance of the repository to safely contain the disposed waste must be achieved to support the application for the site authorization for disposal. This paper describes the approaches adopted by BNFL to reviewing these risks by the use of systematic Safety and Engineering Assessments supported in turn by experimental programmes and computations models. (author). 6 refs., 1 tab., 4 figs

  17. Reduction of BNFL discharges: The Alara Principle

    International Nuclear Information System (INIS)

    Mummery, P.W.

    1986-01-01

    Although the title identified as the subject is rather broad, it is proposed to concentrate on liquid waste discharges from Sellafield to illustrate the range of considerations in practise. Such discharges arise from the nature of the work carried out at Sellafield. This comprises principally storage of spent fuel elements, magnox AGR and LWR, dismanteling and reprocessing of spent fuel and storage of recovered uranium and plutonium, manufacture of plutonium-based fuel for the prototype fast reactor at Dounreay, and management of the resulting wastes

  18. Evaluation and Demonstration of the BNFL Ionsens

    International Nuclear Information System (INIS)

    Salaymeh, S.R.

    1999-01-01

    This report describes the technology, system, and process that has been developed and tested. It also discusses the technology''s advantages, disadvantages, system performance, and its effectiveness. A comparison to the baseline technologies as well as other competing technologies will be presented. This report will include a brief discussion of commercial availability and technology readiness for implementation and recommendations for its use

  19. How good is BNFL's health and safety?

    International Nuclear Information System (INIS)

    Berry, R.J.; Coulston, D.J.

    1989-01-01

    A historical perspective of the development of health and safety philosophy and practice within the nuclear industry is followed by a description of the Company's safety management system. This involves three elements, policy, implementation and audit. Data given on discharges to the environment and occupational dose. (U.K.)

  20. Annual report on radioactive discharges and monitoring of the environment 1986

    International Nuclear Information System (INIS)

    1987-01-01

    British Nuclear Fuels plc (BNFL) provides a comprehensive range of nuclear fuel cycle services, ie the purification and processing of uranium ore concentrates, the enrichment of uranium, the manufacture of uranium and plutonium based fuels, the reprocessing of irradiated fuel, and the conditioning and storage of nuclear materials and radioactive wastes. Some of these activities give rise to discharges of radioactive isotopes to the environment. This annual report follows the pattern established in 1977 in that it gives information on radioactive discharges, through authorised and scheduled outlets, and on environmental monitoring for all of the Company's Works and sites, ie Sellafield Site and the Drigg Storage and Disposal Site; Chapelcross Works; Springfield Works and the Ulnes Walton Disposal Site; and Capenhurst Works. Where a site also encompasses laboratories of the United Kingdom Atomic Energy Authority (UKAEA) reference is made to the significance of the discharges from the latter. It also includes assessment of radiation doses to representative members of the most highly exposed group of the general population (the critical group) for the most important environmental pathways in the vicinity of each site. Information for the period 1971-76 inclusive has also been published by BNFL and prior to 1971, the year in which BNFL was formed, information was published by the UKAEA. An appendix contains certificates of Authorisation granted by the DOE, MAFF and Scottish Office imposing limits and conditions relating to methods of disposal and quantities to be discharged. (author)

  1. The implications of plant design on the life-time costs for nuclear fuel cycle facilities

    International Nuclear Information System (INIS)

    Macphee, D.S.; Hexter, B.C.; Young, M.P.; Wilson, B.J.

    1997-01-01

    Utilising the experience gained during many years of design and project management of nuclear plant, BNFL is now approaching the final stages of the construction and commissioning of the Sellafield MOX Plant (SMP) in the UK. The paper uses the SMP project to highlight the benefits of these experiences, in particular addressing the implications of the approach to plant design on life time costs. In addition to providing BNFL with a state of the art, commercial scale MOX fuel fabrication facility, the construction of this 120 tHM/yr facility, which is currently in the advanced stages of commissioning, represents a significant demonstration of the design and project management skills of BNFL Engineering Ltd. As well as meeting the main process requirements, the plant design incorporates the highest standards of safety, together with input from the future plant operators and potential customers. As befits a commercial scale plutonium handling facility, SMP also incorporates material accountancy and security provisions that will meet all international requirements. Design, construction and commissioning of this complex and highly automated plant, has benefited from a totally integrated approach to design and documentation that considers not only project implementation but also overall lifetime costs. In addition, project management techniques, developed over many years of major project construction at Sellafield, have been utilised in order to ensure successful project implementation against a background of significant technical challenge and 'fast track' timescales. (author)

  2. Development and Presentation of the Drigg Post-Closure Safety Case

    International Nuclear Information System (INIS)

    Kelly, Eugene; Watts, Len; Grimwood, Paul

    2001-01-01

    Drigg is an operational facility for the near-surface disposal of solid low level radioactive waste (LLW). The disposal facility is located in Cumbria, north-west England, near the Sellafield nuclear site, and is owned and operated by British Nuclear Fuels plc (BNFL). Disposals at Drigg are carried out under the terms of an authorisation granted by the UK Environment Agency. Periodically the Drigg authorisation is subject to formal regulatory review. The current regulatory guidance, 'Disposal Facilities on Land for Low and Intermediate Level Radioactive Wastes: Guidance on Requirements for Authorisation' (the GRA) was published in 1997 and contains guidance on the principles and requirements against which the Environment Agency will consider applications for disposal authorisation. BNFL has undertaken to produce an updated Drigg postclosure safety case (PCSC) in September 2002 to support the next authorisation review. In preparation for this, BNFL published a 'Status Report on the Development of the 2002 Drigg PCSC' in March 2000. This paper discusses the main components of the Drigg PCSC and how they relate to each other. Central to the safety case will be a systematic, post-closure radiological safety assessment (PCRSA). However the main focus of this paper is on the other main components of the PCSC which are presented in conjunction with the PCRSA to make a complete and integrated safety case. In addition other confidence building activities which are key to developing and presenting the safety case are discussed, in particular communications with the stakeholders

  3. Health and safety annual report 1987

    International Nuclear Information System (INIS)

    1988-01-01

    The principal activities and organisation of BNFL are reviewed in relation to the impact these activities have on the workforce, members of the general public and the environment, together with services for occupational safety within the company. (author)

  4. Developments in fuel manufacturing

    International Nuclear Information System (INIS)

    Ion, S.E.; Harrop, G.; Maricalva Gonzalez, J.

    1995-01-01

    The status of the investment and R and D programmes in the UK and Spanish fuel fabrication facilities is outlined. Due to a number of circumstances, BNFL and ENUSA have been in the forefront of capital investment, with associated commitment to engineering and scientific research and development. Carrying through this investment has allowed the embodiment of proven state of the art technologies in the design of fuel fabrication plants, with particular emphasis on meeting the future challenge of health and safety, and product quality, at an acceptable cost. ENUSA and BNFL currently supply fuel, not only to their respective 'home' markets but also to France, Belgium, Sweden, and Germany. Both organisations employ an International Business outlook and partake in focused and speculative R and D projects for the design and manufacture of nuclear fuel. (orig./HP)

  5. Development and Evaluation of a Pilot Prototype Automated Online Sampling System

    International Nuclear Information System (INIS)

    Whitaker, M.J.

    2000-01-01

    An automated online sampling system has been developed for the BNFL-Hanford Technetium Monitoring Program. The system was designed to be flexible and allows for the collection and delivery of samples to a variety of detection devices that may be used

  6. NTL 11 spent fuel flask - meeting the challenge of regulatory and technological change

    International Nuclear Information System (INIS)

    Cory, A.R.

    2004-01-01

    By June 2005, when shipments of spent fuel for reprocessing from Germany are concluded, the NTL11 flask type will have been responsible for transporting a total of 1500 tonnes of heavy metal in the form of spent fuel. Excluding domestic transports in France and the UK, this represents 25% of the total European spent fuel transported for reprocessing since the flasks came into service in 1977. Approximately 40% of the total for the flask type will have been transported to BNFL's Sellafield facility, the remainder to Cogema at La Hague. The NTL11 flask can justifiably be described as being the workhorse of BNFL's European spent fuel transport business. The NTL11 flask started life under the ownership of Nuclear Transport Limited, an associate company of BNFL, and in recent years the original fleet of five flasks has been absorbed into the BNFL inventory. A recent build programme has seen a further four flasks added to the fleet, an expedient measure to cope with the additional transport requirements imposed by the need to meet the June 2005 deadline for the removal of contracted fuels from Germany. While there have been certain evolutionary changes affecting the package design, there have also been more significant changes in the Design Safety Case. These have sometimes been necessary to meet regulatory changes, or the challenges posed by the regulators. In other cases advantage has been taken of improvements in analytical techniques to demonstrate increased margins of operational safety. Where possible those margins have also been increased by other means, such as taking advantage of commercial trends to reduce package thermal loads. The NTL11 flask was designed around the reactor and fuel characteristics prevailing in the 1970's. Over the lifetime of the flask the responsible engineering teams have faced and met the successive challenges to develop the capability of the Package to face the changing requirements of the industry and the Transport Regulations. Both

  7. Customer satisfaction techniques applied to the transport of nuclear fuels to meet ISO 9001:2000 requirements

    International Nuclear Information System (INIS)

    Fisher, G.K.

    2004-01-01

    Understanding the needs of potential and existing customers is seen as essential to the continuing success of the nuclear fuel transport business. A recognised process utilised for this is the recording and measurement of customer satisfaction. This paper looks at what customer satisfaction means to BNFL International Transport in terms of, understanding what the customers needs are, supplying those needs or proposing appropriate alternatives, delivering on contractual obligations, in terms of the product or service being supplied to cost and time, listening to the changing needs of customers should this occur and monitoring the perception of customers in terms of performance. Within BNFL as a whole customer satisfaction is managed through the application of a Management Framework. Within this framework are set a number of values, these are focused on acknowledging social and environmental responsibilities while satisfying the needs of customers. Customer satisfaction is a key aspect of this philosophy

  8. Customer satisfaction techniques applied to the transport of nuclear fuels to meet ISO 9001:2000 requirements

    Energy Technology Data Exchange (ETDEWEB)

    Fisher, G.K. [BNFL (United Kingdom)

    2004-07-01

    Understanding the needs of potential and existing customers is seen as essential to the continuing success of the nuclear fuel transport business. A recognised process utilised for this is the recording and measurement of customer satisfaction. This paper looks at what customer satisfaction means to BNFL International Transport in terms of, understanding what the customers needs are, supplying those needs or proposing appropriate alternatives, delivering on contractual obligations, in terms of the product or service being supplied to cost and time, listening to the changing needs of customers should this occur and monitoring the perception of customers in terms of performance. Within BNFL as a whole customer satisfaction is managed through the application of a Management Framework. Within this framework are set a number of values, these are focused on acknowledging social and environmental responsibilities while satisfying the needs of customers. Customer satisfaction is a key aspect of this philosophy.

  9. Mixing of process heels, process solutions, and recycle streams: Results of the small-scale radioactive tests

    International Nuclear Information System (INIS)

    Lumetta, G.J.; Bramson, J.P.; Farmer III, O.T.; Greenwood, L.R.; Hoopes, F.V.; Mann, M.A.; Steele, M.J.; Steele, R.T.; Swoboda, R.G.; Urie, M.W.

    2000-01-01

    Various recycle streams will be combined with the low-activity waste (LAW) or the high-level waste (HLW) feed solutions during the processing of the Hanford tank wastes by BNFL, Inc. In addition, the LAW and HLW feed solutions will also be mixed with heels present in the processing equipment. This report describes the results of a test conducted by Battelle to assess the effects of mixing specific process streams. Observations were made regarding adverse reactions (mainly precipitation) and effects on the Tc oxidation state (as indicated by K d measurements with SuperLigreg s ign 639). The work was conducted according to test plan BNFL-TP-29953-023, Rev. 0, Small Scale Mixing of Process Heels, Solutions, and Recycle Streams. The test went according to plan, with only minor deviations from the test plan. The deviations from the test plan are discussed in the experimental section

  10. Optimum utilisation of the uranium resource

    International Nuclear Information System (INIS)

    Ion, S. E.; Wilson, P.D.

    1998-01-01

    The nuclear industry faces many challenges, notably to maximise safety, secure an adequate energy supply, manage wastes satisfactorily and achieve political acceptability. One way forward is to optimise together the various interdependent stages of the fuel cycle - the now familiar 'holistic approach'. Many of the issues will demand large R and D expenditure, most effectively met through international collaboration. Sustainable development requires optimum utilisation of energy potential, to which the most accessible key is recycling uranium and the plutonium bred from it. Realising anything like this full potential requires fast-neutron reactors, and therefore BNFL continues to sustain the UK involvement in their international development. Meanwhile, current R and D programmes must aim to make the nuclear option more competitive against fossil resources, while maintaining and developing the necessary skills for more advanced technologies The paper outlines the strategies being pursued and highlights BNFL 's programmes. (author)

  11. Discharge reductions-value for money?

    International Nuclear Information System (INIS)

    Morley, R G; Coates, R; Taylor, R H

    2004-01-01

    Through the Nuclear Liabilities Management Authority White Paper, the UK Government and the Regulators have signalled a commitment to further improving the operation of the regulatory regime and to its operating within the principles of proportionality, transparency, consistency and accountability which underpin the Government's approach to regulation in general. Particular emphasis is placed upon ensuring that there is greater consistency in the treatment of risk and hazard; proportionate and cost effective delivery of public, worker and environmental protection; and an open and transparently applied regulatory system. The paper uses the historical record of radioactive discharges from BNFL's Sellafield reprocessing site in the UK and seeks to identify what have been the key drivers for change, particularly over the past 20 years of significant discharge reductions. The paper examines the current context for ongoing and future discharges from the site, and the incorporation of the use of the concepts of best practicable environmental option and best practicable means. Intergovernmental commitments such as the OSPAR Sintra and Bremen statements and the developing UK policy framework are also considered, together with BNFL's work with a wide range of 'green' stakeholders. The paper outlines the principal components of BNFL's decision-making processes for discharge control and abatement; and how these interact with the relevant external pressures. It then analyses whether the overall drivers and outcomes align with the declared desire of the UK Government to ensure that the taxpayer receives value for money in the new national arrangements for managing historic nuclear liabilities

  12. Providing Radiation Protection Experts in the United Kingdom

    International Nuclear Information System (INIS)

    Partington, C.; Owen, D.

    2004-01-01

    The EEC Directive on Qualified Experts in Radiation Protection has been implemented in the United Kingdom by the Ionising Radiations Regulations 1999 (IRR99). These Regulations require Radiation Employers to appoint suitable Radiation Protection Advisers (RPA) who must be consulted in certain circumstances when starting work with, or using ionising radiations. Radiation Protection Advisers have to have a current certificate of competence and, to gain one of these, must have demonstrated their competence in one of two ways either by achieving a National Vocational Qualification in Radiation Protection Practice or by being Certificated by an Assessing Body. Assessing Bodies have to be recognised by the Health and Safety Executive, who undertake a rigorous assessment process to determine whether the proposed Assessing Body is fit to undertake RPA Assessments. By July 2003, only two such Assessing Bodies had been approved in the UK. These two Assessing Bodies are ? RPA 2000 a company established by the four leading Radiation Protection Professional Societies in the UK for assessing anyone in the UK as Radiation Protection Advisers, And ? BNFL established by BNFL to assess the competence of BNFL's own Radiation Protection Advisers. This paper will describe the standards against which Radiation Protection Advisers are assessed, the manner in which each of these two Assessing Bodies carry out the assessment process and their experience to date. The way in which Radiation Employers carry out the appointment process will also be described. Potential future developments of the Assessment Process and standards will also be discussed. (Author)

  13. A new approach to preparing safety cases for existing nuclear plant (COSR)

    International Nuclear Information System (INIS)

    Rice, S.A.; Buchan, A.B.

    2000-01-01

    BNFL is committed to achieving world class safety performance, through a process of continuously reviewing and improving its safety practices. In the mid 1990s, as part of this process, the company began to develop a new type of safety case, for existing non-reactor nuclear plants, called the continued operation safety report (COSR). Following a significant amount of development work from experts within BNFL and important contributions from its regulators, the first approved COSR was recently completed and submitted to the Nuclear Installations Inspectorate. The COSR aims to provide a visibly integrated safety and engineering case for the adequacy of continued operation of a nuclear facility. It achieves this by identifying the main plant structures, systems and components that have a safety function and provides the appropriate supporting engineering substantiation. The COSR aims to explore plant safety and identify worthwhile improvements. The document also aims to be reader-friendly by focusing on the main safety issues. It is therefore a slim safety summary which provides operators, safety specialists and regulators with an overview and introduction into the broader, more detailed safety case. This paper provides an overview of the COSR and its production process, describing the safety case improvements that have been made by comparing it to its predecessor, the fully developed safety case. The paper also illustrates the benefits of the COSR by providing current examples of its application on existing BNFL plant. Finally, the paper describes ongoing development work aimed at further improving the COSR and its production process. (author)

  14. Formulation of engineering design principles for the treatment of irradiated fuel and associated radioactive waste

    International Nuclear Information System (INIS)

    Banford, A.W.; Hanson, B.C.; Scully, P.J.; Taylor, R.

    2007-01-01

    The industrial scale treatment of irradiated fuel in the UK has resulted in BNFL developing extensive experience of the process design, build, commissioning, and operation necessary for successful nuclear processing plant. Much of the design experience now resides in Nexia Solutions (formally BNFL Research and Development Division) who have always defined and undertaken the extensive development programmes necessary to underpin the design at all stages of the project life-cycle. Since the 1990's, Nexia Solutions has built up a large portfolio of plant designs for a range of spent fuel applications, from fuel conditioning to partitioning and transmutation. In addition, by investigation of a large and diverse portfolio of technologies Nexia Solutions has developed innovative concepts for plant design that could present significant economic savings on conventional approaches. Using this experience and the lessons learned, we have developed and refined our own engineering design principles necessary for the successful design of commercial spent fuel and waste treatment plant. Our approach is to advocate an integral concept, with both science and engineering designs working in parallel during development. 4 foundation principles for success have been identified: -) understand the strategic objective, -) adopt a risk driven programme, -) engage in engineering activities early, and -) timely application of appropriate engineering methodologies. 2 Case studies presented in this paper: first, the BNFL segregated effluent treatment plant and secondly, the selection of a pyrochemical process for recycle of fast reactor, demonstrate how this approach has been adopted and the benefits that have been gained

  15. Annual report on occupational safety 1989

    International Nuclear Information System (INIS)

    1990-01-01

    This report presents detailed information on occupational safety relating to BNFL's employees for 1989 and data compared with the previous year. Routine monitoring, non-radiological safety and 'incidents' are discussed and 'statutory' whole-body exposures, nuclear incidents, lost-time accidents, and types of injury are tabulated. (author)

  16. Global Spent Fuel Logistics Systems Study (GSFLS). Volume 2A. GSFLS visit findings (appendix). Interim report

    Energy Technology Data Exchange (ETDEWEB)

    None

    1978-01-31

    This appendix is a part of the interim report documentation for the Global Spent Fuel Logistics System (GSFLS) study. This appendix provides the legal/regulatory reference material, supportive of Volume 2 - GSFLS Visit Finding and Evaluations; and certain background material on British Nuclear Fuel Limited (BNFL).

  17. The design and operation of the THORP central control room: a human factors perspective

    International Nuclear Information System (INIS)

    Reed, Julie.

    1996-01-01

    The new Thermal Oxide Reprocessing Plant (THORP) at British Nuclear Fuels (BNFL) Sellafield Site is now operational. This paper describes the Central Control Room (CCR), focusing on the control system components. Throughout the design, commissioning and operation of THORP, human factors played an important part. (author)

  18. International co-operation in the supply of nuclear fuel cycle services

    International Nuclear Information System (INIS)

    Allday, C.

    1977-01-01

    The paper draws on British Nuclear Fuels' (BNFL) wide experience of international collaboration in nuclear fuel process activities to examine the pros and cons of international agreements. Initially, the factors that influence the need to co-operate, the extent of possible co-operation and the alternative types of agreement, are reviewed. Next, the benefits, problems and risks associated with each function, such as management, financial R and D, marketing and operations that could be covered within the scope of an international agreement, are examined in detail. The paper continues by calling upon specific experience obtained by BNFL in the co-operation with other organizations over several years in both major and much smaller agreements, illustrating the rationale behind the co-operation, the resolution of 'teething' troubles and the present status of these organizations. In conclusion, the paper comments upon the effectiveness of collaboration agreements and identifies several requirements for international co-operation to succeed. (author)

  19. Windscale advanced gas-cooled reactor (WAGR) decommissioning project overview

    International Nuclear Information System (INIS)

    Pattinson, A.

    2003-01-01

    The current BNFL reactor decommissioning projects are presented. The projects concern power reactor sites at Berkely, Trawsfynydd, Hunterstone, Bradwell, Hinkley Point; UKAEA Windscale Pile 1; Research reactors within UK Scottish Universities at East Kilbride and ICI (both complete); WAGR. The BNFL environmental role include contract management; effective dismantling strategy development; implementation and operation; sentencing, encapsulation and transportation of waste. In addition for the own sites it includes strategy development; baseline decommissioning planning; site management and regulator interface. The project objectives for the Windscale Advanced Gas-Cooled Reactor (WAGR) are 1) Safe and efficient decommissioning; 2) Building of good relationships with customer; 3) Completion of reactor decommissioning in 2005. The completed WAGR decommissioning campaigns are: Operational Waste; Hot Box; Loop Tubes; Neutron Shield; Graphite Core and Restrain System; Thermal Shield. The current campaign is Lower Structures and the remaining are: Pressure vessel and Insulation; Thermal Columns and Outer Vault Membrane. An overview of each campaign is presented

  20. Radionuclides in house dust

    CERN Document Server

    Fry, F A; Green, N; Hammond, D J

    1985-01-01

    Discharges of radionuclides from the British Nuclear Fuel plc (BNFL) reprocessing plant at Sellafield in Cumbria have led to elevated concentrations radionuclides in the local environment. The major routes of exposure of the public are kept under review by the appropriate Government departments and monitoring is carried out both by the departments and by BNFL itself. Recently, there has been increasing public concern about general environmental contamination resulting from the discharges and, in particular, about possible exposure of members of the public by routes not previously investigated in detail. One such postulated route of exposure that has attracted the interest of the public, the press and Parliament arises from the presence of radionuclides within houses. In view of this obvious and widespread concern, the Board has undertaken a sampling programme in a few communities in Cumbria to assess the radiological significance of this source of exposure. From the results of our study, we conclude that, alt...

  1. A large decommissioning project with added value

    International Nuclear Information System (INIS)

    Clements, D.W.

    1998-01-01

    The East Tennessee Technology Park (ETTP) in Oak Ridge, Tennessee, is a centerpiece for the Department of Energy's Reindustrialization program, which seeks to convert formerly used facilities for broad, industrial purposes. BNFL and its partners have been charged with the decommissioning and decontamination of three large gaseous diffusion buildings. BNFL's prior experience with a similar site, Capenhurst, in the United Kingdom was successful in reducing the quantities and costs of low level wastes for disposal. In that program, over 99% of 160,000 tonnes of surface-contaminated materials were safely and cost-effectively treated. Resulting materials could thus be recycled for complete unrestricted re-use within the UK. Decommissioning and decontamination at the ETTP site will be informed by the prior experience and lessons learned. Specialized technologies and approaches developed at Capenhurst will find expression at ETTP. The result will be safe, cost-effective techniques that permit maximum recycle and further use of presently contaminated buildings for industrial purposes. (author)

  2. Precarious opportunity: Canada's changing nuclear energy policies and institutional choices. Chapter 1

    International Nuclear Information System (INIS)

    Doern, G.B.; Dorman, A.; Morrison, R.W.

    2001-01-01

    This article (Chapter One) discusses the two main scenarios typically advanced for Canada's nuclear energy future. The first view is that the nuclear energy industry can prosper and make an important contribution to energy and the environment in this age of climate change policy. This view is supported by some recent international studies which also express cautious optimism. A somewhat different view is the perception by some that the nuclear industry is economically in decline and environmentally questionable. These views have emerged as a result of recent serious safety concerns that have been raised about British nuclear Fuels Ltd (BNFL) regarding MOX fuel, where it has been alleged that data on safety were faked by BNFL workers. This article also provides an overview of how nuclear policy ideas, policy institutions, and policy interests have changed. Second, it draws out in more detail key policy and institutional choices confronting Canada's nuclear policy makers

  3. Work that lasts for decades

    International Nuclear Information System (INIS)

    Anon.

    1982-01-01

    The organization and financing of BNFL (British Nuclear Fuels Ltd) is described. Its activities - uranium enrichment, fuel manufacture and reprocessing, and radioactive waste processing - are discussed. Problems of world trade and competition in the nuclear field are considered. Programmes for future work and expansion are outlined. (U.K.)

  4. Product evaluation phase 1 report

    International Nuclear Information System (INIS)

    Fairhall, G.A.

    1984-01-01

    This report concerns the intermediate-level radioactive waste arisings from the reprocessing of irradiated nuclear fuel at BNFL Sellafield. Headings are: introduction (origin of waste; current stocks and future arisings); characterisation of sludges; initial evaluation of potential matrices (for solidification of waste in form suitable for disposal); waste simulation. (U.K.)

  5. Niobia-doped UO2 fuel manufacturing experience at British nuclear fuels Ltd

    International Nuclear Information System (INIS)

    Marsh, G.; Wood, G.A.; Perkins, C.P.

    1998-01-01

    BNFL Fuel Division has made niobia doped fuel for over twenty years in its Springfields Research and Development facilities. This paper reviews this experience together with feedback from successful in-reactor and laboratory tests. Recent experience in qualifying and manufacturing niobia doped fuel pellets for a European PWR will be described. (author)

  6. Fuel cycle and waste management: A perspective from British nuclear fuels plc

    International Nuclear Information System (INIS)

    Holmes, R.G.G.; Fairhall, G.A.; Robbins, R.A.

    1996-01-01

    The phrase fuel cycle and waste management implies two separate and distinct activities. British Nuclear Fuels plc (BNFL) has adopted a holistic approach to the fuel cycle that integrates the traditional fuel cycle activities of conversion to uranium hexafluoride, fuel fabrication, power generation, and reprocessing with waste arisings, its subsequent treatment, and disposal

  7. Main conclusions of a seminar on managing technical resources in a changing nuclear industry

    International Nuclear Information System (INIS)

    Storey, P.D.

    2000-01-01

    The author recapitulates the different points from I Mech E Conference (Managing Technical resources in a changing Nuclear Industry -London, 29 September 1999), as following: UK position, BNFL Magnox and AEAT, UK view from BEGL, view from WANO, UK view from UKAEA, USA view from PECO Energy, and view from OECD NEA

  8. Two new research melters at the Savannah River Technology Center

    International Nuclear Information System (INIS)

    Gordon, J.R.; Coughlin, J.T.; Minichan, R.L.; Zamecnik, J.R.

    2000-01-01

    The Savannah River Technology Center (SRTC) is a US Department of Energy (DOE) complex leader in the development of vitrification technology. To maintain and expand this SRTC core technology, two new melter systems are currently under construction in SRTC. This paper discusses the development of these two new systems, which will be used to support current as well as future vitrification programs in the DOE complex. The first of these is the new minimelter, which is a joule-heated glass melter intended for experimental melting studies with nonradioactive glass waste forms. Testing will include surrogates of Defense Waste processing Facility (DWPF) high-level wastes. To support the DWPF testing, the new minimelter was scaled to the DWPF melter based on melt surface area. This new minimelter will replace an existing system and provide a platform for the research and development necessary to support the SRTC vitrification core technology mission. The second new melter is the British Nuclear Fuels, Inc., research melter system (BNFL melter), which is a scaled version of the BNFL low-activity-waste (LAW) melter proposed for vitrification of LAW at Hanford. It is designed to process a relatively large amount of actual radiative Hanford tank waste and to gather data on the composition of off-gases that will be generated by the LAW melter. Both the minimelter and BNFL melter systems consist of five primary subsystems: melter vessel, off-gas treatment, feed, power supply, and instrumentation and controls. The configuration and design of these subsystems are tailored to match the current system requirements and provide the flexibility to support future DOE vitrification programs. This paper presents a detailed discussion of the unique design challenges represented by these two new melter systems

  9. The management of solid radioactive waste at Sellafield and Drigg: individual reports in order of building number. V. 2

    International Nuclear Information System (INIS)

    1996-01-01

    An audit was carried out of the solid low level and intermediate level radioactive waste at the Sellafield and Drigg sites of British Nuclear Fuels plc (BNFL) to establish the state of waste management. The audit was undertaken by a joint team of inspectors from the HSE's Nuclear Installations Inspectorate and HM Inspectorate of Pollution in line with their respective responsibilities for regulation of the storage and disposal of radioactive waste. The report records each solid waste facility and the conditions of storage observed by the team. The report reflects the views of the audit team. It should not be read as the definitive HMIP or NII judgement of the site's performance on waste matters. This continues to be based upon day to day interaction between allocated site inspectors and site managers. However, the recommendations of the team have been endorsed by HMIP and NII and accepted by BNFL. The report is published in two volumes. Volume 1 describes the aims and extent of the audit, the method of working and the findings and recommendations made. The reports on individual buildings are presented in Volume 2. These describe the waste management arrangements observed by members of the audit team. Where shortcomings are identified these have been brought to the attention of BNFL, and to the nominated site inspectors of HMIP and NII, in order that appropriate action may be considered to rectify the position. Where observations have lead to specific recommendations, these are indicated in Volume 2 at the point of arising. The recommendations are presented in full in Volume 1. Volume 1 also includes the overall conclusions of the audit and the recommendations which have been made as a result of the observations described in Volume 2. (UK)

  10. Some engineering considerations when designing centrifuge enrichment plants

    International Nuclear Information System (INIS)

    Edwards, T.T.

    1982-01-01

    A review is given of the three main areas where flexibility is needed in the design of centrifuge enrichment plants. These are: the need to cope with market requirements, the limitations imposed by currently available centrifuges and ever advancing centrifuge technology. Details of BNFL's experience with centrifuge enrichment at Capenhurst are presented. (U.K.)

  11. Transuranium removal from Hanford high level waste simulants using sodium permanganate and calcium

    International Nuclear Information System (INIS)

    Wilmarth, W.R.; Rosencrance, S.W.; Nash, C.A.; Fonduer, F.F.; Di Pirete, D.P.; Di Prete, C.C.

    2000-01-01

    Plutonium and americium are present in the Hanford high level liquid waste complexant concentrate (CC) due to the presence of complexing agents including di-(2-ethylhexyl) phosphoric acid (D 2 EHPA), tributylphosphate (TBP), hydroxyethylene diamine triacetic acid (HEDTA), ethylene diamine tetraacetic acid (EDTA), citric acid, glycolic acid, and sodium gluconate. The transuranic concentrations approach 600 nCi/g and require processing prior to encapsulation into low activity glass. BNFL's (British Nuclear Fuels Limited's) original process was a ferric co-precipitation method based on earlier investigations by Herting and Orth, et al. Furthermore, flocculation and precipitation are widely used for clarification in municipal water treatment. Co-precipitation of Np, Am, and Pu with ferric hydroxide is also used within an analytical method for the sum of those analytes. Tests to evaluate BNFL's original precipitation process indicated the measured decontamination factors (DFs) and filter fluxes were too low. Therefore, an evaluation of alternative precipitation agents to replace ferric ion was undertaken. Agents tested included various transition metals, lanthanide elements, uranium species, calcium, strontium, and permanganate

  12. Experience with respect to dose limitation in nuclear fuel service operations in the United Kingdom supporting civil nuclear power programmes

    International Nuclear Information System (INIS)

    Kennedy, J.W.

    1983-01-01

    Within the United Kingdom, the nuclear power generation programme is supported by nuclear fuel services including uranium enrichment, fuel fabrication and reprocessing, operated by British Nuclear Fuels Limited (BNFL). These have entailed the processing of large quantities of uranium and of plutonium and fission products arising in the course of irradiation of fuel in nuclear power stations and have necessitated substantial programmes for the radiological protection of the public and of the workers employed in the industry. This paper presents and reviews the statistics of doses recorded in the various sectors of nuclear fuel services operations against the background of the standards to which the industry is required to operate. A description is given of the development of BNFL policy in keeping with the objective of being recognized as among those industries regarded as safe and the resource implications of measures to reduce doses received by workers are reviewed in the light of experience. Finally, the paper reviews the epidemiological data which have been, and continue to be, collected for workers who have been employed in these nuclear fuel services. (author)

  13. Environmental radioactivity

    International Nuclear Information System (INIS)

    1985-01-01

    Outline summary of a report prepared under contract to the DOE: Research Priorities and UK Estuaries: An Overview identifying Research Requirements. Topics considered include the study of radionuclides released into the NE Irish Sea from BNFL, Sellafields, differences in the isotopic composition of stable lead in various sediments, the concentration and distribution of 'hot particles' derived from BNFL in the Irish Sea and adjacent areas, together with attempts to separate hot particles from sediments, and the composition and properties of marine surfaces in relation to uptake and loss of radionuclides, particularly in relation to the common mussel, Mytilus edulis. The problem of the presence of transuranic radionuclides in the bottom sediments of the NE Irish Sea is considered. Profiles of radioactivity are being developed at the shelf-break in order to determine the transfer of radionuclides from the sea surface to the deep sea and to coastal waters; organisms examined include phytoplankton, zooplankton and crustacea (shrimps). Organisms such as Acantharia have been examined to determine transfer of elements and radionuclides to skeletal structures eg Sr, Ba and Si. (U.K.)

  14. GRAYSKY-A new gamma-ray skyshine code

    International Nuclear Information System (INIS)

    Witts, D.J.; Twardowski, T.; Watmough, M.H.

    1993-01-01

    This paper describes a new prototype gamma-ray skyshine code GRAYSKY (Gamma-RAY SKYshine) that has been developed at BNFL, as part of an industrially based master of science course, to overcome the problems encountered with SKYSHINEII and RANKERN. GRAYSKY is a point kernel code based on the use of a skyshine response function. The scattering within source or shield materials is accounted for by the use of buildup factors. This is an approximate method of solution but one that has been shown to produce results that are acceptable for dose rate predictions on operating plants. The novel features of GRAYSKY are as follows: 1. The code is fully integrated with a semianalytical point kernel shielding code, currently under development at BNFL, which offers powerful solid-body modeling capabilities. 2. The geometry modeling also allows the skyshine response function to be used in a manner that accounts for the shielding of air-scattered radiation. 3. Skyshine buildup factors calculated using the skyshine response function have been used as well as dose buildup factors

  15. Preparation of the initial safety case

    International Nuclear Information System (INIS)

    Hensley, G.

    1987-01-01

    In British Nuclear Fuels plc (BNFL), the design of nuclear chemical plants for construction and subsequent operation at Sellafield Works is carried out by the Engineering Division of the Spent Fuel Management Services Group based at Risley, Warrington. Plant construction cannot take place, nor plant commissioning, until it has been demonstrated in the initial (design) safety case that the chosen design will allow the plant to be operated in an adequately safe manner, corresponding to an extremely low level of risk. The safety documentation procedure is described. A Preliminary Design Safety Appraisal is made of the initial design proposal to give an early indication of the order of risk that might prevail. The risk from each hazard is compared with an allocated risk target which makes up a proportion of the total plant risk which is quantified in BNFL's risk criteria. Where the risk appears unacceptable, appropriate modifications are made to the design. Prior to commissioning, a comprehensive, detailed risk assessment is carried out. The methodology of probabilistic risk assessment is described and examples given of how different hazards are assessed. (author)

  16. Decommissioning of the gaseous diffusion plant at BNFL Capenhurst

    International Nuclear Information System (INIS)

    Baxter, S.G.; Bradbury, P.

    1992-01-01

    The history of the on-going dismantling and disposal program for the Capenhurst Diffusion Plant is described. Reference is made to the scale of the project and to the special techniques developed, particularly in the areas of size reduction, decontamination and protection of personnel and the environment. When the project is successfully concluded by the end of 1993 over 99% of the materials of construction of the plant will have been recycled to the environment as clean material. (author)

  17. BNFL and education open-quotes Living with Technologyclose quotes

    International Nuclear Information System (INIS)

    Bolter, H.E.

    1991-01-01

    Following upon a report to a House of Commons Select Committee, the Chairman and Chief Executive gave an undertaking to better inform young people about the Nuclear Industry. This lead to British Nuclear Fuels plc formulating a Corporate education policy and the adoption of a concept open-quotes Living with Technologyclose quotes which slots into the new National Curriculum for schools in England and Wales. One year into implementation, the initiative is proving a great success and at the present time the launch of open-quotes Living with Technologyclose quotes to the education world and public is underway

  18. Environment annual report 1993

    International Nuclear Information System (INIS)

    1994-01-01

    In the 1993 Environment Annual Report for BNFL, data are presented for radioactive discharges to the environment and their associated doses to the criteria group members of the public in the vicinity of Sellafield, Drigg, Chapelcross, Springfields and Capenhurst. Similarly, data are also presented for non-radioactive discharges to water and air for each site. (UK)

  19. Country report for the UK

    International Nuclear Information System (INIS)

    Abram, T.

    2000-01-01

    In the frame of the status of the UK nuclear industry, activities concerning fast reactor are reviewed. There is no government funded program except for decommissioning work at Dounrey. Major activities are concerned with knowledge preservation, fuel cycle modelling and scenario studies, and gas-cooled fast reactor feasibility studies. European, international and BNFL collaboration are also reviewed

  20. Product evaluation phase 1 report

    International Nuclear Information System (INIS)

    Kearsey, H.A.; Hornby, J.

    1984-01-01

    This report concerns the intermediate-level radioactive waste arisings from the reprocessing of irradiated nuclear fuel at BNFL Sellafield. Headings are: general introduction (origin of waste; current stocks and future arisings); characteristics of the waste stream; alternative matrices (for solidification of waste in form suitable for disposal); waste simulation; relevance of other Phase II studies. (U.K.)

  1. Progress report for 1986 from the Plutonium Contaminated Materials Working Party

    International Nuclear Information System (INIS)

    Higson, S.G.

    1987-11-01

    The paper covers progress during 1986 under the joint BNFL/MOD/DoE funded PCM Working Party studying the management, treatment and immobilization of plutonium contaminated materials. Development is reported under each of seven main programme headings including reduction of arisings, Pu measurement, decommissioning and non-combustible PCM treatment, liquid effluent treatment, sorting and packaging, PCM immobilisation and engineering objectives. (author)

  2. Fourth annual report

    International Nuclear Information System (INIS)

    1983-06-01

    The report of the (United Kingdom) Radioactive Waste Management Advisory Committee for 1982-1983 falls under the headings: introduction and summary; review of the year; current sea disposal - the scientific evidence; liquid discharges from BNFL Sellafield; intermediate-level wastes; high-level wastes - the state of research on the options; transport of radioactive wastes and spent fuel; future work. (U.K.)

  3. Waste Feed Delivery Strategy for Tanks 241-AN-102 and 241-AN-107

    International Nuclear Information System (INIS)

    BLACKER, S.M.

    2000-01-01

    This engineering study establishes the detailed retrieval strategy, equipment requirements, and key parameters for preparing detailed process flowsheets; evaluates the technical and programmatic risks associated with processing, certifying, transferring, and delivering waste from Tanks 241-AN-102 and 241-AN-107 to BNFL; and provides a list of necessary follow-on actions so that program direction from ORP can be successfully implemented

  4. Annual report on occupational safety 1985

    International Nuclear Information System (INIS)

    1986-09-01

    This report presents information on occupational safety relating to the Company's employees for the year 1985, and compares data with figures for the previous year. The following headings are listed: principle activities of BNFL, general policy and organisation, radiological safety, including whole body, skin and extremity, and internal organ doses, non-radiological safety, incidents reportable to the health and safety executive. (U.K.)

  5. Product evaluation phase 1 report

    International Nuclear Information System (INIS)

    Ward, M.

    1984-01-01

    This report concerns the intermediate-level radioactive waste arisings from the reprocessing of irradiated nuclear fuel at BNFL Sellafield. Tokai Mura end caps arise when the fuel from the Japanese Tokai Mura reactor is decanned prior to fuel processing. Headings are: introduction (origin and arisings); waste characterisation; alternative matrices for encapsulation of waste in form suitable for disposal. (U.K.)

  6. Health and safety annual report 1989

    International Nuclear Information System (INIS)

    1989-01-01

    This 1989 annual report on Health and Safety in BNFL is intended to give the public a general review of the impact of the Company's activities on its workforce, the public and the environment. The activities at Sellafield, Springfields, Chapelcross, Drigg and Capenhurst are outlined, together with sections on medical services and transport, and radiation monitoring of workforce and the environment. (author)

  7. Waste Feed Delivery Strategy for Tanks 241-AN-102 and 241-AN-107

    Energy Technology Data Exchange (ETDEWEB)

    BLACKER, S.M.

    2000-04-13

    This engineering study establishes the detailed retrieval strategy, equipment requirements, and key parameters for preparing detailed process flowsheets; evaluates the technical and programmatic risks associated with processing, certifying, transferring, and delivering waste from Tanks 241-AN-102 and 241-AN-107 to BNFL; and provides a list of necessary follow-on actions so that program direction from ORP can be successfully implemented.

  8. Experience of the remote dismantling of the Windscale advanced gas-cooled reactor and Windscale pile chimneys

    International Nuclear Information System (INIS)

    Wright, E.M.

    1993-01-01

    This paper gives brief descriptions of some of the remote dismantling work and equipment used on two large decommissioning projects: the BNFL Windscale Pile Chimneys Project (remote handling machine, waste packaging machine, remotely controlled excavator, remotely controlled demolition machine) and the AEA Windscale Advanced Gas-cooled Reactor Project (remote dismantling machine, operational waste, bulk removal techniques, semi-remote cutting operations)

  9. Analysis of transport logistics and routing requirements for radioactive waste management systems with respect to a minimum power scenario

    International Nuclear Information System (INIS)

    James, I.A.

    1984-10-01

    This report assesses the transport logistics associated with disposal of intermediate-level radioactive waste, as generated by CEGB, SSEB, UKAEA and BNFL, in accordance with a 'Minimum Power Scenario'. Transport by road and rail is analysed, as in previous reports; use of coastal shipping however has not been included but has been replaced with a combined road/rail option. (author)

  10. A preliminary redrafting of the Italian technical guide no.26 on radioactive waste management

    International Nuclear Information System (INIS)

    Tocci, M.

    1993-01-01

    The recent National Energy Plan confirms the need for reprocessing of the nuclear spent fuel arising from the Nuclear Power Plants (NPPs) that were definitively put out of operation after Chernobyl accident. Two campaigns concerning the Italian spent fuel reprocessing are starting at this time. The first-one is related to LATINA (MAGNOX, GCR 160 MWe) while the second one will concern GARIGLIANO (BWR 160 MWe), CAORSO (BWR 840 MWe) and TRINO (PWR, 200 MWe). The first campaign will involve about 600 tons of MAGNOX spent fuel arising from LATINA NPP which will be reprocessed in the next future by BNFL (British Nuclear Fuel Limited) at Sellafield. The vitrified High Level Wastes (HLW) shall return to Italy starting from 1994. ENEA-DISP (Italian directorate for Nuclear Safety) has received from BNFL the technical specifications of the glass blocks. The approval of those specifications is scheduled by the end of 1993, in order to allow the delivery of the wastes. During the licensing iter ENEA-DISP will use its own Technical Guide N. 26, which identifies and specifies the basic criteria and requirements for an appropriate waste management policy. (author). 4 figs., 5 refs

  11. Enhanced safety margins during wet transport of irradiated fuel by catalytic recombination of radiolysis hydrogen and oxygen

    International Nuclear Information System (INIS)

    Spencer, J.T.; Bankhead, M.; Hodge, N.A.

    2004-01-01

    BNFL has developed and tested a new method for use in wet transport of irradiated fuel. The method uses a catalyst to recombine the hydrogen and oxygen produced from radiolysis. The catalyst is installed in the nitrogen ullage gas region. It has twin benefits as it eliminates a gas mixture that could, in principle, exceed the safe target levels set to ensure safety during Transport, and it also reduces overall gas pressure. Pure water radiolysis predictions, from experiment and theory, indicate very low levels of hydrogen and oxygen generation. BNFL's historic experience is that in some transport packages it is possible to produce higher levels of hydrogen and oxygen. This drives the need to improve on our existing ullage gas remediation technology. Our studies of the radiolysis science and our flask data suggest it is the interaction of the liquors and material surfaces that is giving rise to the enhanced levels of hydrogen and/or oxygen. This technical paper demonstrates the performance of the recombiner catalyst under normal and extreme conditions of transport. The paper will present experimental data that shows the recombiner catalyst working to manage the hydrogen and oxygen levels

  12. Big rock point restoration project BWR major component removal, packaging and shipping - planning and experience

    International Nuclear Information System (INIS)

    Milner, T.; Dam, S.; Papp, M.; Slade, J.; Slimp, B.; Nurden, P.

    2001-01-01

    The Big Rock Point boiling water reactor (BWR) at Charlevoix, MI was permanently shut down on August 29th 1997. In 1999 BNFL Inc.'s Reactor Decommissioning Group (RDG) was awarded a contract by Consumers Energy (CECo) for the Big Rock Point (BRP) Major Component Removal (MCR) project. BNFL Inc. RDG has teamed with MOTA, Sargent and Lundy and MDM Services to plan and execute MCR in support of the facility restoration project. The facility restoration project will be completed by 2005. Key to the success of the project has been the integration of best available demonstrated technology into a robust and responsive project management approach, which places emphasis on safety and quality assurance in achieving project milestones linked to time and cost. To support decommissioning of the BRP MCR activities, a reactor vessel (RV) shipping container is required. Discussed in this paper is the design and fabrication of a 10 CFR Part 71 Type B container necessary to ship the BRP RV. The container to be used for transportation of the RV to the burial site was designed as an Exclusive Use Type B package for shipment and burial at the Barnwell, South Carolina (SC) disposal facility. (author)

  13. Control and tracking arrangements for solid low-level waste disposals to the UK Drigg disposal site

    International Nuclear Information System (INIS)

    Elgie, K.G.; Grimwood, P.D.

    1993-01-01

    The Drigg disposal site has been the principal disposal site for solid low-level radioactive wastes (LLW) in the United Kingdom since 1959. It is situated on the Cumbrian coast, some six kilometers to the south of the Sellafield nuclear reprocessing site. The Drigg site receives LLW from a wide range of sources including nuclear power generation, nuclear fuel cycle activities, defense activities, isotope manufacture, universities, hospitals, general industry and clean-up of contaminated sites. This LLW has been disposed of in a series of trenches cut into the underlying clay layer of the site, and, since 1988, also into concrete lined vault. The total volume of LLW disposed of at Drigg is at present in the order of 800,000m 3 , with disposals currently approximately 25,000m 3 per year. British Nuclear Fuels plc (BNFL) owns and operates the Drigg disposal site. To meet operational and regulatory requirements, BNFL needs to ensure the acceptability of the disposed waste and be able to track it from its arising point to its specific disposal location. This paper describes the system that has been developed to meet these requirements

  14. Flask fluid flow simulation using CFD

    International Nuclear Information System (INIS)

    Swindlehurst, W.E.; Livesey, E.; Worthington, D.

    1989-01-01

    BNFL and its subsidiary Company, PNTL, design and operate waterfilled LWR fuel transport flasks for the international transport of irradiated fuel. Although some 150 flasks are currently in operation, new flask designs are being developed. As part of the supporting R and D program, Computational Fluid Dynamics (CFD) codes are being investigated as a means of predicting fluid movements and temperatures within the complex internal geometry of flasks. The ability to simulate fluid flow is particularly important when convection heat transfer is significant. Although obviously relevant to water filled flasks, the technique is applicable to dry flask thermal assessments (where experience shows that convection heat transfer is often underestimated). Computational Fluid Dynamics has emerged in recent years as an important technique in engineering design and safety assessments. Cheaper computing and the development of general CFD codes allows complex engineering structures to be analyzed. However, because of this complexity, it is essential that the application and associated modeling assumptions are critically reviewed. To assess the ability of a CFD code to model flask internals, the code PHOENICS has been used to model the fluid movements in a BNFL Excellox-type flask and the results compared with test data

  15. Provision of NDA instrumentation for the control of operations on plutonium finishing and waste plants at the Sellafield nuclear fuel reprocessing facility

    International Nuclear Information System (INIS)

    Whitehouse, K.R.; Orr, C.H.

    1995-01-01

    On BNFL's Sellafield site a significant number of major plants are involved in the handling, processing and storage of plutonium in various forms including nitrate, oxide and mixed oxide (MOX). Other plants in operation or under construction treat and prepare for storage, plutonium bearing wastes in the form of plutonium contaminated materials -- PCM (transuranic waste -- TRU) or low level waste. Concurrently, a number of old plutonium handling plants are being decommissioned. The safety and cost effectiveness of these widely varying operations has been ensured by the development and installation of a wide range of special radiometric instrumentation. These systems based on a range of neutron counting and high resolution gamma spectrometric techniques -- singly or in combination -- enable BNFL to maintain a detailed and comprehensive picture of the disposition of plutonium within each plant and across the site. This paper describes an overview of the range of plant and paper prove waste measurement systems in this context, highlighting the specific roles of the Plutonium Inventory Measurement System (PIMS) for real time accountancy and the Decommissioning In-Situ Plutonium Inventory Monitor (DISPIM) for material control during decommissioning

  16. Nuclear Industry Family Study

    International Nuclear Information System (INIS)

    1993-01-01

    This is a copy of the U.K.A.E.A. Question and Answer brief concerning an epidemiological study entitled the Nuclear Industry Family Study, to investigate the health of children of AEA, AWE, and BNFL Workers. The study is being carried out by an independent team of medical research workers from the London School of Hygiene and Tropical Medicine, and the Imperial Cancer Research Fund. (UK)

  17. Analysis of irradiated Magnox fuel for fission product and actinide elements

    International Nuclear Information System (INIS)

    Foster, E.; Fudge, A.J.; Glover, K.M.; Wiltshire, R.A.P.

    1980-03-01

    This report describes the methods used for, and the results obtained from, chemical and isotopic analysis of four Magnox fuel samples of known irradiation history. The analysis of this material was carried out in conjunction with CEGB, Berkeley Nuclear Laboratories and BNFL. The data obtained was used to evaluate the accuracy of fuel composition as predicted by computer codes such as RICE (Reactor Inventory Code). (author)

  18. Product evaluation phase 1 report

    International Nuclear Information System (INIS)

    Kearsey, H.A.; Page, R.J.

    1984-01-01

    This report concerns the intermediate-level radioactive waste arisings from the reprocessing of irradiated nuclear fuel at BNFL Sellafield. The graphite waste arises from the reprocessing of CAGR fuel assemblies. Headings are: introduction (origin of waste; future arisings); waste characterisation; initial evaluation of encapsulation options - evaluation of potential matrices for encapsulation of waste in form suitable for disposal; waste simulation; relevance to other phase II studies. (UK)

  19. Sellafield (release of radioactivity)

    Energy Technology Data Exchange (ETDEWEB)

    Cunningham, J; Goodlad, A; Morris, M

    1986-02-06

    A government statement is reported, about the release of plutonium nitrate at the Sellafield site of British Nuclear Fuels plc on 5 February 1986. Matters raised included: details of accident; personnel monitoring; whether radioactive material was released from the site; need for public acceptance of BNFL activities; whether plant should be closed; need to reduce level of radioactive effluent; number of incidents at the plant.

  20. Health and Safety annual report 1993

    International Nuclear Information System (INIS)

    1994-01-01

    In the 1993 Health and Safety Report for BNFL, data showing improvements in radiological and conventional safety are given. Other aspects discussed are emergency planning, the level of incidents, occupational health services, litigation and the compensation scheme, the transport of radioactive materials, research covering transgenerational epidemiology, mortality and cancer studies, genetics and radiobiology, and dosimetry, and finally a summary of radioactive discharges and environmental data. (UK)

  1. Product evaluation phase 1 report

    International Nuclear Information System (INIS)

    Fairhall, G.A.

    1984-01-01

    This report concerns the intermediate-level radioactive waste arisings from the reprocessing of magnox-clad fuel at BNFL Sellafield. The magnox swarf, with its associated debris, retrieved from previous operations has corroded to a sludge. Headings are: introduction (origin, current stocks and future arisings); waste characterisation; initial evaluation of potential matrices for solidification of waste in form suitable for disposal; waste simulation. (U.K.)

  2. Bring in the experts

    International Nuclear Information System (INIS)

    McFarland, Susan

    1999-01-01

    This article focuses on the outsourcing of water treatment by the British Nuclear Fuels Ltd.'s (BNFL) Bradwell-on-Sea nuclear power plant to Ecolochem to avoid the large initial investment cost and reduce maintenance costs. Details are given of the design of a cascade system to produce demineralized water for nuclear cooling by Ecolochem who own, operate and maintain the water treatment plant. (UK)

  3. The Design and Construction of the Advanced Mixed Waste Treatment Facility

    Energy Technology Data Exchange (ETDEWEB)

    Harrop, G.

    2003-02-27

    The Advanced Mixed Treatment Project (AMWTP) privatized contract was awarded to BNFL Inc. in December 1996 and construction of the main facility commenced in August 2000. The purpose of the advanced mixed waste treatment facility is to safely treat plutonium contaminated waste, currently stored in drums and boxes, for final disposal at the Waste Isolation Pilot Plant (WIPP). The plant is being built at the Idaho National Engineering and Environmental Laboratory. Construction was completed in 28 months, to satisfy the Settlement Agreement milestone of December 2002. Commissioning of the related retrieval and characterization facilities is currently underway. The first shipment of pre-characterized waste is scheduled for March 2003, with AMWTP characterized and certified waste shipments from June 2003. To accommodate these challenging delivery targets BNFL adopted a systematic and focused construction program that included the use of a temporary structure to allow winter working, proven design and engineering principles and international procurement policies to help achieve quality and schedule. The technology involved in achieving the AMWTP functional requirements is primarily based upon a BNFL established pedigree of plant and equipment; applied in a manner that suits the process and waste. This technology includes the use of remotely controlled floor mounted and overhead power manipulators, a high power shredder and a 2000-ton force supercompactor with the attendant glove box suite, interconnections and automated material handling. The characterization equipment includes real-time radiography (RTR) units, drum and box assay measurement systems, drum head space gas sampling / analysis and drum venting, drum coring and sampling capabilities. The project adopted a particularly stringent and intensive pre-installation testing philosophy to ensure that equipment would work safely and reliably at the required throughput. This testing included the complete off site

  4. Criticality experiments with low enriched UO2 fuel rods in water containing dissolved gadolinium

    International Nuclear Information System (INIS)

    Bierman, S.R.; Murphy, E.S.; Clayton, E.D.; Keay, R.T.

    1984-02-01

    The results obtained in a criticality experiments program performed for British Nuclear Fuels, Ltd. (BNFL) under contract with the United States Department of Energy (USDOE) are presented in this report along with a complete description of the experiments. The experiments involved low enriched UO 2 and PuO 2 -UO 2 fuel rods in water containing dissolved gadolinium, and are in direct support of BNFL plans to use soluble compounds of the neutron poison gadolinium as a primary criticality safeguard in the reprocessing of low enriched nuclear fuels. The experiments were designed primarily to provide data for validating a calculation method being developed for BNFL design and safety assessments, and to obtain data for the use of gadolinium as a neutron poison in nuclear chemical plant operations - particularly fuel dissolution. The experiments program covers a wide range of neutron moderation (near optimum to very under-moderated) and a wide range of gadolinium concentration (zero to about 2.5 g Gd/l). The measurements provide critical and subcritical k/sub eff/ data (1 greater than or equal to k/sub eff/ greater than or equal to 0.87) on fuel-water assemblies of UO 2 rods at two enrichments (2.35 wt % and 4.31 wt % 235 U) and on mixed fuel-water assemblies of UO 2 and PuO 2 -UO 2 rods containing 4.31 wt % 235 U and 2 wt % PuO 2 in natural UO 2 respectively. Critical size of the lattices was determined with water containing no gadolinium and with water containing dissolved gadolinium nitrate. Pulsed neutron source measurements were performed to determine subcritical k/sub eff/ values as additional amounts of gadolinium were successively dissolved in the water of each critical assembly. Fission rate measurements in 235 U using solid state track recorders were made in each of the three unpoisoned critical assemblies, and in the near-optimum moderated and the close-packed poisoned assemblies of this fuel

  5. The Design and Construction of the Advanced Mixed Waste Treatment Facility

    International Nuclear Information System (INIS)

    Harrop, G.

    2003-01-01

    The Advanced Mixed Treatment Project (AMWTP) privatized contract was awarded to BNFL Inc. in December 1996 and construction of the main facility commenced in August 2000. The purpose of the advanced mixed waste treatment facility is to safely treat plutonium contaminated waste, currently stored in drums and boxes, for final disposal at the Waste Isolation Pilot Plant (WIPP). The plant is being built at the Idaho National Engineering and Environmental Laboratory. Construction was completed in 28 months, to satisfy the Settlement Agreement milestone of December 2002. Commissioning of the related retrieval and characterization facilities is currently underway. The first shipment of pre-characterized waste is scheduled for March 2003, with AMWTP characterized and certified waste shipments from June 2003. To accommodate these challenging delivery targets BNFL adopted a systematic and focused construction program that included the use of a temporary structure to allow winter working, proven design and engineering principles and international procurement policies to help achieve quality and schedule. The technology involved in achieving the AMWTP functional requirements is primarily based upon a BNFL established pedigree of plant and equipment; applied in a manner that suits the process and waste. This technology includes the use of remotely controlled floor mounted and overhead power manipulators, a high power shredder and a 2000-ton force supercompactor with the attendant glove box suite, interconnections and automated material handling. The characterization equipment includes real-time radiography (RTR) units, drum and box assay measurement systems, drum head space gas sampling / analysis and drum venting, drum coring and sampling capabilities. The project adopted a particularly stringent and intensive pre-installation testing philosophy to ensure that equipment would work safely and reliably at the required throughput. This testing included the complete off site

  6. EDRP public local inquiry, UKAEA/BNFL precognition on: Contractor accommodation

    International Nuclear Information System (INIS)

    Scott, W.

    1986-01-01

    The availability of accommodation for contractors working on the proposed EDRP at Dounreay is discussed. It is predicted that the contractors could be accommodated without the need for special arrangement and with no adverse effect on the tourist industry. (U.K.)

  7. BNFL assessment of methods of attaining high burnup MOX fuel

    International Nuclear Information System (INIS)

    Brown, C.; Hesketh, K.W.; Palmer, I.D.

    1998-01-01

    It is clear that in order to maintain competitiveness with UO 2 fuel, the burnups achievable in MOX fuel must be enhanced beyond the levels attainable today. There are two aspects which require attention when studying methods of increased burnups - cladding integrity and fuel performance. Current irradiation experience indicates that one of the main performance issues for MOX fuel is fission gas retention. MOX, with its lower thermal conductivity, runs at higher temperatures than UO 2 fuel; this can result in enhanced fission gas release. This paper explores methods of effectively reducing gas release and thereby improving MOX burnup potential. (author)

  8. Novel finishing concepts within BNFL'S advanced reprocessing programme

    Energy Technology Data Exchange (ETDEWEB)

    Hobbs, J.W.; Booth, R.; Lawson, S.; Parkes, P. [BNFL British Nuclear Fuels, Sellafield, Seascale, Cumbria, Research and Technology (United Kingdom)

    2000-07-01

    New methods of converting actinide nitrate solutions to oxide and fabricating the products from the reprocessing of high burn up and MOX fuels are necessary for the next generation of fuel cycle facilities in order to meet dose criteria and cost reduction targets. Options to support this include never fully separating the plutonium from the uranium and reducing decontamination factors. The product stream from such a reprocessing plant will require a finishing route capable of significant levels of automation and dose minimization. Casting of molten uranyl nitrate into pellets followed by de-nitration under vacuum has been investigated as a novel way of manufacturing oxide fuel pellets. Pellets were successfully cast over a range of temperatures and de-nitrated. Incorporation of uranium oxide into the melt was investigated to increase the density of the cast pellet. It has been demonstrated that it is possible to produce extrudates from powder and molten magnesium nitrate mixtures. Results of a preliminary study of the flow behaviour during extrusion of magnesium nitrate simulant loaded with alumina powder are also discussed. (authors)

  9. EDRP public local inquiry, UKAEA/BNFL precognition on: Water supply

    International Nuclear Information System (INIS)

    Ward, D.L.

    1986-01-01

    The eventual water requirement for the proposed EDRP at Dounreay is estimated to be about 400m 3 /day. It is concluded that the additional requirement to the existing needs of the Dounreay Nuclear Establishment will have no significant effect on the total extraction rate from Loch Shurrery or on the operation of the present water treatment plant at Shebster. (UK)

  10. Release Storage and Disposal Program Product Sampling Support

    International Nuclear Information System (INIS)

    CALMUS, R.B.

    2000-01-01

    This document includes recommended capabilities and/or services to support transport, analysis, and disposition of Immobilized High-Level and Low-Activity Waste samples as requested by the US DOE-Office of River Protection (DOE-ORP) as specified in the Privatization Contract between DOE-ORP and BNFL Inc. In addition, an approved implementation path forward is presented which includes use of existing Hanford Site services to provide the required support capabilities

  11. A comparison of the observed and the expected cancers of the haematopoietic and lymphatic systems among workers at Windscale

    International Nuclear Information System (INIS)

    Dolphin, G.W.

    1976-12-01

    Data are given about the cases of cancers of the haematopoietic and lymphatic systems among workers at Windscale Works, BNFL during the period 1950 to 1974. The number of cancers of these types expected to occur in the working population at Windscale has been estimated for the same period. For none of these types is the observed number of cancers significantly different at the 95% confidence level from that expected. (author)

  12. Managing nuclear liabilities: 'hospital pass' or major opportunity?

    International Nuclear Information System (INIS)

    May, D.

    1995-01-01

    This paper sets out to start changing the perception that liabilities management is an unattractive part of the UK Nuclear Industry. The paper describes BNFL's successes and long term challenges in this area and concludes that liabilities management presents a major opportunity to:-Remove an Achilles heel of the industry; Create value for the companies concerned by successfully driving down costs; Sustain and exploit internationally a major UK competitive edge. (Author)

  13. Annual report and accounts 1989/90

    International Nuclear Information System (INIS)

    1990-01-01

    The Annual Report and Accounts starts with the years' highlights followed by the Chairman's Review and Chief Executive and Company Reviews. After a general introduction to BNFL's: operations several aspects are looked at in rather more detail; fuel and engineering, reprocessing, technical and planning and corporate affairs including public relations and personnel. The Directors' and Auditors' reports come next, then the accounts with relevant balance sheets and financial statistics. (UK)

  14. UK national consensus conference on radwaste management

    International Nuclear Information System (INIS)

    Craven-Howe, Andrew

    2000-01-01

    UK CEED organised a consensus conference to debate radwaste disposal. It lasted from 21-24 May 1999. Among the witnesses called to give evidence were UKAEA, BNFL, Nuclear Industries' Inspectorate, Department of the Environment, Transport and the Regions, Friends of the Earth and Greenpeace. The end result was a report produced by the panel of members of the public, recording their views and recommendations. Conclusions are presented. (author)

  15. A harpoon for Greenpeace?: judicial review of the regulation of radioactive substances

    International Nuclear Information System (INIS)

    Purdue, M.

    1994-01-01

    The judgement is reported on an application by Greenpeace Ltd for a judicial review of the decision by HMI of Pollution and the Ministry of Agriculture, Fisheries and Food to grant BNFL permission to test the new thermal oxide reprocessing plant. An analysis follows examining the issues relating to the process of judicial review in the UK and discussion of some of the substantive points raised by the litigation. (UK)

  16. Return of vitrified wastes from France to Japan; Retour des residus vitrifies de France au Japon

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-07-01

    The radioactive wastes resulting from the burnup of nuclear fuels in nuclear reactors represent 3 to 5% of the spent fuel. These wastes cannot be reused nor recycled and thus are vitrified after reprocessing. Japanese power companies have signed contracts with Cogema in France and BNFL in the UK for the reprocessing of their spent fuels. Then, the ultimate reprocessed wastes are sent back to Japan for storage. This information dossier takes stock of different questions relative to the transport of the vitrified wastes from France to Japan: why France sends back containers of vitrified wastes to Japan? What is a vitrified wastes container made of? How containers are transported? What is the regulatory frame applicable to these transports? Which safety measures are taken during transport? Which physical protection is applied? Which temporary storage facilities are used before and after transportation? How is performed the ultimate storage of wastes in Japan? Which quality and safety warranties are taken? Which emergency plans and exercises are provided? What are the applicable civil liability regimes? And what kind of information is given to the public about these transports. Some general information about energy and nuclear power worldwide, energy and environment, radioactivity, BNFL, Cogema and ORC is given in appendixes. (J.S.)

  17. Return of vitrified wastes from France to Japan

    International Nuclear Information System (INIS)

    2000-01-01

    The radioactive wastes resulting from the burnup of nuclear fuels in nuclear reactors represent 3 to 5% of the spent fuel. These wastes cannot be reused nor recycled and thus are vitrified after reprocessing. Japanese power companies have signed contracts with Cogema in France and BNFL in the UK for the reprocessing of their spent fuels. Then, the ultimate reprocessed wastes are sent back to Japan for storage. This information dossier takes stock of different questions relative to the transport of the vitrified wastes from France to Japan: why France sends back containers of vitrified wastes to Japan? What is a vitrified wastes container made of? How containers are transported? What is the regulatory frame applicable to these transports? Which safety measures are taken during transport? Which physical protection is applied? Which temporary storage facilities are used before and after transportation? How is performed the ultimate storage of wastes in Japan? Which quality and safety warranties are taken? Which emergency plans and exercises are provided? What are the applicable civil liability regimes? And what kind of information is given to the public about these transports. Some general information about energy and nuclear power worldwide, energy and environment, radioactivity, BNFL, Cogema and ORC is given in appendixes. (J.S.)

  18. Solid Waste Operations Complex W-113, Detail Design Report (Title II). Volume 3: Specifications

    International Nuclear Information System (INIS)

    1995-09-01

    The Solid Waste Retrieval Facility--Phase 1 (Project W113) will provide the infrastructure and the facility required to retrieve from Trench 04, Burial ground 4C, contact handled (CH) drums and boxes at a rate that supports all retrieved TRU waste batching, treatment, storage, and disposal plans. This includes (1) operations related equipment and facilities, viz., a weather enclosure for the trench, retrieval equipment, weighing, venting, obtaining gas samples, overpacking, NDE, NDA, shipment of waste and (2) operations support related facilities, viz., a general office building, a retrieval staff change facility, and infrastructure upgrades such as supply and routing of water, sewer, electrical power, fire protection, roads, and telecommunication. Title I design for the operations related equipment and facilities was performed by Raytheon/BNFL, and that for the operations support related facilities including infrastructure upgrade was performed by KEH. These two scopes were combined into an integrated W113 Title II scope that was performed by Raytheon/BNFL. Volume 3 is a compilation of the construction specifications that will constitute the Title II materials and performance specifications. This volume contains CSI specifications for non-equipment related construction material type items, performance type items, and facility mechanical equipment items. Data sheets are provided, as necessary, which specify the equipment overall design parameters

  19. Small-Scale Ion Exchange Removal of Cesium and Technetium from Hanford Tank 241-AN-102

    International Nuclear Information System (INIS)

    Hassan, N.M.

    2000-01-01

    The pretreatment process for BNFL, Inc.'s Hanford River Protection Project is to provide decontaminated low activity waste and concentrated eluate streams for vitrification into low and high activity waste glass, respectively. The pretreatment includes sludge washing, filtration, precipitation, and ion exchange processes to remove entrained solids, cesium, transuranics, technetium, and strontium. The cesium (Cs-137) and technetium (Tc-99) ion exchange removal is accomplished by using SuperLig 644, and 639 resins from IBC Advanced Technologies, American Fork, Utah. The resins were shown to selectively remove cesium and technetium (as anionic pertechnetate ) from alkaline salt solutions. The efficiency of ion exchange column loading and elution is a complex function involving feed compositions, equilibrium and kinetic behavior of ion exchange resins, diffusion, and the ionic strength and pH of the aqueous solution. A previous experimental program completed at the Savannah River Tech nology Center2 demonstrated the conceptualized flow sheet parameters with an Envelope C sample from Hanford Tank 241-AN-107. Those experiments also included determination of Cs and Tc batch distribution coefficients by SuperLig 644 and 639 resins and demonstration of small-scale column breakthrough and elution. The experimental findings were used in support of preliminary design bases and pretreatment flow sheet development by BNFL, Inc

  20. Radioactive waste disposal by UKAEA establishments during 1979 and associated environmental monitoring results

    International Nuclear Information System (INIS)

    Flew, E.M.

    1980-07-01

    This report gives details of the amounts of solid and liquid radioactive waste disposed of by the principal establishments of the UKAEA during 1979. Waste arising at the UKAEA Nuclear Power Development Laboratories at Windscale and Springfields, which are both situated on British Nuclear Fuels Ltd. (BNFL) sites, is disposed of by BNFL and included in their authorisations. Discharges to atmosphere of airborne radioactive waste are also included in the report. A summary of the results of the environmental monitoring programmes carried out in connection with the radioactive waste discharges is given. To facilitate an appreciation of the standard of safety achieved, the discharges are, where appropriate, shown as a percentage of those authorised. In the case of atmospheric discharges no quantitative limits are yet specified in the authorisations, but the results and estimates of discharges from stacks are compared with Derived Working Limits (DWL's) (i.e. a limit derived from the dose limits recommended by The International Commission on Radiological Protection in such a way that compliance with it implies virtual certainty of compliance with the relevant dose limits). Environmental monitoring results are also compared with appropriate DWL's. The principles underlying the control of the discharge of radioactive waste to the environment are summarised in an Appendix to the report. (author)

  1. Development and optimisation of generic decommissioning strategies for civil Magnox reactors

    International Nuclear Information System (INIS)

    Carpenter, G.; Hebditch, D.; Meek, N.; Patel, A.; Reeve, P.

    2004-01-01

    BNFL Environmental Services has formulated updated proposals for the use of decision analysis in the development of decommissioning strategy. The proposals are based on the Department of Transport, Local Government and the Regions manual for practitioners on multi-criteria analysis, specifically multi-criteria decision analysis, as suited to complex problems with a mixture of monetary and non-monetary objectives. They take account of up-to-date academic methodology, the newly issued BNFL decision analysis framework for environmental decisions and a wide variety of other engineering, optioneering and optimisation processes. The paper also summarises legislative and company policy areas of importance to decommissioning strategy development. Higher-level generic reactor and site remediation strategies already exist. At the lower level, various generic decommissioning reference processes and project options need development. For the past year, Environmental Services has held responsibility to respond to the Nuclear Installations Inspectorates' quinquennial review, develop and maintain up-to-date strategies, institute the review of a selected number of key strategies, and respond to changing circumstances including stakeholder views. Environmental Services is performing a range of generic studies for selection of strategies and end-points as used for a variety of waste management and site care and maintenance preparations. (author)

  2. Solid Waste Operations Complex W-113, Detail Design Report (Title II). Volume 3: Specifications

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-09-01

    The Solid Waste Retrieval Facility--Phase 1 (Project W113) will provide the infrastructure and the facility required to retrieve from Trench 04, Burial ground 4C, contact handled (CH) drums and boxes at a rate that supports all retrieved TRU waste batching, treatment, storage, and disposal plans. This includes (1) operations related equipment and facilities, viz., a weather enclosure for the trench, retrieval equipment, weighing, venting, obtaining gas samples, overpacking, NDE, NDA, shipment of waste and (2) operations support related facilities, viz., a general office building, a retrieval staff change facility, and infrastructure upgrades such as supply and routing of water, sewer, electrical power, fire protection, roads, and telecommunication. Title I design for the operations related equipment and facilities was performed by Raytheon/BNFL, and that for the operations support related facilities including infrastructure upgrade was performed by KEH. These two scopes were combined into an integrated W113 Title II scope that was performed by Raytheon/BNFL. Volume 3 is a compilation of the construction specifications that will constitute the Title II materials and performance specifications. This volume contains CSI specifications for non-equipment related construction material type items, performance type items, and facility mechanical equipment items. Data sheets are provided, as necessary, which specify the equipment overall design parameters.

  3. Chief Constable's annual report 1986

    International Nuclear Information System (INIS)

    1987-01-01

    The nature of the UKAEA constabulary, its personnel, administration and training, are all covered in this report. The crimes recorded at the UKAEA and BNFL sites are analysed. Traffic problems, transport and communications are covered. Miscellaneous police functions (eg lost property), the constabulary social activities and visitors to nuclear establishments are mentioned. The report ends with a policy statement on the aims and objectives of the constabulary. The report covers 1986. (U.K.)

  4. Separate individual control systems come together at EP2

    International Nuclear Information System (INIS)

    Podmore, A.

    1991-01-01

    At BNFL's EP2 radioactive waste encapsulation plant in the UK, eight area supervisory control and data acquisition systems (SCADAs) and one central SCADA are being installed to provide computer-controlled processing of waste drums. The individual systems are all autonomous, minimizing the effect they have on other areas of the process. At the same time, they are part of an integrated system which provides effective communication between the various areas. (author)

  5. Modelling of the thermal behaviour of 48 inch cylinders

    Energy Technology Data Exchange (ETDEWEB)

    Clayton, D.G.; Hayes, T.J.; Livesey, E.; Lomas, J.; Price, M. [British Nuclear Fuels plc, Risley Warrington Cheshire (United Kingdom)

    1991-12-31

    This paper describes the current state of the analytical models being developed by British Nuclear Fuels plc (BNFL) to improve the understanding of the response of Uranium Hexafluoride containers engulfed in a fire. Details are given of the modeling methods used and physical processes simulated, together with some predictions from the models. Explanations for the differences between the predictions are presented as well as an outline for future development of the models.

  6. Annual report on radioactive discharges and monitoring of the environment, 1996. V. 1

    International Nuclear Information System (INIS)

    1997-01-01

    British Nuclear Fuels Limited (BNFL)'s 1996 report on radioactive discharges from its various sites and monitoring of the surrounding environments are described. For each of the Sellafield, Drigg, Chapelcross, Springfields and Capenhurst sites, details are given on normal operations, radioactive discharges in gaseous, liquid or solid forms, environmental monitoring routines and collective dose and critical group estimates. The second, linked, volume of this report covers certificates of authorisation issued to the company. (UK)

  7. Annual report on radioactive discharges and monitoring of the environment 1984

    International Nuclear Information System (INIS)

    1985-01-01

    Information is given on the liquid, airborne, and solid radioactive discharges through authorised outlets, and on environmental monitoring for all of BNFL's works and sites for 1984; ie Sellafield site and Drigg storage and disposal site; Chapelcross works; Springfields works and Ulnes Walton disposal site; Capenhurst works. Included is assessment of radiation doses to representative members of the most highly exposed group of the general population for the most important environmental pathways. (author)

  8. Analysis and radiological assessment of survey results and samples from the beaches around Sellafield

    International Nuclear Information System (INIS)

    Webb, G.A.M.; Fry, F.A.

    1983-12-01

    After radioactive sea debris had been found on beaches near the BNFL, Sellafield, plant, NRPB was asked by the Department of the Environment to analyse some of the samples collected and to assess the radiological hazard to members of the public. A report is presented containing an analysis of survey reports for the period 19 November - 4 December 1983 and preliminary results of the analysis of all samples received, together with the Board's recommendations. (author)

  9. Safety Case for Safe-store

    International Nuclear Information System (INIS)

    Woollam, Paul B.

    2002-01-01

    Magnox Electric plc (Magnox), a wholly owned subsidiary of BNFL, owns 26 gas-cooled, graphite-moderated units on 11 sites in the UK. Eight units have been permanently shutdown and the remainder will shut this decade in a currently declared closure programme. The first of these reactors went to power in 1952 and the fleet has generated typically 9% of the UK's electricity during the last five decades. In accordance with UK Government policy, BNFL aims for a systematic and progressive reduction in hazards on its decommissioning sites. The end-point of the decommissioning process is that the reactors will be dismantled and their sites de-licensed. This will be done through minimising both the risks to the public, workers and the environment and also the lifetime cost, consistent with world class safety. There will be passive safe storage during deferment periods and it is BNFL's clear intent that the reactors will not be Safe-stored indefinitely. The main hazard associated with any decommissioned nuclear site is the spent fuel. Hence the reactors will be de-fuelled as soon as practicable after shutdown. After this work is complete, Cs-137 contaminated plant (e.g. fuel pools, effluent plant, and drains) will be dismantled when it is no longer needed. All other plant and buildings will also be dismantled when they are no longer needed, except for the reactor buildings which will be put into passive safe storage. Co-60 contaminated plant, such as steam generators, will be dismantled with the reactors. The reactors will be dismantled in a sequenced programme, with a notional start time around 100 years from shutdown. Magnox Electric is ensuring that the reactors and primary circuits on all its sites are well characterised. We have carried out a detailed, peer reviewed hazard identification on the lead site from which we have generated a rolling 25-year basic safety case. We have then searched for cliff edge effects and possible long-term changes to generate the 100-year

  10. Product evaluation phase I report

    International Nuclear Information System (INIS)

    Kearsey, H.A.; Cumming, I.W.

    1984-01-01

    This report concerns the intermediate-level radioactive waste arisings from the reprocessing of irradiated nuclear fuel at BNFL Sellafield. Headings are: introduction (origin of wastes -the THORP dissolver liquor is clarified by centrifugation before passing to the solvent extraction plant; current stocks and future arisings); characteristics of the waste stream; (colloids in the form of cake); initial evaluation of encapsulation options -evaluation of potential matrices for solidification of waste in form suitable for disposal; waste simulation. (U.K.)

  11. Product evaluation phase 1 report

    International Nuclear Information System (INIS)

    Kearsey, H.A.

    1984-01-01

    This report concerns the intermediate-level radioactive waste arisings from the reprocessing of irradiated nuclear fuel at BNFL Sellafield. HEPA filters are used on all THORP ventilation streams to prevent egress of active and potentially active particulate matter from the plant. Headings are: general information (origin and future arisings); characteristics of the waste stream; initial evaluation of encapsulation options - evaluation of potential matrices for encapsulation of waste in form suitable for disposal; waste simulation (U.K.)

  12. Development of a virtual training simulator for a challenging refurbishment task

    International Nuclear Information System (INIS)

    Mort, P.E.

    1996-01-01

    An overview is presented of the technology, developed by British Nuclear Fuels Limited (BNFL), to create a virtual training simulator for refurbishment tasks. It focuses on the Raffinate Project, a challenging plant modification take, performed remotely, during which component removal, welding and installation of new components are all undertaken. The Training Simulator developed required fast multiprocessor computing with system intercommunication. Operators responded well to the Training Simulator and further improvements to the system are underway. (UK)

  13. Conclusions of a study for the large scale melting of radioactive steel scrap arising from the dismantling of nuclear installations

    International Nuclear Information System (INIS)

    Cross, M.T.

    1992-01-01

    This Summary Paper gives an overview of the feasibility assessment carried out by AEA Technology for the evaluation of melting as a waste conditioning method for metallic Low-Level Wastes (LLW). The assessment wa carried out on behalf of BNFL, Nuclear Electric (NE) and the Department of Energy (DEn) in a work programme started in 1987 and completed during 1990. The salient technical findings and economic arguments for the method are presented in this brief appraisal of the study

  14. BTC the UK focus for nuclear fission R and D in the post NDA era

    International Nuclear Information System (INIS)

    Rice, T.G.; Carpenter, J.C.; Williamson, R.

    2005-01-01

    The BNFL Technology Centre at Sellafield, UK, will provide the focal point for nuclear fission R and D in the UK for the 21th Century. The facility provides a range of non-active, trace active, plutonium active and high active facilities enabling NSTS to support the Nuclear Decommissioning Authority's remit to manage the UK's nuclear legacy and other requirements The facilities also provide an environment for academic research and foster the development of University Research Alliances. (Author)

  15. Memento. Maritime transport of MOX fuels from Europe to Japan

    International Nuclear Information System (INIS)

    1999-07-01

    The maritime transport of MOX fuels from Europe to Japan represents the last of the 3 steps of transport of the nuclear fuel reprocessing-recycling program settled between ORC (Japan), BNFL (UK) and Cogema (France). This document summarizes the different aspects of this program: the companies concerned, the physical protection measures, the US-Japan agreements (accompanying warship), the in-depth safety, the handling of MOX fuels (containers and ships), and the Japan MOX fuel needs. (J.S.)

  16. Product evaluation phase 1 report

    International Nuclear Information System (INIS)

    Kearsey, H.A.; Cumming, I.W.

    1984-01-01

    This report concerns the intermediate-level radioactive waste arisings from the reprocessing of irradiated nuclear fuel at BNFL Sellafield. The waste arises during the storage, in multi-element bottles (MEB), and removed of LWR fuel elements in Sellafield feed ponds, in the form of crud and filter-aid. Headings are: introduction (origin of waste; current stocks and future arisings); waste characterisation; initial evaluation of potential matrices for encapsulation of waste in form suitable for disposal; waste simulation. (U.K.)

  17. Setting the scenario - potential hazards of the nuclear fuel cycle

    International Nuclear Information System (INIS)

    Berry, R.J.; McPhail, N.

    1989-01-01

    The range of nuclear fuel cycle services provided by the various plants belonging to BNFL throughout the UK are described. The Sellafield Reprocessing Plant as the site which has the greatest potential for radiological hazard is then considered in more detail. In particular the safety cycle designed to prevent radiological accidents at Sellafield, emergency planning, the consequences of a major accident at Sellafield and the medical arrangements in the event of an accident are all discussed. (UK)

  18. Torness delay is storing up trouble

    International Nuclear Information System (INIS)

    Cavenagh, Andrew.

    1994-01-01

    A recent decision by the Scottish Office to delay planning permission for the construction of a 50 million dry store for spent nuclear fuel at Torness Power Station is proving frustrating and inexplicable to many in the nuclear industry. The possible reasons for this apparent about face in government policy on spent fuel management are debated and the economic ramifications of the decision for British Nuclear Fuels Limited (BNFL), if the store were to go ahead, are outlined. (UK)

  19. EDRP public local inquiry, UKAEA/BNFL precognition on: EDRP gaseous emissions

    International Nuclear Information System (INIS)

    Walker, B.J.

    1986-01-01

    The Eureopean Demonstration Reprocessing Plant will be equipped with a comprehensive ventilation system to collect, and where appropriate treat, the various gaseous arisings from the plant as well as to provide a safe and comfortable working environment for the operators. The purpose of the treatment systems is to reduce the levels of those substances, both radioactive and non-radioactive, which would otherwise have an adverse effect on the environment if discharged without treatment. The ventilation system proposed for the main process areas and the associated treatment system is described. (author)

  20. Studies on irradiated BNFL culture medium for decontamination and longer storage

    International Nuclear Information System (INIS)

    Singh, Antaryami; Malodia, P.; Jain, S.K.; Ram Gopal

    2001-01-01

    The feasibility of gamma radiation for microbial decontamination and shelf-life extension of culture medium was studied. Changes in total viable count, coliform count and fungal count on exposure to 5, 10, 15, 20 and 25 kGy of gamma radiation were examined. The total viable counts were reduced on irradiation. Complete destruction of bacterial and fungal contamination was observed at 20 kGy. Studies were conducted to examine the changes in microbial contamination of the medium during storage. There was no post irradiation proliferation of microorganisms. Also, no significant change in the efficiency of the irradiated culture medium was observed. Thus, irradiation is extremely useful for longer storage and quality-assurance. (author)

  1. Index to UKAEA, BNFL, MOD(PE) AWRE and recommended external standards

    International Nuclear Information System (INIS)

    1977-11-01

    The principal part of the document consists of an alphabetical index and numerical index to United Kingdom Atomic Energy Authority, British Nuclear Fuels Limited, and Atomic Weapons Research Establishment standards, engineering and general stores. Also included are: an index to Engineering Equipment Users Association handbooks and documents, members' specifications, codes of practice and handbooks; British Standard Codes of practice (for building, electrical engineering, civil engineering, mechanical engineering); UKAEA Standardisation Committee memoranda and metric guides; and miscellaneous documents. (U.K.)

  2. Assessment of prospective foodchain doses from radioactive discharges from BNFL Sellafield

    International Nuclear Information System (INIS)

    Ould-Dada, Z.; Tucker, S.; Webbe-Wood, D.; Mondon, K.; Hunt, J.

    2002-01-01

    This paper presents the method used by the UK Food Standards Agency (FSA) to assess the potential impact of proposed radioactive discharges from the Sellafield nuclear site on food and determine their acceptability. It explains aspects of a cautious method that has been adopted to reflect the UK government policy and uncertainties related to people's habits with regard to food production and consumption. Two types of ingestion doses are considered in this method: 'possible' and 'probable' doses. The method is specifically applied to Sellafield discharge limits and calculated possible and probable ingestion doses are presented and discussed. Estimated critical group ingestion doses are below the dose limit and constraint set for members of the public. The method may be subject to future amendments to take account of changes in government policy and the outcome of a recent Consultative Exercise on Dose Assessments carried out by FSA. Uncertainties inherent in dose assessments are discussed and quantified wherever possible

  3. EDRP public local inquiry, UKAEA/BNFL precognition on: General environmental aspects

    International Nuclear Information System (INIS)

    Driver, P.A.

    1986-01-01

    Details of the existing environment of the proposed EDRP site and its environs are presented. An assessment is made of the expected impact of the construction and operation of EDRP at the Dounreay Nuclear Establishment. Relevant extracts from the Environmental Impact Assessment, published by the Applicants, are included. (UK)

  4. Thermal analyses of SRS Pu storage cans inside BNFL 3013 container

    International Nuclear Information System (INIS)

    Paul, P.K.

    1999-10-01

    Plutonium metal is stored at the Savannah River Site (SRS) using different storage can configurations. The temperatures at different locations in the storage configuration play an important role in designing and configuring different storage arrangements. The present work consists of calculating temperatures at different locations in two different storage configurations

  5. Status of spent fuel management in the United Kingdom

    International Nuclear Information System (INIS)

    Dodds, R.

    1996-01-01

    Nuclear generating capacity in the UK is static with no units currently under construction following the completion of the Sizewell B PWR. The Government's reviews of nuclear energy policy and radioactive waste management policy have been published following a public consultation procedure, largely with an endorsement of current policies. Nuclear Electric plc (NE) and Scottish Nuclear Limited's (SNL) AGR and PWR stations are to be privatised as two subsidiaries of a holding company, and it is planned that the Magnox stations and their liabilities will be kept in the public sector, initially in a stand alone company but ultimately integrated with BNFL. Prompt reprocessing of all Magnox fuel will continue. NE and SNL have signed contracts for extensive reprocessing of AGR fuel. In addition, SNL has agreed contractual arrangements with BNFL for long term storage of its remaining overlife arisings of AGR fuel and has therefore on commercial ground opted not to dry store their fuel at the reactor site. NE have not yet made a decision on the fate of their AGR fuel not covered by existing reprocessing contracts. No option selection has taken place for PWR fuel. Following the closure of the Dounreay PFR and the withdrawal from the EFR project, the option of recycle of plutonium in fast reactors has been suspended. (author)

  6. Solid Waste Operations Complex W-113, Detail Design Report (Title II). Volume 1: Title II design report

    International Nuclear Information System (INIS)

    1995-09-01

    The Solid Waste Retrieval Facility--Phase 1 (Project W113) will provide the infrastructure and the facility required to retrieve from Trench 04, Burial ground 4C, contact handled (CH) drums and boxes at a rate that supports all retrieved TRU waste batching, treatment, storage, and disposal plans. This includes (1) operations related equipment and facilities, viz., a weather enclosure for the trench, retrieval equipment, weighing, venting, obtaining gas samples, overpacking, NDE, NDA, shipment of waste and (2) operations support related facilities, viz., a general office building, a retrieval staff change facility, and infrastructure upgrades such as supply and routing of water, sewer, electrical power, fire protection, roads, and telecommunication. Title I design for the operations related equipment and facilities was performed by Raytheon/BNFL, and that for the operations support related facilities including infrastructure upgrade was performed by KEH. These two scopes were combined into an integrated W113 Title II scope that was performed by Raytheon/BNFL. Volume 1 provides a comprehensive narrative description of the proposed facility and systems, the basis for each of the systems design, and the engineering assessments that were performed to support the technical basis of the Title II design. The intent of the system description presented is to provide WHC an understanding of the facilities and equipment provided and the A/E's perspective on how these systems will operate

  7. Realising the organisational learning opportunities

    International Nuclear Information System (INIS)

    Pomfret, D.G.; Bradford, S.T.

    2000-01-01

    An aspect of proactive safety management is learning lessons from unforeseen events. As BNFL has expanded and extended its nuclear services to many more sites, the potential for organisational learning has grown, but sharing through informal networking has become progressively harder. This potential problem has been solved by implementing formalised company-wide arrangements to turn incidents and accidents into organisational learning opportunities through a system called 'Learning from Experience' (LFE). LFE enables event causes and corrective actions to be identified and shared across all BNFL's sites, initially in the UK but ultimately throughout the world. The result is prevention of events having similar causes, and development of a learning culture which breaks down the barriers to adopting best practice'. Key aspects of the system are: Applying root cause analysis to all significant events; Logging all events, their causes and corrective actions onto a Company-wide database; Screening the database regularly by locally appointed Feedback Co-ordinators trained in identifying learning opportunities and knowledgeable of their own business area, and; Placing and tracking actions to prevent similar events at local Event Review Meetings. The paper describes the implementation and initial experience in operation of the LFE system, which is seen as a significant step towards becoming an expanding and learning company with no accidents or incidents. (author)

  8. Status and prospects for reprocessing

    International Nuclear Information System (INIS)

    Rossney, G.K.

    1977-01-01

    Following the formation of United Reprocessors (U.R.G.) in 1976 by British Nuclear Fuels Limited (B.N.F.L.) in the United Kingdom, the Commissariat a l'Energie Atomique (C.E.A.) in France and K.E.W.A. Kernbrennstoff-Wiederaufarbeitungs-Gesellschaft MBH (K.E.W.A.) in Germany, collaboration is now well established for the marketing of their reprocessing services for irradiated oxide fuel from thermal reactors. In addition collaboration in the continued evolution of the technology has progressed and an extensive research and development programme has been established, the results of which are exchanged between the shareholders. During 1976 the U.K. Government has given approval to B.N.F.L. to sign further contracts with foreign customers, subject to certain conditions. In France, the fuel cycle activities of the C.E.A. have been vested in a new company (Compagnie Generale Des Matieres Nucleaires (C.O.G.E.M.A.)) and their La Hague plant has commenced reprocessing operations on irradiated oxide fuel. In Germany, an agreement has been signed between K.E.W.A. and P.W.K. for the pre-project study for the proposed German plant. Against this background this paper reviews the present status of reprocessing by the shareholders of U.R.G. and the prospects for reprocessing

  9. Efficient heterogeneous execution of Monte Carlo shielding calculations on a Beowulf cluster

    International Nuclear Information System (INIS)

    Dewar, D.; Hulse, P.; Cooper, A.; Smith, N.

    2005-01-01

    Recent work has been done in using a high-performance 'Beowulf' cluster computer system for the efficient distribution of Monte Carlo shielding calculations. This has enabled the rapid solution of complex shielding problems at low cost and with greater modularity and scalability than traditional platforms. The work has shown that a simple approach to distributing the workload is as efficient as using more traditional techniques such as PVM (Parallel Virtual Machine). In addition, when used in an operational setting this technique is fairer with the use of resources than traditional methods, in that it does not tie up a single computing resource but instead shares the capacity with other tasks. These developments in computing technology have enabled shielding problems to be solved that would have taken an unacceptably long time to run on traditional platforms. This paper discusses the BNFL Beowulf cluster and a number of tests that have recently been run to demonstrate the efficiency of the asynchronous technique in running the MCBEND program. The BNFL Beowulf currently consists of 84 standard PCs running RedHat Linux. Current performance of the machine has been estimated to be between 40 and 100 Gflop s -1 . When the whole system is employed on one problem up to four million particles can be tracked per second. There are plans to review its size in line with future business needs. (authors)

  10. The development of an ergonomics standard for the design of operator interfaces

    International Nuclear Information System (INIS)

    Kirwan, B.; Reed, J.; Litherland, M.

    1990-01-01

    BNFL has realised the need to take a consistent approach to the ergonomic design of operator interfaces. Towards this aim, a design standard document has been produced under the direction of a principal design engineer based on the key ergonomics aspects of plant design. The standard was requested by the designers, and the original standard was produced by ergonomists working on BNFL projects. This standard was then reviewed by a large number of key design and operations personnel, and a series of multidisciplinary meetings produced the final version. The standard contains six sections (ergonomics requirements for the design of Control Rooms, Consoles and Panels Design, Labelling, VDU Systems, Alarm Systems and Colour Coding) containing approximately 180 guidelines in text format or supplemented by diagrams and tables. Each guideline is classified as either mandatory or advisory. A high proportion of effort concentrated on making the document usable by designers. The standard is not intended to be fully comprehensive, since the range of possible variations in the designs of interfaces makes such a task intractable at this stage. However, the document does ensure that account is taken of ergonomics throughout the design phase, and particularly in the early phases whilst design change is still cost-effective, and that designers are aware of the important issues and principles. (author)

  11. Transport of MOX fuel

    International Nuclear Information System (INIS)

    Porter, I.R.; Carr, M.

    1997-01-01

    The regulatory framework which governs the transport of MOX fuel is set out, including packages, transport modes and security requirements. Technical requirements for the packages are reviewed and BNFL's experience in plutonium and MOX fuel transport is described. The safety of such operations and the public perception of safety are described and the question of gaining public acceptance for MOX fuel transport is addressed. The paper concludes by emphasising the need for proactive programmes to improve the public acceptance of these operations. (Author)

  12. Radioactivity in surface and coastal waters of the British Isles, 1988

    International Nuclear Information System (INIS)

    Hunt, G.J.

    1989-01-01

    This report presents the results of the aquatic environmental monitoring programme performed during 1988 by the Ministry of Agriculture, Fisheries and Food's (MAFF's) Directorate of Fisheries Research (DFR). Radioactivity measurements are made in aquatic organisms and environmental materials in the vicinity of nuclear establishments including BNFL, UKAEA, nuclear power stations operated by the electricity boards, defence establishments and Amersham International. A summary of estimated public radiation exposures in 1988, relating to liquid radioactive waste discharges from nuclear establishments is presented. (UK)

  13. Radiation risks - how low can one get

    International Nuclear Information System (INIS)

    Bunyard, P.

    1978-01-01

    The level of the maximum permissible dose of ionizing radiation at present adopted is discussed. Statistics relating to the incidence of cancer among persons exposed to radiation are considered, with special reference to workers at the USAEC Hanford plant, persons in Nagasaki or Hiroshima at or shortly after the dropping of the atomic bombs, and children whose mothers were x-rayed during pregnancy. The hearings at the Windscale official inquiry into the proposed BNFL thermal oxide reprocessing plant are also discussed. (U.K.)

  14. Centrifuge design and development

    International Nuclear Information System (INIS)

    Edwards, T.T.; Holmes, M.D.

    1987-01-01

    BNFL has been enriching uranium on an industrial scale using the centrifuge process for over a decade. Together with its Urenco partners, a joint development programme has been and is being vigorously pursued to reduce specific costs, increase output and maintain competitiveness throughout the 1990s. The paper summarises the development of the centrifuge from its earliest concepts through to the centrifuges of today which are jointly designed by the Urenco partners. The potential for further development is also examined. (author)

  15. Tank Farm Contractor Operation and Utilization Plan [SEC 1 Thru 3

    International Nuclear Information System (INIS)

    KIRKBRIDE, R.A.

    2000-01-01

    This document updates the operating scenario and plans for feed delivery to BNFL Inc. of retrieval and waste from single-shell tanks, and the overall process flowsheets for Phases 1 and 2 of the River Protection Project. The plans and flowsheets are updated with the most recent guidance from ORP and tank-by-tank inventory. The results provide the technical basis for the RTP-2 planning effort. Sensitivity cases were run to evaluate the effect of changes on key parameters

  16. The permission of transport of irradiated nuclear fuel elements

    International Nuclear Information System (INIS)

    Klomberg, T.J.M.

    2000-01-01

    In July and October 2000 the Dutch government granted permits for the transportation of irradiated nuclear fuel elements. The environmental organization Greenpeace objected against the permit, but that was rejected by the Dutch Council of State. A brief overview is given of the judgements and the state-of-the-art with respect to the transportation of the elements from Dutch reactors and storage facilities in Petten, Dodewaard and Borssele to Cogema in La Hague, France and BNFL in Sellafield, England

  17. Country report for the UK

    International Nuclear Information System (INIS)

    Hesketh, Kevin

    2001-01-01

    Status of nuclear power generation in Britain can be summarised as follows: 7 Agr type reactors and 1 PWR, capacity 9.6 GW, and 7 Magnox reactors, capacity 2.9 GW. The fast reactors research and development programme is not sponsored by the Government, except for decommissioning work at Dounreay. Small BNFL-founded programme involves technology in fast reactor research and development in several fields: knowledge preservation, Capran-Cuadra European cooperation; Eu fifth framework activities; collaboration with Japanese research organisations

  18. The role of advertising in promoting Sellafield

    Energy Technology Data Exchange (ETDEWEB)

    Cartwright, Bob [BNFL (United Kingdom)

    1989-07-01

    During the last two and half years, British Nuclear Fuels havevspent approaching 9 million pounds on advertising, expenditure designed to increase the public's acceptance of nuclear power and BNFL's operations in particular. That money has been spent against a difficult background, the campaign having started just seven weeks after the Chernobyl disaster, although the strategy, was developed before Chernobyl changed so many people's attitude towards nuclear power. Sellafield was seen by many in the nuclear industry, and not only in Britain, as a major problem, and the public, judging by opinion research conducted at the time, shared that view. Research showed: Most people Saw BNFL as an environmental polluter and a danger to health; Sellafield was aeon as a dangerous place at which to work or near which to live; BNFL was seen as secretive and dishonest. One of the major argument for using advertising as the focal point of any major campaign is that, unlike press relations, it can be controlled. This was particularly important, as the press coverage was already bad, and something dramatic had to be done to change the situation. At first, we considered two fairly obvious strategies. To try and explain the benefits of nuclear power and BNFL's role, and secondly to explain the risks and put them into the context of other everyday risks. The campaign started in June 1986, with colour advertisements in magazines and newspaper supplements. Attached to the advertisement were invitation cards, with nine million printed. This was followed by a 50 second TV advertisement, broadcast nationally. Our aim to make the campaign newsworthy certainly worked. With the help of a public relations exercise, the TV ad was shown on a wide range of news programmes, and many newspaper articles were written about this new approach to selling nuclear power to the public. People started to visit Sellafield in ever increasing numbers. The biggest surprise was at the end of 1987, when Sellafield

  19. Managing plutonium in Britain. Current options[Mixed oxide nuclear fuels; Nuclear weapons

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-09-01

    This is the report of a two day meeting to discuss issues arising from the reprocessing of plutonium and production of mixed oxide nuclear fuels in Britain. It was held at Charney Manor, near Oxford, on June 25 and 26, 1998, and was attended by 35 participants, including government officials, scientists, policy analysts, representatives of interested NGO's, journalists, a Member of Parliament, and visiting representatives from the US and Irish governments. The topic of managing plutonium has been a consistent thread within ORG's work, and was the subject of one of our previous reports, CDR 12. This particular seminar arose out of discussions earlier in the year between Dr. Frank Barnaby and the Rt. Hon. Michael Meacher MP, Minister for the Environment. With important decisions about the management of plutonium in Britain pending, ORG undertook to hold a seminar at which all aspects of the subject could be aired. A number of on-going events formed the background to this initiative. The first was British Nuclear Fuels' [BNFL] application to the Environment Agency to commission a mixed oxide fuel [MOX] plant at Sellafield. The second was BNFL's application to vary radioactive discharge limits at Sellafield. Thirdly, a House of Lords Select Committee was in process of taking evidence, on the disposal of radioactive waste. Fourthly, the Royal Society, in a recent report entitled Management of Separated Plutonium, recommended that 'the Government should commission a comprehensive review... of the options for the management of plutonium'. Four formal presentations were made to the meeting, on the subjects of Britain's plutonium policy, commercial prospects for plutonium use, problems of plutonium accountancy, and the danger of nuclear terrorism, by experts from outside the nuclear industry. It was hoped that the industry's viewpoint would also be heard, and BNFL were invited to present a paper, but declined on the grounds that they

  20. Managing plutonium in Britain. Current options

    International Nuclear Information System (INIS)

    1998-01-01

    This is the report of a two day meeting to discuss issues arising from the reprocessing of plutonium and production of mixed oxide nuclear fuels in Britain. It was held at Charney Manor, near Oxford, on June 25 and 26, 1998, and was attended by 35 participants, including government officials, scientists, policy analysts, representatives of interested NGO's, journalists, a Member of Parliament, and visiting representatives from the US and Irish governments. The topic of managing plutonium has been a consistent thread within ORG's work, and was the subject of one of our previous reports, CDR 12. This particular seminar arose out of discussions earlier in the year between Dr. Frank Barnaby and the Rt. Hon. Michael Meacher MP, Minister for the Environment. With important decisions about the management of plutonium in Britain pending, ORG undertook to hold a seminar at which all aspects of the subject could be aired. A number of on-going events formed the background to this initiative. The first was British Nuclear Fuels' [BNFL] application to the Environment Agency to commission a mixed oxide fuel [MOX] plant at Sellafield. The second was BNFL's application to vary radioactive discharge limits at Sellafield. Thirdly, a House of Lords Select Committee was in process of taking evidence, on the disposal of radioactive waste. Fourthly, the Royal Society, in a recent report entitled Management of Separated Plutonium, recommended that 'the Government should commission a comprehensive review... of the options for the management of plutonium'. Four formal presentations were made to the meeting, on the subjects of Britain's plutonium policy, commercial prospects for plutonium use, problems of plutonium accountancy, and the danger of nuclear terrorism, by experts from outside the nuclear industry. It was hoped that the industry's viewpoint would also be heard, and BNFL were invited to present a paper, but declined on the grounds that they were 'currently involved in a formal

  1. The role of advertising in promoting Sellafield

    International Nuclear Information System (INIS)

    Cartwright, Bob

    1989-01-01

    During the last two and half years, British Nuclear Fuels havevspent approaching 9 million pounds on advertising, expenditure designed to increase the public's acceptance of nuclear power and BNFL's operations in particular. That money has been spent against a difficult background, the campaign having started just seven weeks after the Chernobyl disaster, although the strategy, was developed before Chernobyl changed so many people's attitude towards nuclear power. Sellafield was seen by many in the nuclear industry, and not only in Britain, as a major problem, and the public, judging by opinion research conducted at the time, shared that view. Research showed: Most people Saw BNFL as an environmental polluter and a danger to health; Sellafield was aeon as a dangerous place at which to work or near which to live; BNFL was seen as secretive and dishonest. One of the major argument for using advertising as the focal point of any major campaign is that, unlike press relations, it can be controlled. This was particularly important, as the press coverage was already bad, and something dramatic had to be done to change the situation. At first, we considered two fairly obvious strategies. To try and explain the benefits of nuclear power and BNFL's role, and secondly to explain the risks and put them into the context of other everyday risks. The campaign started in June 1986, with colour advertisements in magazines and newspaper supplements. Attached to the advertisement were invitation cards, with nine million printed. This was followed by a 50 second TV advertisement, broadcast nationally. Our aim to make the campaign newsworthy certainly worked. With the help of a public relations exercise, the TV ad was shown on a wide range of news programmes, and many newspaper articles were written about this new approach to selling nuclear power to the public. People started to visit Sellafield in ever increasing numbers. The biggest surprise was at the end of 1987, when Sellafield

  2. Final Report: Pilot-scale Cross-flow Filtration Test - Envelope A + Entrained Solids

    International Nuclear Information System (INIS)

    Duignan, M.R.

    2000-01-01

    This report discusses the results of the operation of a cross-flow filter in a pilot-scale experimental facility that was designed, built, and run by the Experimental Thermal Fluids Laboratory of the Savannah River Technology Center of the Westinghouse Savannah River Company.This filter technology was evaluated for its inclusion in the pretreatment section of the nuclear waste stabilization plant being designed by BNFL, Inc. This plant will be built at the U.S. Department of Energy's Hanford Site as part of the River Protection Project

  3. Final Report: Pilot-Scale X-Flow Filtration Test - Env C Plus Entrained Solids Plus Sr/TRU

    International Nuclear Information System (INIS)

    Duignan, M.R.

    2000-01-01

    This report discusses the results of the operation of a cross-flow filter in a pilot-scale experimental facility that was designed, built, and run by the Experimental Thermal Fluids Laboratory of the Savannah River Technology Center of the Westinghouse Savannah River Company. This filtration technology was evaluated for its inclusion in the pretreatment section of the nuclear waste stabilization plant being designed by BNFL, Inc. The plant will be built at the U.S. Department of Energy's Hanford Site as part of the River Protection Project

  4. Annual report and accounts 1986-1987

    International Nuclear Information System (INIS)

    1994-02-01

    The chairman's review summarizes the company achievements over the year 1986/7, especially having met all customer requirements by reaching every production target. This also gave improved financial results. Increased public support for nuclear power was also set as one of BNFL's targets. Each main area of operation is looked at: fuel supply, including fuel manufacture at Springfields, enrichment at Capenhurst and spent fuel management at Sellafield. The accounts show an operating profit of Pound 196 million on a turnover of Pound 792 million. (UK)

  5. Product evaluation phase 1 report

    International Nuclear Information System (INIS)

    Kearsey, H.A.; Hornby, J.

    1984-01-01

    This report concerns the intermediate-level radioactive waste arisings from the reprocessing of irradiated nuclear fuel at BNFL Sellafield. The waste arises from the reprocessing of uranium from overseas PWR type reactors and is the solid dissolver waste remaining after the fuel has been extracted. Headings are: general introduction (origin, current stocks and future arisings); characteristics of the waste stream; alternative matrices - evaluation of potential matrices for encapsulation of waste in form suitable for disposal; waste simulation; relevance of other phase II studies. (U.K.)

  6. Product evaluation phase 1 report

    International Nuclear Information System (INIS)

    Kearsey, H.A.; Page, R.J.

    1984-01-01

    This report concerns the intermediate-level radioactive waste arisings from the reprocessing of irradiated nuclear fuel at BNFL Sellafield. The waste arises from the reprocessing of CAGR fuel assemblies, which consist of fuel pins held inside a graphite sleeve by means of stainless steel support grids and braces. Headings are: introduction (origin of waste and future arisings); waste characterisation; initial evaluation of encapsulation options - evaluation of potential matrices for encapsulation of waste in form suitable for disposal; waste simulation; relevance of other phase II studies. (U.K.)

  7. Product evaluation phase 1 report

    International Nuclear Information System (INIS)

    Kearsey, H.A.; Hornby, J.

    1984-01-01

    This report concerns the intermediate-level radioactive waste arisings from the reprocessing of irradiated nuclear fuel at BNFL Sellafield. The waste arises from the reprocessing of uranium from overseas BWR type reactors and is the solid dissolver waste remaining after the fuel has been extracted. Headings are: general introduction (origin, current stocks and future arisings); characteristics of the waste stream; alternative matrices - evaluation of potential matrices for encapsulation of waste in form suitable for disposal; waste simulation; relevance of other phase II studies. (U.K.)

  8. Practical decommissioning experience with nuclear installations in the European Community

    International Nuclear Information System (INIS)

    Skupinski, E.

    1992-01-01

    Initiated by the Commission of the European Communities (CEC), this seminar was jointly organized by the AEA, BNFL and the CEC at Windermere and the sites of Windscale/Sellafield, where the former Windscale advanced gas-cooled reactor and the Windscale piles are currently being dismantled. The meeting aimed at gathering a limited number of European experts for the presentation and discussion of operations, results and conclusions on techniques and procedures currently applied in the dismantling of large scale nuclear installations in the European Community

  9. The evolution of a LIMS [laboratory information management system

    International Nuclear Information System (INIS)

    Anon.

    1992-01-01

    Changes in the world and United Kingdom markets for nuclear fuels during the 1990s have prompted British Nuclear Fuels (BNFL) to maximise cost effectiveness in its Chemical and Metallurgical Services department. A laboratory information management system (LIMS) was introduced in order to keep records of analytical techniques and equipment up to date by coordinating various computer systems. Wherever possible automated systems have replaced traditional, labour intensive techniques. So successful has the LIMS system been, that the team now hopes to expand into expert systems. (UK)

  10. Benefiting through partnering

    International Nuclear Information System (INIS)

    Carr, T.J.

    2000-01-01

    As a consequence of dramatic changes in the world market in nuclear services over the last decade, BNFL has embarked on a comprehensive strategic review of its business. Central to this review has been the need for the company to achieve cost reduction and improved efficiency in all aspects of its business. An area where substantial benefits can be gained is in improved efficiency in the discharge of the capital expenditure programme. This paper focuses on the opportunity of profiting through partnering in capital project delivery. (author)

  11. Annual report on radioactive discharges and monitoring of the environment 1992. V. 2

    International Nuclear Information System (INIS)

    1993-01-01

    This Annual Report supplements British Nuclear Fuel plc's Health and Safety Annual Report by providing more detailed information on radioactive discharges, monitoring of the environmental and critical group doses. BNFL has published Annual Reports on Radioactive Discharges and Monitoring of the Environment, covering the period from 1977 to the present. For 1991 this report has been sub-divided into two complementary parts. Volume II reproduces the Certificates of Authorisation under which the Company operates and the statutory environmental monitoring programmes which relate to them. (author)

  12. For sale: 7 AGR stations and a brand new PWR

    International Nuclear Information System (INIS)

    Anon.

    1995-01-01

    Britain's seven AGR stations and the Sizewell B PWR will pass to private ownership under the UK government's plan to privatise the two nuclear generators, Nuclear Electric and Scottish Nuclear, sometime next year. Under the new set-up, the two generators will become operating subsidiaries of a holding company which will be headquartered in Scotland. The companies' ageing Magnox gas-cooled reactors will remain in a separate public sector company before being transferred to British Nuclear Fuels (BNFL) at the time of privatisation. (author)

  13. Annual report on radioactive discharges and monitoring of the environment 1991. V. 2

    International Nuclear Information System (INIS)

    1992-01-01

    This Annual Report supplements British Nuclear Fuel plc's Health and Safety Annual Report by providing more detailed information on radioactive discharges, monitoring of the environmental and critical group doses. BNFL has published Annual Reports on Radioactive Discharges and Monitoring of the Environment, covering the period from 1977 to the present. For 1991 this report has been sub-divided into two complementary parts. Volume II reproduces the Certificates of Authorisation under which the Company operates and the statutory environmental monitoring programmes which relate to them. (author)

  14. Product evaluation phase 1 report

    International Nuclear Information System (INIS)

    Fairhall, G.A.

    1984-01-01

    This report concerns the intermediate-level radioactive waste arisings from the reprocessing of irradiated nuclear fuel at BNFL Sellafield. The site ion exchange effluent plant will remove Cs and Sr from active liquid effluents using Mud Hills clinoptilolite. Approximately 40 to 50 m 3 of spent ion exchanger will be generated each year together with 7.5 m 3 of filter sand. Headings are: introduction; characterisation; initial evaluation of potential matrices for encapsulation of waste in form suitable for disposal; waste simulation. (U.K.)

  15. Corrosion tests of 316L and Hastelloy C-22 in simulated tank waste solutions

    International Nuclear Information System (INIS)

    Danielson, M.J.; Pitman, S.G.

    2000-01-01

    Both the 316L stainless steel and Hastelloy C-22 gave satisfactory corrosion performance in the simulated test environments. They were subjected to 100 day weight loss corrosion tests and electrochemical potentiodynamic evaluation. This activity supports confirmation of the design basis for the materials of construction of process vessels and equipment used to handle the feed to the LAW-melter evaporator. BNFL process and mechanical engineering will use the information derived from this task to select material of construction for process vessels and equipment

  16. Product evaluation phase 1 report

    International Nuclear Information System (INIS)

    Kearsey, H.A.; Cumming, I.W.

    1984-01-01

    This report concerns the intermediate-level radioactive waste arisings from the reprocessing of irradiated nuclear fuel at BNFL Sellafield. The waste occurs as the product of the process to remove carbon-14 from the THORP dissolver off-gas using a caustic scrubber. The carbon dioxide released during fuel dissolution is ultimately fixed as barium carbonate. Headings are: introduction (origin of waste, current stocks and future arisings); waste characterisation; initial evaluation of potential matrices for encapsulation of waste in form suitable for disposal; waste simulation. (U.K.)

  17. National report for United Kingdom. 32nd annual meeting of the IAEA International Working Group on Fast Reactors, Vienna, 18-19 May 1999

    International Nuclear Information System (INIS)

    Abram, T.; Picker, C.

    1999-01-01

    Much of the UK nuclear industry has now completed the transition from state to private ownership. The UK continues to support international development of fast reactor technology, mainly through participation in the European Fast Reactor collaboration, with all funding provided by BNFL. Inactive commissioning is about to begin on the PFR Sodium Disposal Plant, which includes a caesium removal plant. The defuelling machine is being refurbished to permit the control and shutdown rods to be removed. No further reprocessing of fuel has taken place. (author)

  18. Modifications to River Protection Project (RPP) Level -0 Logic

    International Nuclear Information System (INIS)

    SEEMAN, S.E.

    2000-01-01

    The following modifications were made to the River Protection Project Level-0 logic in going from Rev. I to Rev. 2. The first change was the change to the heading at the top of the drawing: ''TWRS Program Logic'' to ''River Protection Project Mission Logic''. Note that purely format changes (e.g., fonts, location of boxes, date format, addition of numbers to ''ghost'' boxes) are not discussed. However, the major format change was to show DOE-BNFL Inc. Interface Control Documents (ICDs) on the logic

  19. Risk perception of nuclear energy and the effect of information

    International Nuclear Information System (INIS)

    Taylor, Caroline

    2000-08-01

    Results from 4 studies are reported. A mixture of survey, experimental and quasi-experimental designs and a variety of samples (undergraduates, postgraduates and graduates of Nottingham University, visitors to Sellafield and a random national UK sample) were used to examine risk perceptions of nuclear energy. The roles of risk, benefit, preference, knowledge, control, trust, attitudes, intentions to act and personality, in relation to nuclear energy, were examined. A survey study examined and explored the above-mentioned variables. Then experimental and quasi-experimental studies were devised using a BNFL video advert, a BNFL written newspaper advert and BNFL's Sellafield Visitors' Centre (SVC), to test the effectiveness of information on these variables. Through pre-post experimental and quasi-experimental studies, it was shown that levels of knowledge could be increased through information. This increase was also seen to be sustained over time, especially when people engaged in their learning environment (reading a newspaper or going to Sellafield). Regarding levels of knowledge, passively watching a video had a significant but very small effect. Changes in attitudes were also recorded, although these were only sustained over time for the Visitors' Centre. Concerning the other variables in question, changes in perceived risk, perceived benefit and preference were also recorded for the samples, although these results either could not be attributed to the different types of information, were not sustained or were no different to observations in the control groups. Some changes were recorded for aspects of control in the advert study although none were seen in the SVC study. No changes were found in trust for any of the different types of information. The main, consistent finding, was that sustained changes were recorded for knowledge and attitudes. These were both found to be linked to many of the variables under investigation, including risk perception. A study

  20. Nested Fixed-Depth Fluidic Sampler and At Tank Analysis System Deployment Strategy and Plan

    International Nuclear Information System (INIS)

    REICH, F.R.

    2000-01-01

    Under the Hanford Site River Protection Project (RPP) privatization strategy, the U.S. Department of Energy (DOE) Office of River Protection (ORP) requires the CH2M Hill Hanford Group, Inc. (CHG) to supply tank waste to the privatization contractor, BNFL Inc. (BNFL), for separation and/or treatment and immobilization (vitrification). Three low-activity waste (LAW) specification envelopes represent the range of liquid waste types in the large, Hanford Site underground waste storage tanks. The CHG also is expected to supply high-level waste (HLW) separation and/or treatment and disposal. The HLW envelope is an aqueous slurry of insoluble suspended solids (sludge). The Phase 1 demonstration will extend over 24 years (1996 through 2019) and will be used to resolve technical uncertainties. About one-tenth of the total Hanford Site tank waste, by mass, will be processed during this period. This document provides a strategy and top-level implementation plan for demonstrating and deploying an alternative sampling technology. The alternative technology is an improvement to the current grab sampling and core sampling approaches that are planned to be used to support the RPP privatization contract. This work also includes adding the capability for some at-tank analysis to enhance the potential of this new technology to meet CHG needs. The first application is to LAW and HLW feed staging for privatization; the next is to support cross-site waste transfer from 200 West Area tanks

  1. Theoretical, Methodological, and Empirical Approaches to Cost Savings: A Compendium

    Energy Technology Data Exchange (ETDEWEB)

    M Weimar

    1998-12-10

    This publication summarizes and contains the original documentation for understanding why the U.S. Department of Energy's (DOE's) privatization approach provides cost savings and the different approaches that could be used in calculating cost savings for the Tank Waste Remediation System (TWRS) Phase I contract. The initial section summarizes the approaches in the different papers. The appendices are the individual source papers which have been reviewed by individuals outside of the Pacific Northwest National Laboratory and the TWRS Program. Appendix A provides a theoretical basis for and estimate of the level of savings that can be" obtained from a fixed-priced contract with performance risk maintained by the contractor. Appendix B provides the methodology for determining cost savings when comparing a fixed-priced contractor with a Management and Operations (M&O) contractor (cost-plus contractor). Appendix C summarizes the economic model used to calculate cost savings and provides hypothetical output from preliminary calculations. Appendix D provides the summary of the approach for the DOE-Richland Operations Office (RL) estimate of the M&O contractor to perform the same work as BNFL Inc. Appendix E contains information on cost growth and per metric ton of glass costs for high-level waste at two other DOE sites, West Valley and Savannah River. Appendix F addresses a risk allocation analysis of the BNFL proposal that indicates,that the current approach is still better than the alternative.

  2. Design and development of effluent treatment plants for the Sellafield reprocessing factory

    International Nuclear Information System (INIS)

    Howden, M.

    1989-01-01

    The reprocessing of spent nuclear fuel has been carried out at Sellafield since the early 1950s. The storage of fuel in water filled ponds prior to reprocessing and the reprocessing operation itself results in the generation of a number of radioactive liquid effluents. The highly active liquors are stored in stainless steel tanks and will, with the commissioning of the Windscale Vitrification Plant, be converted into glass for long term storage and disposal. The medium and low active liquors are, after appropriate treatment, discharged to sea well below the Authorised Limits which are set by the appropriate Regulatory Bodies. Since 1960 these have been the Department of the Environment and the Ministry of Agriculture, Fisheries and Food. Even though the discharges have been well below the limits set, BNFL have for many years adopted a policy of reducing the levels of activity still further. Considerable progress has already been made, by changing reprocessing operations regimes but more importantly by the development and construction of specialised effluent treatment plants. Further reductions are, however, planned. Two major effluent treatment plants form the main basis of BNFL's policy to reduce activity discharges from Sellafield. The first, the Site Ion Exchange Effluent Plant, to treat storage pond water was brought into operation in 1985. The second, the enhanced Actinide Removal Plant to treat medium and low active effluents, is programmed to operate in 1992. (author)

  3. EDRP public local inquiry, UKAEA/BNFL precognition on: Safety aspects of transport

    International Nuclear Information System (INIS)

    Brown, M.L.

    1986-02-01

    The transport of spent fuels and radioactive wastes by rail, sea and air is considered in the light of the proposed EDRP at Dounreay. The frequency and severity of accidents and the risks and consequences are discussed for each mode of transport. (UK)

  4. EDRP public local inquiry, UKAEA/BNFL precognition on: EDRP process and plant

    International Nuclear Information System (INIS)

    Walker, B.J.

    1986-01-01

    A description is given of the process to be operated in the proposed EDRP, and of the plant and equipment in which the process will be carried out. The design and construction of new facilities to be provided on the EDRP site at Dounreay are detailed. (U.K.)

  5. EDRP public local inquiry, UKAEA/BNFL precognition on: Safety aspects of EDRP

    International Nuclear Information System (INIS)

    Brown, M.L.

    1986-01-01

    The safety of the proposed EDRP is discussed, paying particular attention to the environmental impact in both normal operation, and in abnormal or accident conditions. The radiological exposure resulting from EDRP discharges during normal operation is estimated. Design measures for ensuring worker and public safety during both routine and non-routine operation are outlined. The strategy for considering unlikely but potentially more serious accidents in EDRP design is outlined. (U.K.)

  6. Developments in support of low level waste disposal at BNFL's Drigg Site

    International Nuclear Information System (INIS)

    Johnson, L.F.

    1988-01-01

    The continued upgrading of low-level waste pretreatment and disposal practices related to the United Kingdom Drigg disposal site is described, noting the need to take into account operational safety, long term post-closure safety, regulatory and public acceptance factors

  7. Recycling experience in the UK - past, present and future

    International Nuclear Information System (INIS)

    Williams, T.

    1991-01-01

    The United Kingdom (UK) has been commercially recycling uranium and developing the technology for the recycle of plutonium from reprocessing of spent fuel for more than two decades. In this article, a spokesman from British Nuclear Fuels plc (BNFL) describes the current experience of recycling in the UK and identifies the remaining technical and strategic elements being implemented to develop fully the recycle of all the products of reprocessing. He also discusses the economic and commercial benefits of using mixed oxide fuels now and in the future. (author)

  8. A perfect fuel supplier

    International Nuclear Information System (INIS)

    Terasvirta, R.

    2008-01-01

    WWER fuel market is dominated by the Russian fuel vendor JSC TVEL. There have been attempts to open up the market also for other suppliers, such as BNFL/Westinghouse for Finland, Czech Republic, and Ukraine. However, at the moment it seems that JSC TVEL is the only real alternative to supply fuel to WWER reactors. All existing fuel suppliers have certified quality management systems which put a special emphasis on the customer satisfaction. This paper attempts to define from the customer's point of view, what are the important issues concerning the customer satisfaction. (author)

  9. Annual report on occupational safety

    International Nuclear Information System (INIS)

    1985-09-01

    A report is given on the occupational safety relating to BNFL's employees for the year 1984 and the results compared to those obtained in 1983. Data are presented for each of the Company's Sites on whole body exposures, accidental deaths and major injuries and nuclear and non-nuclear incidents. The results show that the Company average body dose continues to be less than 5mSv, there were no accidental deaths but 15 major injuries. One nuclear incident and 9 non-nuclear incidents were notified to the Health and Safety Executive. (UK)

  10. Final Report: Pilot-scale Cross-flow Filtration Test - Envelope A + Entrained Solids

    Energy Technology Data Exchange (ETDEWEB)

    Duignan, M.R.

    2000-06-27

    This report discusses the results of the operation of a cross-flow filter in a pilot-scale experimental facility that was designed, built, and run by the Experimental Thermal Fluids Laboratory of the Savannah River Technology Center of the Westinghouse Savannah River Company.This filter technology was evaluated for its inclusion in the pretreatment section of the nuclear waste stabilization plant being designed by BNFL, Inc. This plant will be built at the U.S. Department of Energy's Hanford Site as part of the River Protection Project.

  11. Plant corrosion: prediction of materials performance

    International Nuclear Information System (INIS)

    Strutt, J.E.; Nicholls, J.R.

    1987-01-01

    Seventeen papers have been compiled forming a book on computer-based approaches to corrosion prediction in a wide range of industrial sectors, including the chemical, petrochemical and power generation industries. Two papers have been selected and indexed separately. The first describes a system operating within BNFL's Reprocessing Division to predict materials performance in corrosive conditions to aid future plant design. The second describes the truncation of the distribution function of pit depths during high temperature oxidation of a 20Cr austenitic steel in the fuel cladding in AGR systems. (U.K.)

  12. Improvements in operational safety performance of the Magnox power stations

    Energy Technology Data Exchange (ETDEWEB)

    Marchese, C.J. [BNFL Magnox Generation, Berkeley (United Kingdom)

    2000-10-01

    In the 43 years since commencement of operation of Calder Hall, the first Magnox power station, there remain eight Magnox stations and 20 reactors still in operation, owned by BNFL Magnox Generation. This paper describes how the operational safety performance of these stations has significantly improved over the last ten years. This has been achieved against a background of commercial competition introduced by privatization and despite the fact that the Magnox base design belongs to the past. Finally, the company's future plans for continued improvements in operational safety performance are discussed. (author)

  13. Annual report on radioactive discharges and monitoring of the environment 1981

    International Nuclear Information System (INIS)

    1982-07-01

    A report is given on discharges and disposal of radioactive wastes through authorised outlets and on environmental monitoring for all of BNFL's Company Works and Sites during 1981. At no time during 1981 have discharges and disposals of radioactive wastes at any of the Works or Sites exceeded those laid down in any of the Authorisations. Similarly, environmental monitoring studies have shown that the radiation doses to the most highly exposed group of the general population were significantly lower than the dose limit recommended by the ICRP. (U.K.)

  14. Automated 99Tc analysis in AW-101 and AN-107 ''diluted feed'' matrixes

    International Nuclear Information System (INIS)

    Egorov, O.B.; DE Kurath, D.E.

    2000-01-01

    A process monitor is needed by British Nuclear Fuels Limited, Inc. (BNFL Inc.) to measure total 99 Tc levels in column effluents during technetium removal from the aqueous fraction of the Hanford high-level tank wastes. The monitor must achieve detection limits of 1 x 10 -8 Ci/mL (0.6 microg/mL). Measurements must be done in near real time, with an analysis frequency of approximately15 min. The monitoring technology must be sufficiently simple and robust for unattended continuous operation in the plant settings

  15. Nuclear waste - the unsolved problem

    International Nuclear Information System (INIS)

    Boyle, S.

    1986-01-01

    Nuclear waste is identified and the problems created by reprocessing are mentioned. The disposal option for low, intermediate and high-level radioactive wastes are discussed. Sites where disposal has taken place have been found to be unsatisfactory because of contamination and radionuclide migration. The Nuclear Industry Radioactive Waste Executive (NIREX) is not seen as having any more credibility than the other nuclear authorities involved (BNFL, UKAEA, CEGB). Until an adequate, publically acceptable, method of disposing of the wastes already created has been found the author states that no more should be created. (U.K.)

  16. Final Report: Pilot-Scale X-Flow Filtration Test - Env C Plus Entrained Solids Plus Sr/TRU

    Energy Technology Data Exchange (ETDEWEB)

    Duignan, M.R.

    2000-07-27

    This report discusses the results of the operation of a cross-flow filter in a pilot-scale experimental facility that was designed, built, and run by the Experimental Thermal Fluids Laboratory of the Savannah River Technology Center of the Westinghouse Savannah River Company. This filtration technology was evaluated for its inclusion in the pretreatment section of the nuclear waste stabilization plant being designed by BNFL, Inc. The plant will be built at the U.S. Department of Energy's Hanford Site as part of the River Protection Project.

  17. Novel uses of magnetic separation in the nuclear industry

    International Nuclear Information System (INIS)

    Coe, B.T.

    1999-08-01

    High Gradient Magnetic Separation (HGMS) has been investigated in the nuclear industry, for the application of advanced technology in present and future nuclear environments within BNFL. Previous applications of HGMS have been reviewed and future novel applications investigated. The two most promising applications were then chosen as the focus of the PhD. In the first project, HGMS has been used to selectively recover biologically precipitated iron sulphide (Fe 1-x S) particles containing heavy metal ions, from a BNFL soil remediation effluent stream. The uptake of the ions is believed to be a consequence of the bacterial metabolism and the adsorptive properties of the iron sulphide. Biologically precipitated iron sulphide is known to differ in structure to its chemically precipitated equivalent and as such has certain advantages, for example, increased adsorbent properties and magnetic properties. The HGMS system was optimised and its performance investigated as a function of the magnetic field, the flow rate and the concentration of the biological particles in solution, with time. Results have shown that an efficiency of over 95% can be obtained, proving that HGMS is a valuable method for the concentration of metal ions from contaminated soils, especially when the adsorbed heavy metals are toxic or even radioactive and difficult to handle by other means. In the second project, the removal out of solution of radioactive technetium, in the form of the pertechnate ion [TcO 4 - ] was investigated. This was achieved using ion exchange techniques, Liquid Scintillation Counting LSC and HGMS. (author)

  18. Solid Waste Operations Complex W-113, Detail Design Report (Title II). Volume 5: Design validation assessments and lists

    International Nuclear Information System (INIS)

    1995-09-01

    The Solid Waste Retrieval Facility--Phase 1 (Project W113) will provide the infrastructure and the facility required to retrieve from Trench 04, Burial ground 4C, contact handled (CH) drums and boxes at a rate that supports all retrieved TRU waste batching, treatment, storage, and disposal plans. This includes (1) operations related equipment and facilities, viz., a weather enclosure for the trench, retrieval equipment, weighing, venting, obtaining gas samples, overpacking, NDE, NDA, shipment of waste and (2) operations support related facilities, viz., a general office building, a retrieval staff change facility, and infrastructure upgrades such as supply and routing of water, sewer, electrical power, fire protection, roads, and telecommunication. Title I design for the operations related equipment and facilities was performed by Raytheon/BNFL, and that for the operations support related facilities including infrastructure upgrade was performed by KEH. These two scopes were combined into an integrated W113 Title II scope that was performed by Raytheon/BNFL. The following Code Evaluation analyzes the applicable sections of the National Fire Protection Association (NFPA) 101, Life Safety Code, 1994 Edition and the 1994 Edition of the Uniform Building Code (UBC) to the W113 Trench Enclosure. A Building Code Analysis generally establishes four primary design criteria: occupancy classification; separation requirements; egress requirements; and construction type. The UBC establishes requirements for all criteria. This analysis is limited to the Trench Enclosure Building. The General Office Building and the Retrieval Staff Change Building is not within the scope of this analysis

  19. IFPE/FUMEX-II/CASE27, 7 idealised cases for functional dependence of FGR predictions

    International Nuclear Information System (INIS)

    Turnbull, J.A.; Rossiter, Glyn; Sontheimer, Fritz; Tayal, Mukesh

    2004-01-01

    Description: Seven idealised cases to illustrate the functional dependence of fission gas release (FGR) predictions. (1) Temperature vs Bu for onset of FGR (draft available); (2a) FGR for constant 15 kW/m to 100 MWd/kgU; (2b) FGR for 20 kW/m at BOL decreasing linearly to 10 kW/m at 100 MWd/kgU; (2c) FGR for more realistic power histories supplied by BNFL; (2d) FGR for idealized 'real' histories supplied by FANP; (3a) Candu-Effect of Power on Fission Gas Release; (3b) Candu-Effect of Power Envelope on Fuel Performance

  20. Investigation of the possible increased incidence of cancer in West Cumbria

    International Nuclear Information System (INIS)

    Rubery, E.D.

    1985-01-01

    The report of the Black Advisory Group on an investigation of the possible increased incidence of cancer in West Cumbria is briefly considered. The Advisory Group was unable to reach definite conclusions as to whether there is a link between discharges of radioactive material from BNFL Sellafield and the incidence of cancer due to uncertainties in the available epidemiological data and the radiation dose estimate data. The implementation of ten recommendations of the Black Advisory Group are briefly described covering epidemiological, radiation protection and organisational matters in an effort to clarify the situation and to enhance public safety. (U.K.)

  1. Sellafield - a nuclear licensed site

    International Nuclear Information System (INIS)

    Bloom, Phillipa.

    1987-01-01

    The report is based on the experience gained when visiting the Exhibition Centre at the BNFL Sellafield site and joining the hour-long coach trip round the site. The sights are recorded and a description given of the processes undertaken at Sellafield to reprocess the Magnox fuel and store the spent fuel from AGR reactors. The purpose of the main plant building, and the passage of the spent fuel through the various processes is described. Criticism is made of the safety record at Sellafield and a full and open debate on nuclear power is called for. (UK)

  2. Sellafield: boom or bombshell?

    International Nuclear Information System (INIS)

    Ingham, J.

    1988-01-01

    Building work at the Sellafield reprocessing plant is reviewed. BNFL is about halfway through its programme to build new plants for reprocessing and storing spent nuclear fuels. Most money is being spent on THORP, the thermal oxide reprocessing plant, but vitrification and encapsulation plants are also being built. All the construction work has provided employment for many workers, many from outside the area but also local labour which has altered the local job market. However, problems are envisaged when the construction programme is complete in 1992 and the number of jobs greatly reduced. Unemployment and economic depression are forecast. (U.K.)

  3. The development of a commercial MOX fuel manufacturing capability in the U.K

    International Nuclear Information System (INIS)

    Macphee, D.S.; Young, M.P.

    1995-01-01

    BNFL is implementing a strategy to establish a commercial MOX manufacturing capability within the UK. The design and provision of the fabrication plants is incorporating the considerable experience within the Company of MOX technology, fuel fabrication and nuclear plant design. The first phase of the strategy is complete with the successful operation of the Demonstration Facility. The development programmes supporting the increased scale of operation for a commercial scale facility are substantially complete. Design and construction of a 120t HM/year plant is well advanced supported by a substantial in-house design and project management team. (author)

  4. Radioactivity in surface and coastal waters of the British Isles, 1980

    International Nuclear Information System (INIS)

    Hunt, G.J.

    1982-01-01

    Results are presented for an environmental monitoring programme performed during 1980 by the Fisheries Radiobiological Loaboratory. The programme was set up to verify the satisfactory control of liquid radioactive waste discharges from UK nuclear establishments to the aquatic environment. The results showed that all exposures were well within the ICRP-recommended limit for members of the public. Discharges from BNFL's Sellafield Site gave rise to the highest exposures. The collective effective dose equivalent to the UK population from liquid radioactive discharges in 1980 was 100 man-Sv, a reduction from 130 man-Sv reported for 1979. (U.K.)

  5. THORP's case continues to crumble

    International Nuclear Information System (INIS)

    Roche, P.

    1990-01-01

    With a stockpile of plutonium of over 40 tonnes, there is no need to reprocess spent nuclear fuel for either military use or as fuel for fast reactors. The position of reprocessing at THORP, Sellafield's Thermal Oxide Reprocessing Plant is less secure. BNFL has contracts for the first ten years of THORP's operation but is finding it harder to sign contracts for subsequent years as many countries are now opting for on-site storage of spent fuels rather than reprocessing. The Labour Party has not made a commitment to abandon THORP, but it may not survive economically anyhow. (UK)

  6. A Transparent Framework for guiding Radiological and Non-Radiological Contaminated Land Risk Assessments

    International Nuclear Information System (INIS)

    Lee, Alex; Mathers, Dan

    2003-01-01

    A framework is presented that may be used as a transparent guidance to both radiological and non-radiological risk assessments. This framework has been developed by BNFL, with external consultation, to provide a systematic approach for identifying key system drivers and to guide associated research packages in light of data deficiencies and sources of model uncertainty. The process presented represents an advance on existing working practices yet combines regulator philosophy to produce a robust, comprehensive, cost-effective and transparent work package. It aims at lending added confidence to risk models thereby adding value to the decision process

  7. Fuelling a US reaction

    International Nuclear Information System (INIS)

    Wyman, V.

    1989-01-01

    Within half a dozen years, US operators of nuclear power stations are likely to begin turning their backs on their own government's ideas about how they should get their nuclear fuel. Instead, they will sign up with private companies which want to supply them with uranium enrichment, the key service needed to turn natural uranium into the more potent types used in modern nuclear reactors. This change will be good news in particular for Urenco, the European nuclear fuel enrichment company one third owned by British Nuclear Fuels (BNFL). The prospects for Urenco are assessed. (author)

  8. Failure to substantiate two cases of alleged occupational radiation carcinogenesis

    International Nuclear Information System (INIS)

    Halnan, K.E.

    1988-01-01

    Outline report of two cases tried in Liverpool in July 1987. The first involved a case of Hodgkins disease in a man now 57 years who had worked for B.N.F.L. or its predecessors at Sellafield between 1954 and 1977. The second was a case of adenocarcinoma of the stomach in an employee working at Dounreay between 1958 and 1965. These cases came to court before the new revised calculations of radiation dosage from the Japanese atomic bombs had finally been agreed and published, and also before these had been taken into account by UNSCEAR. (U.K.)

  9. The risk of childhood leukaemia near nuclear establishments

    International Nuclear Information System (INIS)

    Fry, F.A.

    1997-01-01

    The author concentrates on an epidemiological investigation on the increased incidence of leukaemia in young people of age 0∼24 years old in the years of 1963∼1992 in Seascale, a Village near the BNFL reprocessing plant at Sellafield on the north-west coast of England. A comparison of this incidence is made with that revealed in regions of other similar nuclear establishments. It has been concluded that the increased incidence of leukaemia in young people in Seascale can not be imputed to any single factor, but interaction between different factor cannot be ruled out

  10. Toshiba-Westinghouse, the new electronuclear giant

    International Nuclear Information System (INIS)

    Guezel, J.Ch.

    2006-01-01

    Toshiba, so far a minor actor of the world nuclear industry, won in summer 2005 in front of General Electric and Mitsubishi Heavy Industries, the takeover bid launched by the public British organization BNFL which controls Westinghouse. In case of success of this operation, Toshiba will own a quarter of the world nuclear capacities and will become the first competitor of Areva. The main objective of Toshiba is to win market shares abroad thanks to the prospects offered by Westinghouse's technologies in particular in China which is one of the most targeted market today. Short paper. (J.S.)

  11. Annual report on radioactive discharges and monitoring of the environment 1991. V. 1

    International Nuclear Information System (INIS)

    1992-01-01

    This Annual Report supplements and updates British Nuclear Fuel plc's Health and Safety and the Environment Annual Report by providing more detailed information on radioactive discharges, monitoring of the environment and critical groups doses. BNFL has published Annual Reports on Radioactive Discharges and Monitoring of the Environment since 1977. This year the report is again sub-divided into two complementary volumes. Volume I includes, for each of the Company's sites, annual data on radioactive discharges into the environment and the associated environmental monitoring programmes. Critical groups doses for each site are presented in summary tables at the beginning of each chapter. (author)

  12. Risk perception of nuclear energy and the effect of information

    Energy Technology Data Exchange (ETDEWEB)

    Taylor, Caroline

    2000-08-01

    Results from 4 studies are reported. A mixture of survey, experimental and quasi-experimental designs and a variety of samples (undergraduates, postgraduates and graduates of Nottingham University, visitors to Sellafield and a random national UK sample) were used to examine risk perceptions of nuclear energy. The roles of risk, benefit, preference, knowledge, control, trust, attitudes, intentions to act and personality, in relation to nuclear energy, were examined. A survey study examined and explored the above-mentioned variables. Then experimental and quasi-experimental studies were devised using a BNFL video advert, a BNFL written newspaper advert and BNFL's Sellafield Visitors' Centre (SVC), to test the effectiveness of information on these variables. Through pre-post experimental and quasi-experimental studies, it was shown that levels of knowledge could be increased through information. This increase was also seen to be sustained over time, especially when people engaged in their learning environment (reading a newspaper or going to Sellafield). Regarding levels of knowledge, passively watching a video had a significant but very small effect. Changes in attitudes were also recorded, although these were only sustained over time for the Visitors' Centre. Concerning the other variables in question, changes in perceived risk, perceived benefit and preference were also recorded for the samples, although these results either could not be attributed to the different types of information, were not sustained or were no different to observations in the control groups. Some changes were recorded for aspects of control in the advert study although none were seen in the SVC study. No changes were found in trust for any of the different types of information. The main, consistent finding, was that sustained changes were recorded for knowledge and attitudes. These were both found to be linked to many of the variables under investigation, including risk

  13. EDRP public local inquiry, UKAEA/BNFL precognition on: Risk targets and EDRP design

    International Nuclear Information System (INIS)

    Brown, M.L.

    1986-06-01

    A full description is presented of the extent to which risk is controlled by the targets to be implemented in the proposed EDRP design, including a discussion of a particular accident sequence. Risk expressions and the usefulness of risk criteria are reviewed. Details are given of the accident consequence modelling as used by the UKAEA. Terrorist attack and sabotage are briefly discussed. (UK)

  14. The vertical distribution of radionuclides in a Ribble Estuary saltmarsh: transport and deposition of radionuclides

    International Nuclear Information System (INIS)

    Brown, J.E.; McDonald, P.; Parker, A.; Rae, J.E.

    1999-01-01

    Routine discharges of low-level liquid radioactive waste by British Nuclear Fuels plc (BNFL) at Sellafield and Springfields have resulted in enhanced levels of radionuclides in sediments of the Ribble Estuary, NW England, UK. Variations in radionuclide concentrations ( 137 Cs, 230 Th, and 239240 Pu) with depth in a mature saltmarsh core were analysed in order to investigate historical discharge trends and waste-dispersal mechanisms. Core samples from Longton/Hutton Marsh were analysed by gamma-spectrometry and α-spectrometry for radionuclides and by laser granulometry to establish grain-size variations with depth. Distinct subsurface maxima were present for 137 Cs and 239240 Pu with activities as high as 4500 Bq kg -1 for 137 Cs and 600 Bq kg -1 for 239240 Pu. Thorium-230 exhibited complex activity profiles with depth, specific activities ranging between 200 and 2400 Bq kg -1 . The vertical distributions of Sellafield-derived radionuclides ( 137 Cs and 239240 Pu) in mature saltmarsh deposits reflect the time-integrated discharge pattern from Sellafield, implying a transport mechanism that has involved the mixing of sediment labelled with radioactivity from recent discharges and sediment labelled from historical discharge events before deposition. A mechanism involving the transport of contaminated silt therefore seems to dominate. The vertical distribution of Springfields-derived 230 Th in the same areas reflects the annual gross-α discharge pattern from BNFL Springfields. In contrast to the Sellafield-derived radionuclides, a fairly rapid transport mechanism from source to sink is implied, with little or no time for mixing with radionuclides discharged years earlier. (Copyright (c) 1999 Elsevier Science B.V., Amsterdam. All rights reserved.)

  15. Alpha detection on moving surfaces

    International Nuclear Information System (INIS)

    MacArthur, D.; Orr, C.; Luff, C.

    1998-01-01

    Both environmental restoration (ER) and decontamination and decommissioning (D and D) require characterization of large surface areas (walls, floors, in situ soil, soil and rubble on a conveyor belt, etc.) for radioactive contamination. Many facilities which have processed alpha active material such as plutonium or uranium require effective and efficient characterization for alpha contamination. Traditional methods for alpha surface characterization are limited by the short range and poor penetration of alpha particles. These probes are only sensitive to contamination located directly under the probe. Furthermore, the probe must be held close to the surface to be monitored in order to avoid excessive losses in the ambient air. The combination of proximity and thin detector windows can easily cause instrument damage unless extreme care is taken. The long-range alpha detection (LRAD) system addresses these problems by detecting the ions generated by alpha particles interacting with ambient air rather than the alpha particle directly. Thus, detectors based on LRAD overcome the limitations due to alpha particle range (the ions can travel many meters as opposed to the several-centimeter alpha particle range) and penetrating ability (an LRAD-based detector has no window). Unfortunately, all LRAD-based detectors described previously are static devices, i.e., these detectors cannot be used over surfaces which are continuously moving. In this paper, the authors report on the first tests of two techniques (the electrostatic ion seal and the gridded electrostatic LRAD detector) which extend the capabilities of LRAD surface monitors to use over moving surfaces. This dynamic surface monitoring system was developed jointly by Los Alamos National Laboratory and at BNFL Instruments. All testing was performed at the BNFL Instruments facility in the UK

  16. Country nuclear fuel cycle profile: Netherlands

    International Nuclear Information System (INIS)

    2005-01-01

    In 2002, the Netherlands' only reactor, the 449 MW(e) PWR at Borssele, provided 3.6 TW·h of electricity, equivalent to 4% of domestic electricity output. Two successive governments ordered the Borssele nuclear power plant to shut down by December 2003, earlier than had originally been foreseen. However, the Government that came into office at the beginning of August 2002 has agreed to postpone closure of this plant, as it said 'taking into account the Kyoto obligations, it would not be sensible to close Borssele prematurely'. The new Cabinet will consult with the owner of the plant to seek an agreement on continuing its operation, taking into account its economic and technical lifetime. Uranium enrichment is carried out by Urenco Nederland B.V., which is located in Almelo. Urenco Nederland is owned by the multinational company Urenco Ltd, which is located in Marlow (UK) and which has three shareholders holding equal shares: Ultra Centrifuge Nederland (UCN) in the Netherlands, Uranit (Germany) and BNFL. The Government of the Netherlands owns 99% of the shares in UCN. The current capacity of Urenco Nederland is 1850 t SWU/a. However, in 1999 the company obtained a licence to expand its capacity to 2500 t SWU/a, for which a fifth enrichment plant has been built at the Almelo site. In early 2003 a new nuclear licence was issued to increase capacity to 2800 t SWU/a. Urenco uses advanced gas ultracentrifuge technology for the enrichment of uranium. Spent fuel is being reprocessed at the BNFL reprocessing facility in the UK and at the Cogema reprocessing facility in France

  17. Annual report on radioactive discharges and monitoring of the environment 1992. V. 1

    International Nuclear Information System (INIS)

    1993-01-01

    This Annual Report supplements the Company's Health and Safety Annual Report by providing more detailed information on radioactive discharges, monitoring of the environment and critical group doses. BNFL has published Annual Reports on Radioactive Discharges and Monitoring of the Environment, covering the period from 1977 to the present. For 1990 this report has been sub-divided into two complementary parts. Volume I includes annual data for each of the Company sites on radioactive discharges into the environment and the associated environmental monitoring programmes. Volume II reproduces the Certificates of Authorisation under which the Company operates and the statutory environmental monitoring programmes which relate to them. (author)

  18. Leaching studies of low-level waste as input to radiological assessment at the Drigg disposal site, Cumbria

    International Nuclear Information System (INIS)

    Poulton, J.; Rushbrook, P.E.

    1989-01-01

    Over the period of operation of the low-level waste disposal site at Drigg in Cumbria, several radiological assessments have been carried out. This paper discusses data requirements for such an assessment and in particular describes a project to measure the leaching behaviour of wastes. This project, jointly set up by the staff of BNFL and Environmental Safety Centre at Harwell, began in 1985. The objectives were to determine the processes operating within the waste disposal trenches at Drigg and conditions affecting them. The paper describes the installation and operation of the first of a series of lysimeters designed to simulate conditions in current trenches. (author)

  19. Remote handling developments for inspection and repair of highly active reprocessing plant

    International Nuclear Information System (INIS)

    Jones, E.L.

    1988-01-01

    Having the capability to carry out regular and comprehensive inspection of active plant can have benefits beyond the need to satisfy the possible requirements of National Regulatory Authorities. Intermediate inspection can provide qualitative data on the state of the plant, whilst regular inspection can provide quantitative data on which to base predictive judgments. Information of this sort can allow confidence in predicting the actual life of the plant as opposed to the theoretical. The following paper addresses the areas of plant inspection and repair by reference to specific projects either already completed or at an advanced stage of development at BNFL's Sellafield reprocessing plant. (author)

  20. Long-reach manipulators for decommissioning

    International Nuclear Information System (INIS)

    Webster, D.A.; Challinor, S.F.

    1993-01-01

    A survey of redundant facilities at Sellafield has identified that in many cases the conventional means of deploying remote handling equipment are not appropriate and that novel means must be employed. However, decommissioning is not a value adding activity and so expensive one off designs must be avoided. The paper will describe BNFL's approach to the synthesis from proprietary parts of a manipulator which can lift 3 te at a horizontal reach of over 5 metres and yet can still perform the dextrous manipulation necessary to remove small items. It will also cover the development of the manipulator control systems and the adaption of commercial handtools to be manipulator friendly. (author)

  1. Decommissioning in British Nuclear Fuels plc

    International Nuclear Information System (INIS)

    Colquhoun, A.

    1988-01-01

    Decommissioning projects at the BNFL Sellafield site have been selected taking the following into account; the need to gain experience in preparation for the decommissioning of the Magnox reactors and for the post Magnox stage; the need to develop larger scale projects; the need to be cost effective and to foster long term safety. The balance between prompt or delayed decommissioning has to consider operator dose uptake and radioactive waste management. The ten year plan for decommissioning at Sellafield is described briefly. Currently decommissioning is of the fuel pond and decanning plant, the Windscale Pile Chimneys, the coprecipitation plant and the uranium recovery plant. (author)

  2. Annual report on radioactive discharges and monitoring of the environment 1990. V. 1

    International Nuclear Information System (INIS)

    1991-01-01

    This Annual Report supplements the Company's Health and Safety Annual Report by providing more detailed information on radioactive discharges, monitoring of the environment and critical group doses. BNFL has published Annual Reports on Radioactive Discharges and Monitoring of the Environment, covering the period from 1977 to the present. For 1990 this report has been sub-divided into two complementary parts. Volume I includes annual data for each of the Company sites on radioactive discharges into the environment and the associated environmental monitoring programmes. Volume II reproduces the Certificates of Authorisation under which the Company operates and the statutory environmental monitoring programmes which relate to them. (author)

  3. The decommissioning of the Latina nuclear power plant

    International Nuclear Information System (INIS)

    Bolla, G.; Macci, E.; Craik, J.F.D.; Walkden, P.

    2001-01-01

    Over the past year, a revised decommissioning programme, drawing upon the combined experience of the two companies, has been developed for the Latina NPP. This has been achieved despite a very demanding time-scale. Theoretical and practical experiences from both Sogin and BNFL's operations in North America and Europe have been used to quantify liabilities and progress the planning process to the point where Sogin have been able to define their funding requirements for Latina with their stakeholders. The project has demonstrated, based on real experience and data, that the Latina NPP can be decommissioned economically for a known cost within the timescale set by the Italian Government. (author)

  4. Annual report on radioactive discharges and monitoring of the environment 1990. V. 2

    International Nuclear Information System (INIS)

    1991-01-01

    This Annual Report supplements the Company's Health and Safety Annual Report by providing more detailed information on radioactive discharges, monitoring of the environment and critical group doses. BNFL has published Annual Reports on Radioactive Discharges and Monitoring of the Environment, covering the period from 1977 to the present. For 1990 this report has been sub-divided into two complementary parts. Volume I includes annual data for each of the Company sites on radioactive discharges into the environment and the associated environmental monitoring programmes. Volume II reproduces the Certificates of Authorisation under which the Company operates and the statutory environmental monitoring programmes which relate to them. (author)

  5. Irradiated nuclear fuel transport from Japan to Europe

    International Nuclear Information System (INIS)

    Kavanagh, M.T.; Shimoyama, S.

    1976-01-01

    Irradiated nuclear fuel has been transported from Japan to Europe since 1969, although U.K. experience goes back almost two decades. Both magnox and oxide fuel have been transported, and the technical requirements associated with each type of fuel are outlined. The specialized ships used by British Nuclear Fuels Limited (BNFL) for this transport are described, as well as the ships being developed for future use in the Japan trade. The ship requirements are related to the regulatory position both in the United Kingdom and internationally, and the Japanese regulatory requirements are described. Finally, specific operational experience of a Japanese reactor operator is described

  6. Being open at Sellafield

    International Nuclear Information System (INIS)

    Logan, Philippa.

    1986-01-01

    The reprocessing of spent fuel at Sellafield is explained briefly stage by stage. The origin of the spent fuels which are reprocessed there is given and the procedures for the different types of spent fuel are explained. The new fuel handling plant is described. Also the site ion-exchange effluent plant (SIXEP), which is designed to reduce the amount of radioactivity in water discharged into the Irish Sea, is mentioned. The work at BNFL on vitrification and the Thermal Oxide Reprocessing Plant (THORP) are also mentioned. The public are able to look round the exhibition centre and see for themselves the plant and operations as described in this article. (U.K.)

  7. Annual report on radioactive discharges and monitoring of the environment 1982

    International Nuclear Information System (INIS)

    1983-08-01

    A report is given on the liquid, airborne and solid radioactive discharges through authorised outlets and on environmental monitoring for all of BNFL's Works and sites for 1982, i.e. Sellafield Site and the Drigg Storage and Disposal Site; Chapelcross Works; Springfields Works and the Ulnes Walton Disposal Site; and Capenhurst Works. The report includes assessment of radiation doses to representative members of the most highly exposed group of the general population for the most important environmental pathways. At no time during 1982 have discharges and disposals of radioactive wastes through authorised outlets at any of the above Works exceeded those laid down in any of the Authorisations. (U.K.)

  8. 'Swapping wastes' planned by nuclear power plant operators in order to exert an influence on the government's radwaste repository project Konrad

    International Nuclear Information System (INIS)

    Harries, K.; Stroetmann, C.

    1992-01-01

    An 'exchange of waste', which would involve taking back high-level radioactive, heat-generating waste in place of low-level radioactive waste from reprocessing, whereby the amount of high-level radioactive waste would be smaller, corresponding in the degree of radioactivity to that of the low-level radioactive waste, is not provided for in the reprocessing contracts with BNFL and is also not approved by the federal government. There is still an urgent need for waste disposal facilities for radioactive waste with negligible generation of heat. Thus the waste disposal project Konrad is not superfluous, but rather should be accelerated quickly. (orig./HSCH) [de

  9. The commercial application of near real time materials accountancy

    International Nuclear Information System (INIS)

    Chater, S.P.; Jones, B.J.; Jones, R.F.; Westwood, L.N.; Wharrier, J.A.

    2001-01-01

    Full text: Near Real Time Materials Accountancy (NRTMA) is the leading edge technical solution employed by BNFL for in-process verification and timely detection of anomalies. It facilitates Safeguards inspection without intrusion and safeguards interim assurance without a monthly plant shut down. BNFL has been committed to the development of NRTMA for commercial plutonium plants. This multimedia poster presentation describes the features of Thorp and SMP relevant to the application of NRTMA, and then the statistical engine of NRTMA, which has many features in common across the two systems. This final point renders BNFL's implementation of NRTMA eligible for application to other nuclear and non-nuclear installations. NRTMA is operational in the Thermal Oxide Reprocessing Plant (Thorp). NRTMA supports fulfilment of the monthly timeliness component of the safeguards approach so that Thorp can remain operational between annual Physical Inventory Takings (PITs). The In-Process Inventory (IPI) is determined by for each vessel, or group of vessels, based on determination of weight and assay (or volume and concentration) or process models. Data trending enhances the quality of important sources of data. Plant status rules are used to determine times when it is appropriate to determine the IPI. The number of IPIs is currently some tens per annual campaign (PIT to PIT), although the NRTMA System can accommodate more. NRTMA is an intrinsic element in the safeguards and nuclear materials control and accountancy arrangements for the Sellafield MOX Plant (SMP). This fulfils the timeliness component of the safeguards approach and does not require monthly clean out or run down for verification. The SMP is a batch process. In a plant location, there is a 'Window of Opportunity' for determining that component of the inventory while it is stationary. The IPI can be determined when the 'Windows of Opportunity' for the entire Works Accountancy Area align. There are potentially many

  10. EDRP public local inquiry, UKAEA/BNFL precognition on: EDRP waste management (excluding gaseous emissions)

    International Nuclear Information System (INIS)

    Kenny, D.A.

    1986-01-01

    The management of radioactive wastes, produced as by-products of the operation of the proposed EDRP, is considered. The arisings of the various types of waste are discussed and an outline is presented of the research and development work being carried out in support of the management of the radioactive wastes. (U.K.)

  11. Windscale Report: a nuclear apologia

    International Nuclear Information System (INIS)

    Patterson, W.C.

    1978-01-01

    Government representatives have pointed repeatedly with pride to Britain's longest nuclear planning inquiry, The Windscale Inquiry, as a model of open examination of a sensitive nuclear proposal. The official Report of the Windscale Inquiry, published in March 1978, bears little relationship to the proceedings of the Inquiry, according to the author. Instead, the Report is a heavy-handed nuclear apologia, he says, so clumsily one-sided as to provoke unease even among many Britons previously unmoved by the issue which gave rise to the inquiry. Windscale, built following WW II to produce plutonium for Britain's nuclear weapons, is now operated by British Nuclear Fuels Ltd. In 1973, BNFL began to plan construction of a new full-scale oxide-fuel reprocessing plant. Protests delayed construction until the inquiry was planned and the inquiry team was formulated in March 1977. When the Inquiry ended, the inspector closeted himself to write the Report. The Report recommended that the oxide fuel reprocessing plant be built immediately. BNFL had asserted that the proposed thermal oxide reprocessing plant, THORP, was necessary for the management of spent fuel from British and other nuclear plants; that it was desirable for ''energy conservation,'' by recovering uranium and plutonium for re-use; that radioactive emissions within and outside the plant would pose no hazard; and that the servicing of foreign customers would not increase the risk of proliferation of nuclear weapons, but would rather help to persuade other countries not to reprocess their own fuel. The inspector agreed without qualification and with emphasis. In doing so he made no attempt even to describe the detailed evidence on either side, or to discuss the cases advanced by objectors. The author discusses the principal conclusions of the report and cites its futility

  12. Office of River Protection (ORP) Monthly Performance Report for July 2000

    International Nuclear Information System (INIS)

    WAGNILD, K.J.

    2000-01-01

    River Protection Project (RPP) performance for the month of July 2000 was very good. The most significant accomplishments that occurred during the month include the following: The Interim Stabilization Project pumped approximately 30,000 gallons from four tanks. Project-to-date (since June 1998) volume pumped is approximately 808,000 gallons. Five tanks have been interim stabilized this fiscal year, and tanks 241-S-106,241-U-103, and 241-U-105 are being evaluated to determine if the stabilization criteria have been met. Out of the 149 single-shell tanks (SSTs), 124 tanks have been stabilized. Pumping this waste from the single-shell tanks to more secure double-shell tanks (DSTs) supports stabilization of the waste tanks and mitigates leakage to the environment. The Interim Stabilization Project is planned to complete by September 2004. Waste Characterization obtained one grab sample in the month of July 2000. A total of 14 core samples, 12 grab samples, and 6 vapor samples have been taken fiscal year-to-date (FYTD) in support of three key FY 2000 sampling milestones. The Waste Treatment Plant Design and Operation organizations have been developed and staffed, including transitioning BNFL Inc./Bechtel National Inc. employees to CHG. Since the termination of the BNFL contract, CHG has temporarily assumed the work scope for design and operation of the Waste Treatment Plant. A new waste treatment facility will be built at the Hanford Site in which highly radioactive waste from the tanks will be turned into glass and permanently stored. Approval of the Notice of Construction (NOC) for the AN Farm tank retrieval system was received from the U.S. Department of Energy (DOE) and the Environmental Protection Agency on July 21,2000. This is a significant step forward for Project W-211, ''Initial Tank Retrieval Systems'' in preparing waste for delivery to the Waste Treatment Plant

  13. Testing of LWR fuel rods to support criticality safety analysis of transport accident conditions

    Energy Technology Data Exchange (ETDEWEB)

    Purcell, P.C. [BNFL International Transport, Spent Fuel Services (United Kingdom); Dallongeville, M. [COGEMA Logistics (AREVA Group) (France)

    2004-07-01

    For the transport of low enriched materials, criticality safety may be demonstrated by applying pessimistic modelling assumptions that bound any realistic case. Where Light Water Reactor (LWR) fuel is being transported, enrichment levels are usually too high to permit this approach and more realistic data is needed. This requires a method by which the response of LWR fuel under impact accident conditions can be approximated or bounded. In 2000, BNFL and COGEMA LOGISTICS jointly commenced the Fuel Integrity Project (FIP) whose objective was to develop such methods. COGEMA LOGISTICS were well advanced with a method for determining the impact response of unirradiated fuel, but required further test data before acceptance by the Transport Regulators. The joint project team extensively discussed the required inputs to the FIP, from which it was agreed that BNFL would organise new tests on both unirradiated and irradiated fuel samples and COGEMA LOGISTICS would take major responsibility for evaluating the test results. Tests on unirradiated fuel rod samples involved both dynamic and quasi-static loading on fuel samples. PWR fuel rods loaded with uranium pellets were dropped vertically from 9m onto a rigid target and this was repeated on BWR fuel rods, similar tests on empty fuel rods were also conducted. Quasi-static tests were conducted on 530 mm long PWR and BWR fuel specimens under axial loading. Tests on irradiated fuel samples were conducted on high burn-up fuel rods of both PWR and BWR types. These were believed original to the FIP project and involved applying bending loads to simply supported pressurised rod specimens. In one test the fuel rod was heated to nearly 500oC during loading, all specimens were subject to axial impact before testing. Considerable experience of fuel rod testing and new data was gained from this test programme.

  14. Feed and product for AVLIS

    International Nuclear Information System (INIS)

    Williams, T.

    1991-01-01

    Today, fuel cycle organizations around the world, including British Nuclear Fuels, Ltd. (BNFL) are undertaking the development of a new and demanding enrichment technology, customarily referred to by its American Acronym AVLIS (atomic vapor laser isotope separation). Successful commercialization of the technology will threaten established fuel cycle activities and is likely to send shock waves throughout the world industry. The stakes are high for all involved in the civil nuclear industry: do the potential rewards match up? US Department of Energy (US DOE) is regarded as the organization most committed to the early commercialization of AVLIS technology and is aiming to deploy an initial commercial plant within 6 years. However, the timescale is of course subject to a satisfactory technical progress and, no less importantly, continued funding of the necessary development and construction activities. Coupled with the changes that will be needed at the enrichment plant interfaces, the implications for feed supply and product usage, it can be seen that the 1997 target deployment date is an ambitious one. Other organizations are also developing atomic laser enrichment routes, but for the post-2000 timeframe. US DOE's desire to push ahead with early AVLIS deployment has to be seen in this global context. The different feed and product material interface requirements could generate resistance to the use of AVLIS by customers and other fuel cycle companies. The BNFL/URENCO atomic vapor laser enrichment development program is able to profit from USDOE's experience by ensuring very early that it encompasses all fuel cycle aspects. A process is being developed that is optimized from yellowcake to ceramic UO 2 , rather than just the difficult enrichment process. This is far more likely, if it becomes economically competitive, to produce a good match with customer requirements and so reduce the commercial risks of such a decision

  15. Testing of LWR fuel rods to support criticality safety analysis of transport accident conditions

    International Nuclear Information System (INIS)

    Purcell, P.C.; Dallongeville, M.

    2004-01-01

    For the transport of low enriched materials, criticality safety may be demonstrated by applying pessimistic modelling assumptions that bound any realistic case. Where Light Water Reactor (LWR) fuel is being transported, enrichment levels are usually too high to permit this approach and more realistic data is needed. This requires a method by which the response of LWR fuel under impact accident conditions can be approximated or bounded. In 2000, BNFL and COGEMA LOGISTICS jointly commenced the Fuel Integrity Project (FIP) whose objective was to develop such methods. COGEMA LOGISTICS were well advanced with a method for determining the impact response of unirradiated fuel, but required further test data before acceptance by the Transport Regulators. The joint project team extensively discussed the required inputs to the FIP, from which it was agreed that BNFL would organise new tests on both unirradiated and irradiated fuel samples and COGEMA LOGISTICS would take major responsibility for evaluating the test results. Tests on unirradiated fuel rod samples involved both dynamic and quasi-static loading on fuel samples. PWR fuel rods loaded with uranium pellets were dropped vertically from 9m onto a rigid target and this was repeated on BWR fuel rods, similar tests on empty fuel rods were also conducted. Quasi-static tests were conducted on 530 mm long PWR and BWR fuel specimens under axial loading. Tests on irradiated fuel samples were conducted on high burn-up fuel rods of both PWR and BWR types. These were believed original to the FIP project and involved applying bending loads to simply supported pressurised rod specimens. In one test the fuel rod was heated to nearly 500oC during loading, all specimens were subject to axial impact before testing. Considerable experience of fuel rod testing and new data was gained from this test programme

  16. Decommissioning of a mixed oxide fuel fabrication facility

    International Nuclear Information System (INIS)

    Buck, S.; Colquhoun, A.

    1990-01-01

    Decommissioning of the coprecipitation plant, which made plutonium/uranium oxide fuel, is a lead project in the BNFL Sellafield decommissioning programme. The overall programme has the objectives of gaining data and experience in a wide range of decommissioning operations and hence in this specific project to pilot the decommissioning of plant heavily contaminated with plutonium and other actinides. Consequently the operations have been used to test improvements in temporary containment, contamination control and decontamination methods and also to develop in situ plutonium assay, plutonium recovery and size-reduction methods. Finally the project is also yielding data on manpower requirements, personnel radiation uptake and waste arisings to help in the planning of future decommissioning projects

  17. Successful public relations for a better public acceptance - a case study on Sellafield

    International Nuclear Information System (INIS)

    Duncan, C.; Prestwood, J.

    1998-01-01

    The Sellafield story is not unique but it can be used as one example of what can be achieved in a community close to a nuclear site. Over the past 12 years BNFL staff at Sellafield have worked diligently to win public acceptance in the local community around Sellafield. It has been an excellent example of teamwork, involving the workforce and the local community. It has taken a great deal of effort and finance and painstaking attention to even the most trivial issues to gain the publics' trust. Today, Sellafield and its activities underpin the economy of West Cumbria. The site employs just under 7000 people directly with a further 1500 in contracting roles

  18. Radioactivity in surface and coastal waters of the British Isles, 1982

    International Nuclear Information System (INIS)

    Hunt, G.J.

    1984-01-01

    The subject is covered in sections, entitled: introduction: discharges of [liquid, solid] radioactive waste; methods of analysis and of presentation and interpretation of results; British Nuclear Fuels plc (BNFL) Sellafield, Cumbria (the fish and shellfish consumption pathway; external exposure; porphyra/ laverbread pathway; other surveys); Springfields, Lancashire; Capenhurst, Cheshire; Chapelcross, Dumfriesshire); United Kingdom Atomic Energy Authority (Atomic Energy Establishment, Winfrith, Dorset; Dounreay Nuclear Power Development Establish-ment, Caithness); nuclear power stations operated by the electricity boards (Berkeley, Gloucestershire and Oldbury, Avon; Bradwell, Essex; Dungeness, Kent; Hartlepool, Cleveland; Heysham, Lancashire; Hinkley Point, Somerset; Hunterston, Ayrshire; Sizewell, Suffolk; Trawsfynydd, Gwynedd; Wylfa, Gwynedd; naval establishments; Amersham International plc; Channel Islands monitoring; summary and conclusions. (U.K.)

  19. Decommissioning of the ICI TRIGA Mark I reactor

    International Nuclear Information System (INIS)

    Parry, D.R.; England, M.R.; Ward, A.; Green, D.

    2000-01-01

    This paper considers the fuel removal, transportation and subsequent decommissioning of the ICI TRIGA Mark I Reactor at Billingham, UK. BNFL Waste Management and Decommissioning carried out this work on behalf of ICI. The decommissioning methodology was considered in the four stages to be described, namely Preparatory Works, Reactor Defueling, Intermediate Level Waste Removal and Low Level Waste Removal. This paper describes the principal methodologies involved in the defueling of the reactor and subsequent decommissioning operations, highlighting in particular the design and safety case methodologies used in order to achieve a solution which was completed without incident or accident and resulted in a cumulative radiation dose to personnel of only 1.57 mSv. (author)

  20. Roll up, roll up and see a Sellafield exhibition

    International Nuclear Information System (INIS)

    Matthews, Virginia.

    1986-01-01

    Since July 1986 a commercial advertising campaign has been encouraging people to visit the BNFL plant at Sellafield to find out for themselves what goes on there. As a result it is now a flourishing tourist attraction. Casual visitors can visit the Ehibition Centre and go on a bus tour of the site lasting an hour. Pre-booked visitors can go on a five hour tour which looks at the processes in detail. The object is to open up the site so that people can be better informed and can make up their minds about the merits or otherwise of Sellafield, and nuclear power in general, with a knowledge of the facts. (UK)

  1. Windscale: a case history in the political art of muddling through

    International Nuclear Information System (INIS)

    Wynne, B.

    1980-01-01

    This chapter concentrates mainly upon those factors which preceded and eventually led to the Windscale Inquiry (into the BNFL proposal to construct a plant to reprocess spent nuclear fuel from reactors using oxide fuels). This will help to illustrate some of the many covert themes which permeated the Inquiry as an exercise in conflict-management, and hopefully should assist in the understanding of the limitations of this form of decision-making process. The chapter will conclude with a comment upon the role of the Inquiry in the wider political context of the British energy 'debate' and upon the likely implications of the Inquiry for future decision-making ventures on similar technological developments. (author)

  2. KWL annual report 1983

    International Nuclear Information System (INIS)

    1983-01-01

    The application for decommissioning comprises the shutdown of the plant, methods for safe shielding of the nuclear section, and a modification in the utilization of the conventional plant sections. The planning documents are worked out by the Nuklear-Ingenieur-Service GmbH, Hanau. The activities for the Euratom research programmes have been completed by KWL. The final report on the determination of the activation of the biological shield is available. The processing of the enriched uranium originating from unirradiated FE as well as the conversion to UF 6 has been terminated. All spent fuel elements have been transported to BNFL. The joint works management of KWL and the VEW-power plant Emsland has been rearranged. (DG) [de

  3. Encapsulation - how it will be achieved

    International Nuclear Information System (INIS)

    Barlow, P.

    1990-01-01

    The work of the new Encapsulation Plant at British Nuclear Fuel Limited's (BNFL) Sellafield site is described in this article. Intermediate-level radioactive materials are encapsulated in a cement matrix in 500 litre stainless steel drums suitable for storage, transport and disposal. The drums will be stored in an above-ground air-cooled store until UK Nirex Limited have built the planned underground disposal facility. The concept of product specification is explored as it applies to the four stages of nuclear waste management, namely, processing, storage, transport and disposal. By following this approach the encapsulation plant will work within government regulations and the public concerns over safety and environmental issues can be met. U.K

  4. White paper updating conclusions of 1998 ILAW performance assessment

    International Nuclear Information System (INIS)

    MANN, F.M.

    2000-01-01

    The purpose of this document is to provide a comparison of the estimated immobilized low-activity waste (LAW) disposal system performance against established performance objectives using the beat estimates for parameters and models to describe the system. The principal advances in knowledge since the last performance assessment (known as the 1998 ILAW PA [Mann 1998a]) have been in site specific information and data on the waste form performance for BNFL, Inc. relevant glass formulations. The white paper also estimates the maximum release rates for technetium and other key radionuclides and chemicals from the waste form. Finally, this white paper provides limited information on the impact of changes in waste form loading

  5. White paper updating conclusions of 1998 ILAW performance assessment

    Energy Technology Data Exchange (ETDEWEB)

    MANN, F.M.

    2000-05-11

    The purpose of this document is to provide a comparison of the estimated immobilized low-activity waste (LAW) disposal system performance against established performance objectives using the beat estimates for parameters and models to describe the system. The principal advances in knowledge since the last performance assessment (known as the 1998 ILAW PA [Mann 1998a]) have been in site specific information and data on the waste form performance for BNFL, Inc. relevant glass formulations. The white paper also estimates the maximum release rates for technetium and other key radionuclides and chemicals from the waste form. Finally, this white paper provides limited information on the impact of changes in waste form loading.

  6. A study of fish and shellfish consumers near Sellafield: assessment of the critical groups including consideration of children

    International Nuclear Information System (INIS)

    Leonard, D.R.P.; Hunt, G.J.

    1985-01-01

    A survey of people's consumption rates in 1981 and 1982, of fish and shellfish caught near the British Nuclear Fuels plc (BNFL) Sellafield site is described. Particular emphasis has been given to mollusc eaters and consumption rates of children because of the potentially higher radiation doses they may receive. Appropriate critical groups have been selected for dose assessment purposes using principles recommended by the International Commission on Radiological Protection (ICRP). Methods for consideration of children in critical groups are suggested and a comparison of these methods using the present data shows similar results. Combination of seafood consumption pathways is also considered, and it is shown that a simple additive approach is not excessively conservative. (author)

  7. Environmental monitoring for radioactivity in Scotland: 1981 to 1985

    Energy Technology Data Exchange (ETDEWEB)

    Anon.

    1987-01-01

    A bulletin, prepared by Her Majesty's Industrial Pollution Inspectorate (HMIPI) of the Scottish Development Department (SDD), contains a summary of the environmental monitoring for radioactivity carried out in Scotland as part of the statutory procedure for ensuring the safety of radioactive waste disposals from nuclear facilities. The monitoring results for discharges to both the atmosphere and the sea over the period 1981 to 1985 are presented for BNFL's Chapelcross and Sellafield Works, UKAEA Dounreay Nuclear Power Development Establishment, SSEB Hunterston Power Station and MOD Naval Installations. It is concluded that public radiation exposure in Scotland from environmental radioactivity arising from radioactive waste disposal has been well within the internationally recommended limits.

  8. Expanding nuclear horizons

    International Nuclear Information System (INIS)

    Anon.

    1991-01-01

    British Nuclear Fuels' new thermal oxide reprocessing plant (THORP) at Sellafield, in the North West of England, is a testimony to the company's intelligent use of computers and to the power of shared information in the design and construction of plant. BNFL Engineering (BE) has succeeded in creating an impressive marriage between off-the-shelf materials control and CAD systems and its own in-house information systems. Now the company is embarking on a pioneering marketing push of its own know-how gained by a team that has a unique range of skills - from design and construction of plant, through operation to final de-commissioning. This article looks particularly at computer systems and software. (author)

  9. Successful public relations for a better public acceptance - a case study on Sellafield

    Energy Technology Data Exchange (ETDEWEB)

    Duncan, C. [British Nuclear Fuels plc, Risley (United Kingdom); Prestwood, J. [British Nuclear Fuels plc, Sellafield (United Kingdom)

    1998-12-31

    The Sellafield story is not unique but it can be used as one example of what can be achieved in a community close to a nuclear site. Over the past 12 years BNFL staff at Sellafield have worked diligently to win public acceptance in the local community around Sellafield. It has been an excellent example of teamwork, involving the workforce and the local community. It has taken a great deal of effort and finance and painstaking attention to even the most trivial issues to gain the publics` trust. Today, Sellafield and its activities underpin the economy of West Cumbria. The site employs just under 7000 people directly with a further 1500 in contracting roles.

  10. EDRP public local inquiry, UKAEA/BNFL precognition on: the transport of irradiated fuel by rail

    International Nuclear Information System (INIS)

    Singleton, Leslie

    1986-02-01

    The experience in handling of irradiated fuel flasks by the British Railways Board is outlined. The steps taken to ensure the effective and safe transport of irradiated fuel and nuclear waste by rail are identified. It is concluded that the proposed rail transport link to the EDRP at Dounreay should prove practicable. (UK)

  11. Artificial radionuclides in an intertidal sediment from northwest England

    International Nuclear Information System (INIS)

    Morris, K.; Keith-Roach, M.J.; Butterworth, J.C.; Livens, L.K.; Day, J.P.; Hursthouse, A.S.; Fifield, L.K.; Bardgett, R.D.

    1998-01-01

    An intertidal sediment core has been analysed for the principal transuranium elements present in the BNFL Sellafield radioactive waste discharges (Np, Pu, Am) and the high yield fission products 99 Tc and 137 Cs. Interstitial water samples were collected using porous cup samplers and early results from these analyses show that there is a pronounced seasonality in the pattern of dissolved Pu, which apparently relates to changes in dissolved Fe and Mn. More recent work has concentrated on the characterization of changes in the sediment microbial community and on the development of analytical methods for the analysis of dissolved Np, apparently the most readily mobilized of the transuranic elements, which is present at concentrations of the order of 10 8 atoms/litre

  12. The transport implications of regional policies for the disposal of intermediate level radioactive wastes

    International Nuclear Information System (INIS)

    James, I.A.

    1985-09-01

    This report aims to evaluate transport parameters and logistics associated with the disposal of intermediate-level radioactive wastes, as generated by CEGB, SSEB, UKAEA and BNFL. The assumed power scenario is DoE Scheme 3, which approximates to a moderate power generation scenario, with a 15 GWe PWR programme commissioned between 1991 and 2010, existing Magnox and AGR stations are assumed to have a 30 year lifespan. Three transport options are again assumed, namely; road, rail and a hybrid system, as is consistent with previous studies. These three options will be used in investigating regional policies of disposal, initially at the national level and then progressively disaggregating to a system of three regional depositories serving their respective catchment areas. (author)

  13. Near real time materials accountancy development programme for Thorp

    International Nuclear Information System (INIS)

    Jones, B.J.

    1991-01-01

    BNFL is currently designing and installing a fully automated system of data capture, storage and processing for its Thermal Oxide Reprocessing Plant (THORP) at Sellafield. A prototype Near Real Time Materials Accountancy (NRTMA) system has been used to demonstrate the advantages of this method of materials control to the future plant operators and their feedback continues to be incorporated in the development of user interfaces. NRTMA has been included in the User Requirements Specification for Chemical Plant Information Computer, the top-tier computer which is being provided to archive, retrieve and analyse plant data. The paper describes a development programme of performance and quality related improvements to the prototype NRTMA system. Furthermore, advanced diagnostic systems are described which will help the operator in the resolution of anomalies

  14. Corrupt to the core

    International Nuclear Information System (INIS)

    Lowry, D.

    1988-01-01

    Many countries do not have the facilities necessary to process their nuclear waste. They have to export it to another country with suitable facilities. Some countries in Europe both export their own waste and import other peoples. This situation is described with details of facilities available and current practices of who sends what where. The problem of nuclear waste processing and disposal has led to corruption and widespread malpractice, in particular in West Germany and Belgium. Although not involved with these scandals Britain will receive large amounts of spent nuclear fuel once the THORP (Thermal Oxide Reprocessing Plant) is ready at BNFL's site at Sellafield. Britain will then have to deal with companies and countries whose record on the transportation of nuclear waste is bad. (U.K.)

  15. Decommissioning of the gaseous diffusion plant at BNF plc Capenhurst in the UK

    International Nuclear Information System (INIS)

    Clements, D.W.; Cross, J.R.

    1993-01-01

    Since 1982, a gaseous diffusion plant located at the British Nuclear Fuels plc (BNFL) site at Capenhurst in the United Kingdom, has been undergoing decontamination, decommissioning, and dismantling. By March 1994, the decontamination and decommissioning activities will be complete with 99% of the materials used to construct the plant recycled to the environment as clean material. This paper describes the history of the decontamination, decommissioning, dismantling, and disposal program. Reference is made to the scale of the project and to the special techniques developed, particularly in the areas of size reduction, decontamination, and protection of personnel and the environment. The quantities of material involved that require decontamination and release levels for recycling materials in the U.K. metals market are discussed

  16. UK-Russian collaboration high level waste immobilization studies

    International Nuclear Information System (INIS)

    Anderson, E.; Burakov, B.; Galkin, B.; Starchenko, V.; Vasiliev, V.; Shulyak, N.; Homes, R.G.G.; Weaver, W.; Goddard, D.; Clegg, R.; Richardson, S.

    1995-01-01

    Recent social changes in Russia have opened up many opportunities for business collaboration. To build on this, in 1992 British Nuclear Fuels Limited (BNFL) concluded and signed an agreement with the Russian ministry MINATOM to collaborate on a wide range of topics relevant to the international nuclear industry. These covered the such subjects as developing national regulatory frameworks, sharing operational experiences and practices, and establishing collaborative R and D programmes. One outcome of the agreement with MINATOM has been the setting up of a number of collaborative R and D projects with the V.G. Kholpin Radium Institute in St. Petersburg. This paper presents the results from one of these joint programmes, and describes the mutual benefits that can be obtained from such collaborative work. (authors)

  17. Introducing autonomy to robotic manipulators in the nuclear industry

    International Nuclear Information System (INIS)

    Boddy, C.L.; Webster, A.W.

    1991-01-01

    The National Advanced Robotics Research Centre was set up in 1988 to provide a forum for the development and transfer to industry of the technology of Advanced Robotics. In the area of robot manipulators, research has been carried out into increasing the low-level autonomy of such devices e.g. reactive collision avoidance, gross base disturbance rejection. This groundwork has proven the feasibility of using advanced control concepts in robotic manipulators, and, indeed, indicated new areas of robot kinematic design which can now be successfully exploited. Within the newly defined BNFL Integrated Robotics Programme a number of joint projects have been defined to demonstrate this technology in realistic environments, including the use of advanced interactive computer simulation and kinematically redundant manipulators. (author)

  18. The MOX Demonstration Facility - the stepping stone to commercial MOX production

    International Nuclear Information System (INIS)

    Macdonald, A.G.

    1994-01-01

    The paper provides an insight into MOX fuel and the economic benefits of its use in pressurized water reactors (PWRs). BNFL and AEA are collaborating in the design, construction and operation of a thermal MOX Demonstration Facility (MDF) on the AEA Windscale site in Cumbria. The process flowsheet and equipment employed in MDF are discussed and the special precautions required to handle plutonium bearing materials are highlighted. The process flowsheet includes the short binderless route which has been specially developed for use in MDF and results in fuel pellets with an homogeneous structure. MDF is the forerunner to the design and construction of a larger scale Sellafield MOX Plant and hence is the stepping-stone to commercial MOX production. (author)

  19. Annual report on radioactive discharges and monitoring of the environment 1992. V. 1

    International Nuclear Information System (INIS)

    1993-01-01

    This Annual Report supplements and updates the Company's Environment Annual Report by providing more detailed information on radioactive discharges, monitoring of the environment and critical group doses. BNFL has published Annual Reports on Radioactive Discharges and Monitoring of the Environment since 1977. This year the report is again sub-divided into two complementary volumes. Volume I consists of site papers, one for each of the Company's sites and includes annual data on radioactive discharges into the environment and the associated environmental monitoring programmes. Critical group doses for each site are presented in summary tables at the beginning of each Site paper. Volume II reproduces the Certificates of Authorisation regulating the Company's discharges and the statutory environmental monitoring programmes which relate to them. (Author)

  20. IFPE/HBEP REV.1, Battelle's High Burn-Up Effects Programme for Fuel Performance

    International Nuclear Information System (INIS)

    Turnbull, J.A.

    2002-01-01

    Description: It contains data from phase 2 and 3 on fabrication, dimensions, fuel and cladding properties and composition, reactor conditions and Post Irradiation Examination (PIE) data of the High Burn-up Effects Programme (HBEP) carried out at the Battelle North-west Laboratories. Each data set contains a full irradiation history with clad temperature and local power listed for each rod at 5, 10 or 12 axial zones as a function of cumulative time to the end of the given time interval over which the power has been constant. Data is provided for 45 rods from phase 2 and 36 rods from phase 3. The different rods have been manufactured by: ASEA/TVO, BN, BNFL, FBFC, FRA/CEA, GE, KWU/CE, WEC

  1. The long term storage of advanced gas-cooled reactor (AGR) fuel

    International Nuclear Information System (INIS)

    Standring, P.N.

    1999-01-01

    The approach being taken by BNFL in managing the AGR lifetime spent fuel arisings from British Energy reactors is given. Interim storage for up to 80 years is envisaged for fuel delivered beyond the life of the Thorp reprocessing plant. Adopting a policy of using existing facilities, to comply with the principles of waste minimisation, has defined the development requirements to demonstrate that this approach can be undertaken safely and business issues can be addressed. The major safety issues are the long term integrity of both the fuel being stored and structure it is being stored in. Business related issues reflect long term interactions with the rest of the Sellafield site and storage optimisation. Examples of the development programme in each of these areas is given. (author)

  2. Sizewell B cycle 5 core design with Framatome ANP's CASCADE-3D and British Energy's PANTHER

    International Nuclear Information System (INIS)

    Attale, F.; Koegl, J.; Knight, M.; Bryce, P.

    2001-01-01

    Sizewell B Cycle 5 is the first cycle, after 4 cycles with BNFL fuel, with a reload consisting of Framatome ANP HTP (high thermal performance) fuel assemblies. The impact of this fuel vendor change on the Nuclear Design area is that, according to British energy's (BE) practice, the Framatome ANP's nuclear design code system CASCADE-3D is used for the majority of the cycle specific safety case calculations. However, other parts of the safety submission (e.g. 3D transient analyses) are made by using the BE code PANTHER. Before using in parallel two different code systems for reload core licensing extensive comparisons of applied methodologies and obtained results were required to ensure an acceptable level of agreement. (orig.)

  3. Sizewell B cycle 5 core design with Framatome ANP's CASCADE-3D and British Energy's PANTHER

    Energy Technology Data Exchange (ETDEWEB)

    Attale, F.; Koegl, J. [Framatome ANP GmbH, Nuclear Fuel Cycle, Erlangen (Germany); Knight, M.; Bryce, P. [British Energy, Nuclear Technology Branch, Gloucester (United Kingdom)

    2001-07-01

    Sizewell B Cycle 5 is the first cycle, after 4 cycles with BNFL fuel, with a reload consisting of Framatome ANP HTP (high thermal performance) fuel assemblies. The impact of this fuel vendor change on the Nuclear Design area is that, according to British energy's (BE) practice, the Framatome ANP's nuclear design code system CASCADE-3D is used for the majority of the cycle specific safety case calculations. However, other parts of the safety submission (e.g. 3D transient analyses) are made by using the BE code PANTHER. Before using in parallel two different code systems for reload core licensing extensive comparisons of applied methodologies and obtained results were required to ensure an acceptable level of agreement. (orig.)

  4. Computer-based training at Sellafield

    International Nuclear Information System (INIS)

    Cartmell, A.; Evans, M.C.

    1986-01-01

    British Nuclear Fuel Limited (BNFL) operate the United Kingdom's spent-fuel receipt, storage, and reprocessing complex at Sellafield. Spent fuel from graphite-moderated CO 2 -cooled Magnox reactors has been reprocessed at Sellafield for 22 yr. Spent fuel from light water and advanced gas reactors is stored pending reprocessing in the Thermal Oxide Reprocessing Plant currently being constructed. The range of knowledge and skills needed for plant operation, construction, and commissioning represents a formidable training requirement. In addition, employees need to be acquainted with company practices and procedures. Computer-based training (CBT) is expected to play a significant role in this process. In this paper, current applications of CBT to the filed of nuclear criticality safety are described and plans for the immediate future are outlined

  5. An assessment of the radiological significance of consuming wild foods collected near the Sellafield nuclear fuel reprocessing plant

    International Nuclear Information System (INIS)

    Fulker, M.J.; McKay, K.; Jackson, D.; Leonard, D.R.P.

    1996-01-01

    Extensive monitoring of conventional agricultural produce in the vicinity of the BNFL Sellafield plant is undertaken, by both the operator and the Ministry of Agriculture, Fisheries and Food, to determine levels of radioactivity and douses arising to the consumer Monitoring is also undertaken, albeit less extensively, for market garden and domestic produce. By contrast, few data exist with respect to levels of radioactivity in 'wild foods' (e.g. hedgerow fruits, field mushrooms etc.) or associated consumption habits. It has been postulated that such foodstuffs could contribute an appreciable radiation exposure dose to groups of high level consumers, potentially including members of the existing identified critical group for local agricultural produce. This paper assess the actual radiological significance of wild foods collected near Sellafield. (author)

  6. Reprocessing plants safety

    International Nuclear Information System (INIS)

    Davies, A.G.; Leighton, C.; Millington, D.

    1989-01-01

    The reprocessing of irradiated nuclear fuel at British Nuclear Fuels (BNFL) Sellafield site consists of a number of relatively self-contained activities carried out in separate plants across the site. The physical conditions and time scales applied in reprocessing and storage make it relatively benign. The potential for minor releases of radioactivity under fault conditioning is minimised by plant design definition of control procedures, training and supervision. The risks to both the general public and workforce are shown to be low with all the safety criteria being met. Normal operating conditions also have the potential for some occupational radiation exposure and the plant and workers are monitored continuously. Exposure levels have been reduced steadily and will continue to fall with plant improvements. (U.K.)

  7. Fuel integrity project: analysis of light water reactor fuel rods test results

    International Nuclear Information System (INIS)

    Dallongeville, M.; Werle, J.; McCreesh, G.

    2004-01-01

    BNFL Nuclear Sciences and Technology Services and COGEMA LOGISTICS started in the year 2000 a joint project known as FIP (Fuel Integrity Project) with the aim of developing realistic methods by which the response of LWR fuel under impact accident conditions could be evaluated. To this end BNFL organised tests on both unirradiated and irradiated fuel pin samples and COGEMA LOGISTICS took responsibility for evaluating the test results. Interpretation of test results included simple mechanical analysis as well as simulation by Finite Element Analysis. The first tests that were available for analysis were an irradiated 3 point bending commissioning trial and a lateral irradiated hull compression test, both simulating the loading during a 9 m lateral regulatory drop. The bending test span corresponded roughly to a fuel pin intergrid distance. The outcome of the test was a failure starting at about 35 mm lateral deflection and a few percent of total deformation. Calculations were carried out using the ANSYS code employing a shell and brick model. The hull lateral compaction test corresponds to a conservative compression by neighbouring pins at the upper end of the fuel pin. In this pin region there are no pellets inside. The cladding broke initially into two and later into four parts, all of which were rather similar. Initial calculations were carried out with LS-DYNA3D models. The models used were optimised in meshing, boundary conditions and material properties. The calculation results compared rather well with the test data, in particular for the detailed ANSYS approach of the 3 point bending test, and allowed good estimations of stresses and deformations under mechanical loading as well as the derivation of material rupture criteria. All this contributed to the development of realistic numerical analysis methods for the evaluation of LWR fuel rod behaviour under both normal and accident transport conditions. This paper describes the results of the 3 point bending

  8. Control of radiocaesium discharges to the Irish Sea: ICRP-26 in practice

    International Nuclear Information System (INIS)

    Handyside, I.; Hunt, G.J.; Partington, C.

    1982-01-01

    Experience of application of the ICRP dose limitation system is described in the context of control of radioactive waste discharges to the north-east Irish Sea from the British Nuclear Fuels Limited (BNFL) Sellafield Works. The radiological significance of these discharges is mainly due to radiocaesium from the magnox fuel storage ponds. The discharges increased in 1974 owing to corrosion of magnox fuel; radiation exposure of the public mainly through the fish and shellfish consumption pathway also increased. BNFL, in consultation with Government Departments, decided to install an ion-exchange treatment plant to remove radioactivity from pond effluents. This plant is presently being built and will provide a long-term reduction in radiocaesium discharges. Optimization will play a major part in determining its operating regime. Meanwhile, measures to reduce discharges have been taken by circulating pond water through skips of zeolite installed in the ponds. Differential cost-benefit analysis has been used to indicate the optimum replacement rate of skips; experience of this is described. A range of skip costs was used to allow for some factors which were not uniquely definable. Detrimental costs were estimated from collective dose commitments and a range of values of the man-Sv from Pound 2000 to Pound 50,000. Other, non-quantifiable, factors were relevant. Following these considerations, the current skip replacement frequency is about 30 year -1 . Skips are presently reducing collective effective dose equivalent commitments to the UK and European populations by about half, or some 150 man-Sv.year -1 . Finally, to demonstrate conformity with the overall ICRP dose limitation system, compliance with dose limits is described. Effective dose equivalents to the relevant critical groups for the years 1977 to 1980 are presented. The use of zeolite skips has, here too, given significant reductions over this time, from 33% to (provisionally) 15% of the ICRP-recommended dose

  9. Fuel integrity project: analysis of light water reactor fuel rods test results

    Energy Technology Data Exchange (ETDEWEB)

    Dallongeville, M.; Werle, J. [COGEMA Logistics (AREVA Group) (France); McCreesh, G. [BNFL Nuclear Sciences and Technology Services (United Kingdom)

    2004-07-01

    BNFL Nuclear Sciences and Technology Services and COGEMA LOGISTICS started in the year 2000 a joint project known as FIP (Fuel Integrity Project) with the aim of developing realistic methods by which the response of LWR fuel under impact accident conditions could be evaluated. To this end BNFL organised tests on both unirradiated and irradiated fuel pin samples and COGEMA LOGISTICS took responsibility for evaluating the test results. Interpretation of test results included simple mechanical analysis as well as simulation by Finite Element Analysis. The first tests that were available for analysis were an irradiated 3 point bending commissioning trial and a lateral irradiated hull compression test, both simulating the loading during a 9 m lateral regulatory drop. The bending test span corresponded roughly to a fuel pin intergrid distance. The outcome of the test was a failure starting at about 35 mm lateral deflection and a few percent of total deformation. Calculations were carried out using the ANSYS code employing a shell and brick model. The hull lateral compaction test corresponds to a conservative compression by neighbouring pins at the upper end of the fuel pin. In this pin region there are no pellets inside. The cladding broke initially into two and later into four parts, all of which were rather similar. Initial calculations were carried out with LS-DYNA3D models. The models used were optimised in meshing, boundary conditions and material properties. The calculation results compared rather well with the test data, in particular for the detailed ANSYS approach of the 3 point bending test, and allowed good estimations of stresses and deformations under mechanical loading as well as the derivation of material rupture criteria. All this contributed to the development of realistic numerical analysis methods for the evaluation of LWR fuel rod behaviour under both normal and accident transport conditions. This paper describes the results of the 3 point bending

  10. Research activities of the nuclear graphite research group at the University of Manchester, UK

    International Nuclear Information System (INIS)

    Marsden, B.J.; Fok, A.S.L.; Marrow, J.; Mummery, P.

    2004-01-01

    In 2001 the Nuclear Safety Division (NSD) of the UK Health and Safety Executive (HSE) decided to underwrite the Nuclear Graphite Research Group (NGRG) at the University of Manchester, UK with the aim of providing a source of independent research and advice to the HSE (NSD). Since then the group has rapidly expanded to 16 members and attracted considerable funding from the nuclear power industry and the regulator for a wide range of research and consultancy work. It is now also part of the Material Performance Centre within the BNFL Universities Research Alliance. Extensive collaboration exists between the group and other nuclear research institutes, both in the UK and overseas. This paper briefly describes some of the research programmes being carried out by the NGRG at Manchester. (author)

  11. The media treatment of nuclear risks

    International Nuclear Information System (INIS)

    Wilkinson, J.

    1987-01-01

    The way that newspapers, radio and television news work, is explained so that reporting of nuclear stories can be better understood. The media's attitude to what makes a story newsworthy is explained. This, coupled with a chronology of the rise of the anti-nuclear lobby, is used to explain why some stories have been given prominence. The secretive and evasive attitude of the nuclear industry coupled with poorly communicated information about leaks etc have contributed to a lack of trust and made the public more aware and concerned with nuclear matters. This has sometimes led to unbalanced reporting by the media. The coverage of the Chernobyl reactor accident is examined. Some general points about the openness of BNFL and the government's reporting of nuclear incidents are made. (UK)

  12. The development of a deep repository-progress in the UK

    International Nuclear Information System (INIS)

    Beale, H.; Mogg, C.S.

    1992-01-01

    United Kingdom Nirex Ltd, a company jointly owned by the major partners in the UK nuclear industry, is responsible for developing a deep disposal facility for low-level and intermediate-level radioactive waste. In July 1991 Nirex announced its intention to concentrate geological investigations at Sellafield, where BNFL's existing operations give rise to approximately 60% of the wastes destined for a repository. The main features of the Nirex design process, from early considerations through the main features of a preferred conceptual design and its advantages, are described. Subject to Nirex obtaining planning permission, following a Public Inquiry, the proposed program would allow the UK nuclear industry to fulfill its responsibilities with respect to declared Government policy by providing a safe deep geological disposal facility early in the next century. (author)

  13. The current status and future plans for the Monte Carlo codes MONK and MCBEND

    International Nuclear Information System (INIS)

    Smith, N.; Shuttleworth, T.; Grimstone, M.; Hutton, L.; Armishaw, M.; Bird, A.; France, N.; Connolly, S.

    2001-01-01

    MONK and MCBEND are software tools used for criticality/reactor physics and shielding/dosimetry/general radiation transport applications respectively. The codes are developed by a collaboration comprising AEA Technology and BNFL, and AEA Technology's ANSWERS Software Service supplies them to customers throughout the world on a commercial basis. In keeping with this commercial nature it is vital that the codes' development programmes evolve to meet the diverse expectations of the current and potential customer base. This involves striving to maintain an acceptable balance in the development of the various components that comprise a modern software package. This paper summarises the current status of MONK and MCBEND by indicating how the task of trying to achieve this difficult balance has been addressed in the recent past and is being addressed for the future. (orig.)

  14. Energy policy and the public health

    International Nuclear Information System (INIS)

    Wade, B.

    1979-01-01

    The various aspects of the nuclear fuel cycle and its effect on public health are described. For the U.K., it is shown that the maximum doses to an individual of the general public are well below the ICRP standards. For nuclear workers, the standard mortality ratio rate for UKAEA and BNFL workers is less than the national average and considerably less than that for miners, quarrymen and other industrial employees. The radiological risk to the general public from nuclear plant accidents is very small compared to the general hazards of life. In conclusion, the hazards involved in nuclear technology are no different in kind or in scale to those of existing technologies and indeed the radiological effects on health are better understood than the health risks associated with other technologies. (U.K.)

  15. Funding Decommissioning - UK Experience

    International Nuclear Information System (INIS)

    MacKerron, Gordon

    2006-01-01

    'Funding' started with CEGB and SSEB (state-owned electric utilities) in 1976 using the internal un-segregated fund route (i.e unfunded). This continued until privatisation of electricity industry (excluding nuclear) in 1990. Assets bought with the internal un-segregated fund were mostly transferred into non-nuclear private utilities. New state-owned Nuclear Electric (England and Wales) was given a 'Fossil Fuel Levy', a consumer charge of 10% on retail bills, amounting to c. BP 1 bn. annually. This allowed Nuclear Electric to trade legally (A reserve of BP 2.5 bn. was available from Government if company ran out of money). By 1996 the newer nuclear stations (AGRS plus PWR) were privatised as British Energy. British Energy started an external segregated fund, the Nuclear Decommissioning Fund, with a starting endowment of c. BP 225 m. - and BE made annual contributions of British Pound 16 m. into the Fund. Assumptions were that BE had 70 to accumulate cash and could get a 3.5% average annual real return. Older stations (Magnox) were left in private sector and went to BNFL in 1997. Magnox inherited the surplus cash in BE - mostly unspent Fossil Fuel Levy receipts - of c. BP 2.6 bn. Government gave an 'Undertaking' to pay BP 3.8 bn. (escalating at 4.5% real annually) for Magnox liabilities, should Magnox Electric run out of cash. BNFL inherited the BP 2.6 bn. and by 2000 had a 'Nuclear Liabilities Investment Portfolio' of c. BP 4 bn. This was a quasi-segregated internal fund for liabilities in general. [Note: overall UK nuclear liabilities in civilian sector were running at c. BP 48 bn. by now]. BE started profitable and paid BP 100 m. annually in dividends to private investors for several years. BE ran into severe financial problems after 2001 and Government organised restructuring aid, now approved by European Commission. Terms include: - BE now to contribute BP 20 m. a year into an expanded Nuclear Liabilities Fund; - A bond issue of BP 275 m. to go to Fund; - 65

  16. "Glass Formulation and Testing with TWRS LAW Simulants," Final Report to Duratek Inc. and BNFL Inc.

    Energy Technology Data Exchange (ETDEWEB)

    Muller, Isabelle S. [The Catholic University of America, Washington, DC (United States); Pegg, Ian L. [The Catholic University of America, Washington, DC (United States); Gan, Hao [The Catholic University of America, Washington, DC (United States); Buechele, Andrew C. [The Catholic University of America, Washington, DC (United States); Kim, C. [The Catholic University of America, Washington, DC (United States); Lai, Shan-Tao T. [The Catholic University of America, Washington, DC (United States); Del Rosario, G. [The Catholic University of America, Washington, DC (United States); Yan, Q. [The Catholic University of America, Washington, DC (United States); Kruger, Albert A. [The Catholic University of America, Washington, DC (United States)

    2015-06-22

    This report presents the results of glass formulation development with TWRS LAW simulants that was conducted at the Vitreous State Laboratory of The Catholic University of America during TWRS Phase I.

  17. Decommissioning of nuclear power stations

    International Nuclear Information System (INIS)

    Gregory, A.R.

    1988-01-01

    In the United Kingdom the Electricity Boards, the United Kingdom Atomic Energy Authority (UKAEA) and BNFL cooperate on all matters relating to the decommissioning of nuclear plant. The Central Electricity Generating Board's (CEGB) policy endorses the continuing need for nuclear power, the principle of reusing existing sites where possible and the building up of sufficient funds during the operating life of a nuclear power station to meet the cost of its complete clearance in the future. The safety of the plant is the responsibility of the licensee even in the decommissioning phase. The CEGB has carried out decommissioning studies on Magnox stations in general and Bradwell and Berkeley in particular. It has also been involved in the UKAEA Windscale AGR decommissioning programme. The options as to which stage to decommission to are considered. Methods, costs and waste management are also considered. (U.K.)

  18. The case for reprocessing: the operational experience of a modern reprocessing industry

    International Nuclear Information System (INIS)

    Giraud, J.P.; Kelly, W.

    1993-01-01

    Reprocessing is a high-tech industry that works. An impressive effort of R and D, industrial deployment and operational experience has been accumulated by COGEMA and BNFL, leading these companies to offer a commercial service which is the only proper management of spent fuel and waste that is both technically demonstrated and qualified by the safety authorities of European and overseas countries. Reprocessing, as every technology-based industry will continue to progress in the future. Recycling the fissile materials reclaimed from spent fuel: uranium and plutonium, is the complementary and indispensable last link to effectively close the fuel cycle and control in particular the production of plutonium and other long-lived actinides. This paper will describe the state of development attained in France and Great Britain and will underline the main advantages of the reprocessing/recycling strategy

  19. The selling of Sellafield (the public image)

    International Nuclear Information System (INIS)

    White, David.

    1986-01-01

    The advertising campaign planned to restore the public image of Sellafield is discussed. Two aspects of the Sellafield site are being promoted especially, the first is that the discharges of long life radioactivity are being reduced. The second is the 'site accessibility' of Sellafield -BNFL is trying to encourage visitors to see for themselves what goes on at Sellafield. There is evidence that this will allay the fears and suspicions of the public. It is suggested, however, that providing information about nuclear power may be counter-productive as the concept of nuclear disaster may receive greater attention. The Sellafield site is difficult to promote whilst it continues to suffer leaks and it is suggested that the only way to promote Sellafield successfully may be by appealing to nationalism as the French have done in their nuclear campaign. (U.K.)

  20. Enhancements in the thorp reprocessing plant

    Energy Technology Data Exchange (ETDEWEB)

    Wakem, M.J.; Brownridge, M. [Thorp Technical Dept. and Research and Technology, BNFL plc, Sellafield, seascale, Cumbria, CA (United Kingdom)

    2000-07-01

    A number of successful enhancements have been made to the process at the Thorp reprocessing plant at Sellafield. After a long and detailed Research and Development programme followed by an intensive design/construction project, Thorp was inactively commissioned with first active shear in March 1994. The plant has now reached a mature stage in its development, following successful active commissioning demonstrating flowsheet or better performance in the solvent extraction cycles. Enhancements are now sought to achieve a range of objectives. Against a background of ever tighter regulatory control both in terms of safety and environmental discharge, BNFL are continuing to invest in further improvements with short, medium and longer term objectives to improve plant throughput; expand the range of feed fuels; reduce environmental discharges and reduce running costs. This paper describes a few of these enhancements. (authors)

  1. Enhancements in the thorp reprocessing plant

    International Nuclear Information System (INIS)

    Wakem, M.J.; Brownridge, M.

    2000-01-01

    A number of successful enhancements have been made to the process at the Thorp reprocessing plant at Sellafield. After a long and detailed Research and Development programme followed by an intensive design/construction project, Thorp was inactively commissioned with first active shear in March 1994. The plant has now reached a mature stage in its development, following successful active commissioning demonstrating flowsheet or better performance in the solvent extraction cycles. Enhancements are now sought to achieve a range of objectives. Against a background of ever tighter regulatory control both in terms of safety and environmental discharge, BNFL are continuing to invest in further improvements with short, medium and longer term objectives to improve plant throughput; expand the range of feed fuels; reduce environmental discharges and reduce running costs. This paper describes a few of these enhancements. (authors)

  2. Statement of work for architect-engineer services, initial pretreatment module

    International Nuclear Information System (INIS)

    Sowa, K.B.

    1994-01-01

    This Statement of Work describes the Architect-Engineer services to be provided by Raytheon/BNFL in providing a conceptual design (Contract TGW-SVV-063869) for the Initial Pretreatment Module (IPM), Project W-236B, at the Hanford site, Richland, Washington. The IPM Project, a radiochemical process facility, will be designed and constructed for an initial phase of waste pretreatment, which will be for the removal of cesium from supernatant wastes to produce a Low-level waste (LLW) stream to a vitrification facility. The design shall also accommodate side streams of High-Level Waste (HLW) fractions that will be directed to suitable, existing storage tanks where they will be recombined with an additional high-activity waste fraction generated from pretreatment of the tank waste sludges and solids. This combined high-activity waste fraction will be immobilized as glass and disposed in a geological repository

  3. System specification/system design document comment review: Plutonium Stabilization and Packaging System. Notes of conference

    International Nuclear Information System (INIS)

    1996-01-01

    A meeting was held between DOE personnel and the BNFL team to review the proposed resolutions to DOE comments on the initial issue of the system specification and system design document for the Plutonium Stabilization and Packaging System. The objectives of this project are to design, fabricate, install, and start up a glovebox system for the safe repackaging of plutonium oxide and metal, with a requirement of a 50-year storage period. The areas discussed at the meeting were: nitrogen in can; moisture instrumentation; glovebox atmosphere; can marking bar coding; weld quality; NFPA-101 references; inner can swabbing; ultimate storage environment; throughput; convenience can screw-top design; furnacetrays; authorization basis; compactor safety; schedule for DOE review actions; fire protection; criticality safety; applicable standards; approach to MC and A; homogeneous oxide; resistance welder power; and tray overfill. Revised resolutions were drafted and are presented

  4. Current meter observations near the Sellafield pipeline, 1984-1986

    International Nuclear Information System (INIS)

    Jones, S.R.; Norris, S.

    1988-01-01

    Low-level liquid radioactive wastes are discharged into the north-east Irish Sea, under authorization, from the Sellafield reprocessing plant run by British Nuclear Fuels (BNFL). The effluent contains a range of radionuclides including caesium-137. The discharges are monitored and assessed by the Aquatic Environment Protection Division which is part of the Ministry of agriculture, Food and Fisheries. The results from the Sellafield current meter mooring in the Irish Sea from December 1983 to December 1986 are presented. The aim was to assess long-term tidal and residual current conditions under a variety of wind and current combinations as part of the assessment of the distribution of discharged radionuclides. The instrumentation is described briefly. Periods of data loss (due to meter failure or loss) and the data processing are explained. The results of the current metering are presented. (U.K.)

  5. Optimization study and preliminary design for Latina NPP early core retrieval and reactor dismantling

    International Nuclear Information System (INIS)

    Macci, E.; Zirpolo, S.; Imparato, A.; Cacace, A.; Parry, D.; Walkden, P.

    2002-01-01

    In June 2000, an agreement was established between Sogin and BNFL to enable the two companies to co-operate, using their specific experiences in the decommissioning field, for the benefit of projects in Italy, the United Kingdom and for third markets. A decommissioning strategy for the Latina NPP was initially developed in a Phase 1 Study which produced a conceptual design for the decommissioning of the reactor. This study was completed in June 2000. Since then, a second study has been completed, which has further developed the strategy and produced preliminary designs for the early dismantling of the core and reactor building at Latina. The engineering and safety data were produced in order to support Sogin in the preparation of a safety case for plant decommissioning. This safety case was submitted to the Italian Regulator, ANPA, in February 2002. (author)

  6. Office of River Protection (ORP) Monthly Performance Report for September 2000

    International Nuclear Information System (INIS)

    WAGNILD, K.J.

    2000-01-01

    CH2M Hill Hanford Group, Inc. (CHG) had an outstanding year. The most significant accomplishments that occurred throughout fiscal year (FY) 2000 include the following: On April 24,2000, DOE ORP received BNFL Inc. B-1 deliverables and CHG completed Phase 1 Part B-2 Readiness-to-Proceed (RTP), to demonstrate the ability to provide waste feed to be treated/stored in a long-term disposal facility. The RTP consisted of key enabling assumptions, critical risks, waste handling actions, financial and schedule risk analysis, staffing plans, a project execution plan, and a resource loaded schedule. The Department determined that the BNFL Inc. proposal was unacceptable in many areas and essentially shifted the financial risk from BNFL Inc. back to the Federal government; thus a key benefit of privatization was lost. On May 8,2000, the Secretary announced that the privatization contract be terminated. In the interim, the Department directed the onsite Tank Farm Contractor, CHG, to continue the design work scope for the Waste Treatment and Immobilization Plant until a new waste treatment contract is awarded. DOE ORP released its request for proposals (RFP) for a new Waste Treatment and Immobilization contractor on August 31,2000 and is on schedule to meet award of the contract by January 15,2000. CHG successfully reached 1,000,000 safe work hours without a lost workday injury or illness on Wednesday, September 23,2000. The record was initiated on May 23,2000 and took 114 days to achieve. All Tri-Party Agreement and Consent Decree milestones scheduled for the fiscal year were completed. Along with meeting all enforceable agreement milestones, nineteen out of twenty Performance Incentives (PIS) were successfully completed. The 20 PIS comprised of 114 specific deliverables, of which 107 were met. In addition to the 20 scheduled PIS, six accelerated activities were completed. Tank 241-SY-101 hydrogen generation was successfully mitigated this fiscal year, including a series of

  7. SRP Meeting: North west regional conference

    Energy Technology Data Exchange (ETDEWEB)

    Kennedy, Annette [NNC Limited, Manchester (United Kingdom)

    2002-06-01

    The SRP North West Regional Conference was held in the Education Centre, Christie Hospital NHS Trust in Manchester on the subject of Ionising Regulations 1999 (IRR99) two years on. The Chairman for the morning session was David Abbott from BNFL and for the afternoon was Anne Walker from Christie Hospital. Dr Joanne Nettleton, a HM Principal Specialist Inspector (Radiation) in the Field Operations Directorate, explained the view of the HSE. She outlined that the IRR99 have been in force since January 2000 after a comprehensive consultation exercise. The results that have been seen to date are, not surprisingly, no increase in exposure levels, an increased profile of radiation protection and an improved standing of RPAs. The SRP run a Continuing Professional Development scheme as a personal aid to maintain an adequate level of professionalism, demonstrate competence and as a guide to employers for them to maintain a professional Radiation Protection Service. There are currently over 300 people using the SRPs CPD scheme. They have also detailed a new mentoring system. In conclusion RPA 2000 is successfully meeting the needs of RPAs in the UK and the portfolios of evidence are improving. Overall, the SRP CPD scheme is effective and cheap. David Owen, Radiological Protection Manager responsible for policy and strategy issues in this field, gave a summary of the operation of the BNFL RPA Assessment Scheme, of which he is Secretary to the Management Board. The BNFL RPA Assessment Scheme is recognised by the HSE and has a number of subtle differences from the RPA 2000 scheme. RPAs advise on the restriction of exposure, designation of area, local rules, selection of the RPS, the training of the RPS and other staff, hazard identification, risk assessment, facility design, contingency planning, waste management and transport and any other matters relating to ionising radiation. Becoming an RPA within the medical sector is not easy. Firstly there is two years basic training

  8. SRP Meeting: North west regional conference

    International Nuclear Information System (INIS)

    Kennedy, Annette

    2002-01-01

    The SRP North West Regional Conference was held in the Education Centre, Christie Hospital NHS Trust in Manchester on the subject of Ionising Regulations 1999 (IRR99) two years on. The Chairman for the morning session was David Abbott from BNFL and for the afternoon was Anne Walker from Christie Hospital. Dr Joanne Nettleton, a HM Principal Specialist Inspector (Radiation) in the Field Operations Directorate, explained the view of the HSE. She outlined that the IRR99 have been in force since January 2000 after a comprehensive consultation exercise. The results that have been seen to date are, not surprisingly, no increase in exposure levels, an increased profile of radiation protection and an improved standing of RPAs. The SRP run a Continuing Professional Development scheme as a personal aid to maintain an adequate level of professionalism, demonstrate competence and as a guide to employers for them to maintain a professional Radiation Protection Service. There are currently over 300 people using the SRPs CPD scheme. They have also detailed a new mentoring system. In conclusion RPA 2000 is successfully meeting the needs of RPAs in the UK and the portfolios of evidence are improving. Overall, the SRP CPD scheme is effective and cheap. David Owen, Radiological Protection Manager responsible for policy and strategy issues in this field, gave a summary of the operation of the BNFL RPA Assessment Scheme, of which he is Secretary to the Management Board. The BNFL RPA Assessment Scheme is recognised by the HSE and has a number of subtle differences from the RPA 2000 scheme. RPAs advise on the restriction of exposure, designation of area, local rules, selection of the RPS, the training of the RPS and other staff, hazard identification, risk assessment, facility design, contingency planning, waste management and transport and any other matters relating to ionising radiation. Becoming an RPA within the medical sector is not easy. Firstly there is two years basic training

  9. Feasibility Study for the Development of a Surface Plasmon Resonance spectroscopy-based Sensor for the BNFL-Hanford

    International Nuclear Information System (INIS)

    Anderson, B.B.

    2000-01-01

    The Department of Energy must treat and dispose of large volumes of radioactive waste stored in underground storage tanks at five DOE sites. Technology development has been focused on the separation and removal of various radionuclides from the supernatant contained in the Hanford waste tanks

  10. EDRP public local inquiry, UKAEA/BNFL precognition on: PFR fuel reprocessing and radioactive waste management at Dounreay

    International Nuclear Information System (INIS)

    Pugh, O.

    1986-01-01

    A description of PFR fuel reprocessing at Dounreay is given, including brief details of fuel assembly transport, dismantling, chemical separation processes and reprocessing experience. The origin of radioactive wastes from PFR reprocessing, and the types of radioactive waste are outlined. The management of radioactive waste, including storage, treatment and disposal is described. (U.K.)

  11. Managing the nuclear legacy in the UK - Progress towards the establishment of the nuclear decommissioning authority

    International Nuclear Information System (INIS)

    Sellers, Robin M.

    2003-01-01

    In November 2001, the British Government announced its intention to undertake a radical change in the arrangements for managing public sector civil nuclear liabilities in the UK. The UK Government's proposals for this transformation were published in a White Paper Managing the Nuclear Legacy - A Strategy for Actions published on 4 July 2002. This envisages the establishment of a new organisation, the Nuclear Decommissioning Authority (NDA), responsible to Government and with a remit to ensure that the UK's nuclear legacy is cleaned up safely, securely, cost effectively and in ways which protect the environment. The NDA will be responsible for some twenty UK nuclear sites comprising about 85% of the UK's civil nuclear liabilities. These sites are those currently operated by the United Kingdom Atomic Energy Authority (UKAEA) and British Nuclear Fuels plc (BNFL), and amongst other things include many facilities from the early years of nuclear power etc in the UK, liabilities associated with the Joint European Torus (JET) fusion research project at UKAEA's Culham site, the Magnox nuclear power stations, and the associated facilities at Sellafield for reprocessing. The challenge is to decommission and demolish these facilities, package the radioactive wastes ready for disposal and remediate the sites, taking into account the uncertainties associated with many of the older facilities and the potential technical novelty of the processes that will have to be deployed to achieve this. To prepare the way for the NDA, a special team has been established within the UK Department of Trade and Industry. This team, known as the Liabilities Management Unit (LMU), includes staff from both private and public sectors, and is supported by a partner contractor (Bechtel Management Company Ltd) who bring high quality, experienced project management skills to the team. LMU's principal tasks are: - Acquiring a detailed knowledge of BNFL and UKAEA liabilities; - Establishing common

  12. Managing the nuclear legacy n the UK: Progress towards the establishment of the Nuclear Decommissioning Authority

    International Nuclear Information System (INIS)

    Sellers, R.M.

    2003-01-01

    In November 2001, the British Government announced its intention to undertake a radical revision of the arrangements for managing public sector civil nuclear liabilities in the UK. Its proposals for this transformation were published in a White Paper 'Managing the Nuclear Legacy - A Strategy for Action' published on 4 July 2002. This calls for the formation of a new organisation, originally referred to as the Liabilities Management Authority, but since renamed the Nuclear Decommissioning Authority (NDA), responsible to Government and with a remit to ensure that the UK's nuclear legacy is cleaned up safely, securely, cost effectively and in ways which protect the environment. The NDA will be responsible for some twenty-one UK nuclear sites comprising about 85% of the UK's civil nuclear liabilities. These sites are those currently operated by the United Kingdom Atomic Energy Authority (UKAEA) and British Nuclear Fuels plc (BNFL), and amongst other things include many facilities from the early years of nuclear power etc in the UK, liabilities associated with the Joint European Torus (JET) fusion research project at UKAEA's Culham site, the Magnox nuclear power stations, and the associated facilities at Sellafield for reprocessing as well as those associated with the UK's fast reactor programme based at Dounreay. The challenge is to decommission and dismantle these facilities, package the radioactive wastes ready for disposal and remedy the sites, taking into account the uncertainties associated with many of the older facilities and the potential technical novelty of the processes that will have to be deployed to achieve this. This paper is concerned with the work of the Liabilities Management Unit (LMU) in preparing the way for the NDA and what it has achieved in its first eighteen months. The following issues are addressed: The Liabilities Management Unit and its remit (which presents the LMU Functional Groups and their responsibilities); Acquiring a detailed

  13. Practice of fuel management and outage strategy at Paks NPP

    International Nuclear Information System (INIS)

    Farago, P.; Hamvas, I.; Szecsenyi, Zs.; Nemes, I.; Javor, E.

    2000-01-01

    The Paks Nuclear Power Plant generates almost 40% of Hungarian electricity production at lowest price. In spite of this fact the reduction of operational and maintenance costs is one of the most important goal of the plant management. The proper fuel management and outage strategy can give a considerable influence for this cost reduction. The aim of loading pattern planning is to get the required cycle length with available fuel cassettes and to keep all key parameters of safety analysis under safety limits. Another important point is production at profit, where both the fuel and spent fuel cost are determining. Earlier the conditions given by our only fuel supplier restricted our possibilities, so at the beginning the fuel arrangement changing was the only way to improve efficiency of fuel using. As first step we introduced the low leakage core design. The next step was the 4 years cycle using of some cassettes. By this way nearly half of 3 years cycle old cassettes remained in the core for fourth cycle. In the immediate future we want to use profiled cassettes developed by Russian supplier. Simultaneously we will load new type of WWER cassettes with burnable poison developed by BNFL Company. Hereby we can apply more BNFL cassettes for four years cycle even more. Both cost of fuel and number of spent fuel can be reduced besides keeping parameters under safety limits. The Hungarian in service inspection rules determine that every four year we have to make a complete inspection of reactor vessel. Therefore earlier we had two types of outages. Every 4 years we planned a long outage with 55-65 days duration and normal ones with about 30-35 days duration between the long ones. During the normal outages this way did not give us enough room to utilise the shortest possible critical path determined by works on reactor. Some years ago we changed our outage strategy. Now we plan every 4 years a long outage, and between them one normal and two short ones. As a result the

  14. Britain's nuclear energy policy

    International Nuclear Information System (INIS)

    Duncan, Colin D.

    2000-01-01

    Full text: In the mid 1980s the Labour Party's position and clear intention was to phase out nuclear generated power in the UK. BNFL's reprocessing business was singled out for particular criticism. Many argued that this sounded the death knell for an industry with a legacy of negative public opinion and no commercial future. How against this background then was the Rt. Hon Tony Blair able, on 9 June 1999, to state that 'If we were to question the continued operation of Thorp, I think that would not be right. Thorp is an operation with orders now valued at some 12 billion pounds, it provides 6000 skilled jobs, it indirectly supports many more... I do not support the case of those who would like us to abandon Thorp?' Furthermore, in June 1999 the Royal Society stated that, 'it is vital to keep the nuclear option open' and in October of the same year the House of Commons Trade Industry Select Committee went further and advised, 'a formal presumption be made now for the purposes of long-term planning that new nuclear plant may be required in the course of the next two decades'. On 13 July 1999, the Secretary of State for Trade and Industry, Rt. Hon Stephen Byers, announced a possible sale of up to 49% of BNFL by a Public Private Partnership. Dare we view this as the genesis of a nuclear renaissance for the United Kingdom? This clear change in political attitude towards the nuclear option has come about as a result of a concerted public and government relations effort over the past ten years. That said, many barriers remain if we are to meet the challenge of delivering new nuclear build in the UK. Public opinion may allow new build but only if the industry demonstrates a track record of safety and environmental stewardship. There will always be the 'not in my back yard' argument so we must be a good neighbour and, most importantly of all, a long-term solution must be found for the disposal of nuclear waste. If the stage is set for the nuclear renaissance, the industry

  15. A dynamic compartmental food chain model of radiocaesium transfer to Apodemus sylvaticus in woodland ecosystems

    International Nuclear Information System (INIS)

    Toal, M.E.; Copplestone, D.; Johnson, M.S.; Jackson, D.; Jones, S.R.

    2001-01-01

    A study was undertaken to quantify the activity concentrations of 137Cs in Apodemus sylvaticus (the woodmouse) in two woodland sites, Lady Wood and Longrigg Wood, adjacent to British Nuclear Fuels Ltd. (BNFL) Sellafield, Cumbria, UK. A deterministic dynamic compartmental food chain model was also constructed to predict 137Cs activity concentration [Bq kg -1 dry weight (dw)] in A. sylvaticus on a seasonal basis given the activity concentrations in its diet. Within the coniferous woodland site (Lady Wood), significant differences were found between seasons (P x / 2.3 Bq kg -1 dw) being attributed to mycophagy. Fungal concentrations ranged from 2-3213 Bq kg -1 dw. The modelled activity concentrations fell between the confidence intervals of the observed data in four of the six seasonal cohorts sampled. Disparities between predicted and observed activity concentrations are attributed to uncertainties surrounding the fundamental feeding ecology of small mammals

  16. The application of research and technology in the Highly Active Liquor storage and treatment facilities at Sellafield

    International Nuclear Information System (INIS)

    Nixon, C.R.

    2004-01-01

    At the Sellafield nuclear site, Highly Active Liquor (HAL) produced from Magnox and Oxide reprocessing operations is evaporated and interim stored in the Highly Active Liquor Evaporation and Storage (HALES) complex prior to vitrification in one of three Waste Vitrification Plant (WVP) processing lines. These plants are integral to the current commercial activities at Sellafield and also in safely discharging liabilities in the future. The management and operation of HALES and WVP are subject to significant regulatory and public scrutiny and there is the requirement to deliver a reduction in the HAL volumes stored in HALES in accordance with a regulator imposed HAL stock reduction specification. In delivering the required reduction BNFL has faced a number of technical and operational challenges which have resulted in the development and execution of significant programmes of research and development and technical and engineering projects. The key challenges faced are briefly presented. (author)

  17. A model for the bioaccumulation of 99Tc in lobsters (Homarus gammarus) from the West Cumbrian coast

    International Nuclear Information System (INIS)

    Olsen, Y.S.; Vives i Batlle, J.

    2003-01-01

    A biokinetic model is presented that simulates the uptake and release of 99 Tc by the European lobster (Homarus gammarus). This organism is of significant radioecological interest since lobsters, in contrast to most other organisms, have a high affinity for 99 Tc. The model is designed to represent annually averaged 99 Tc concentrations in lobsters from the Cumbrian coast, where significant levels of 99 Tc have been released under authorisation by the nuclear fuel reprocessing plant at BNFL Sellafield. This paper describes the construction of the model, how it was calibrated using data from published literature, and preliminary results indicating that model output agrees well with the available monitoring data. Given that this model successfully combines laboratory and field data, this research could potentially make a significant contribution to the field, as, to date, it has been difficult to predict and explain concentrations of 99 Tc in lobsters

  18. Questioning nuclear waste substitution: a case study.

    Science.gov (United States)

    Marshall, Alan

    2007-03-01

    This article looks at the ethical quandaries, and their social and political context, which emerge as a result of international nuclear waste substitution. In particular it addresses the dilemmas inherent within the proposed return of nuclear waste owned by Japanese nuclear companies and currently stored in the United Kingdom. The UK company responsible for this waste, British Nuclear Fuels Limited (BNFL), wish to substitute this high volume intermediate-level Japanese-owned radioactive waste for a much lower volume of much more highly radioactive waste. Special focus is given to ethical problems that they, and the UK government, have not wished to address as they move forward with waste substitution. The conclusion is that waste substitution can only be considered an ethical practice if a set of moderating conditions are observed by all parties. These conditions are listed and, as of yet, they are not being observed.

  19. Nuclear privatization

    International Nuclear Information System (INIS)

    Jeffs, E.

    1995-01-01

    The United Kingdom government announced in May 1995 plans to privatize the country's two nuclear generating companies, Nuclear Electric and Scottish Nuclear. Under the plan, the two companies will become operating divisions of a unified holding company, to be called British Electric, with headquarters in Scotland. Britain's nuclear plants were left out of the initial privatization in 1989 because the government believed the financial community would be unwilling to accept the open-ended liability of decommissioning the original nine stations based on the Magnox gas-cooled reactor. Six years later, the government has found a way around this by retaining these power stations in state ownership, leaving the new nuclear company with the eight Advanced Gas-cooled Reactor (AGR) stations and the recently completed Sizewell B PWR stations. The operating Magnox stations are to be transferred to BNFL, which operates two Magnox stations of their own at Calder Hall and Chapelcross

  20. The role of opinion research in communications programmes

    International Nuclear Information System (INIS)

    Curtin, Tom

    1995-01-01

    Nirex is a company financed by the UK nuclear industry to dispose of intermediate and some long-lived low-level radioactive waste. The company has no responsibility for high-level radioactive waste. Most low-level waste is disposed of at a shallow site owned by BNFL, one of Nirex's shareholders. At Nirex, we use opinion research in a number of ways: as a map to guide communications programmes; to set baselines and targets to isolate issues of concern to our publics. The Company carries out market research covering three key audiences: the general public, politicians, and journalists. For Nirex, opinion research is a map. It guides our communication programmes in dealing with our key audiences. Without it, we would be driving blind. Opinion research allows us to isolate key issues for communication. It also allows us to measure performance and to see which initiatives are successful and which are not

  1. The nuclear fuel cycle: (2) fuel element manufacture

    International Nuclear Information System (INIS)

    Doran, J.

    1976-01-01

    Large-scale production of nuclear fuel in the United Kingdom is carried out at Springfields Works of British Nuclear Fuels Ltd., a company formed from the United Kingdom Atomic Energy Authority in 1971. The paper describes in some detail the Springfields Works processes for the conversion of uranium ore concentrate to uranium tetrafluoride, then conversion of the tetrafluoride to either uranium metal for cladding in Magnox to form fuel for the British Mk I gas-cooled reactors, or to uranium hexafluoride for enrichment of the fissile 235 U isotope content at the Capenhurst Works of BNFL. Details are given of the reconversion at Springfields Works of this enriched uranium hexafluoride to uranium dioxide, which is pelleted and then clad in either stainless steel or zircaloy containers to form the fuel assemblies for the British Mk II AGR or advanced gas-cooled reactors or for the water reactor fuels. (author)

  2. Applications of virtual reality in Magnox

    International Nuclear Information System (INIS)

    Smith, A.L.

    2000-01-01

    This paper describes the current state of use of VR-based simulation tools to assist the design, development and implementation of a range of complex projects within BNFL Magnox Generation. VR systems are used throughout the life cycle of a project. As a conceptual design tool, parametric techniques have been used to optimize limb lengths of a manipulator used for detailed in-reactor inspection. Extensive path planning is carried out off-line, allowing the rehearsal phase to concentrate on difficult issues such as interactions with the work site. During the rehearsal and site implementation phases, the use of a real-time display of a manipulator working in a simulated reactor environment supplements the views from surveillance cameras. Finally, use of output from the VR system can support the quality assurance and documentation aspects of a task by providing further evidence that the correct components have been inspected/repaired. (author)

  3. Studies of environmental radioactivity in Cumbria. Pt. 13

    International Nuclear Information System (INIS)

    Otlet, R.; Longley, H.; Walker, A.J.

    1989-04-01

    The main objective of the project was to reconstruct a chronology of past 14 C levels in atmospheric CO 2 in the vicinity of the Sellafield reprocessing plant by measuring the 14 C in individual tree rings from trees felled at a number of sites. The profile obtained from the results reflects the build up of the plant operations and related aerial emissions and a conversion of the tree ring records to past annual aerial discharges of 14 C has been attempted. This is compared with values provided from recent estimates of aerial emissions. The effect of dispersion along a coastal transect to a distance of 30km from BNFL Sellafield has also been studied. Comparable, but attenuated profiles to the inland sites are observed although the major peaks are not precisely mirrored along the transect. This is attributed to greater year to year variation due to sea breezes. (author)

  4. Dodewaard fuel supply agreement - a model for the future

    International Nuclear Information System (INIS)

    Raven, L.F.; Hubers, C.

    1980-01-01

    An Agreement between the Utility GKN and the Fuel Supplier BNFL has eliminated any Utility imposed penalty clauses for fuel failure due to operational conditions and, consequently, there are no restrictions imposed by the Fuel Supplier on the reactor operational manoeuvres. The result is that the Utility can now decide if the risk of fuel clad failure during a reactor power ramp outweighs the financial loss due to slower ramp rates. It is the Utility and not the Fuel Supplier who is in the best position to make this judgment provided adequate operational experience and computer codes are available to quantify the risk. The paper discusses the reactor operational experience, including the fuel failure rate and the confirmation of PCI failure by post irradiation examination. It establishes the practicality of the Agreement for the Dodewaard reactor and suggests such arrangements could be beneficial to other Utilities. (author)

  5. Loading, transport and storage of casks of the type CASTOR registered HAW28M in the frame of vitrified high-level waste repatriation from France

    International Nuclear Information System (INIS)

    Horn, Thomas; Graf, Wilhelm; Gosch-Warning, Michaela

    2011-01-01

    Until 2005 the German nuclear power plant operators have contracts with AREVA NC (former COGEMA) and NDA (former BNFL) concerning the reprocessing of spent fuel elements. The reprocessed and vitrified radioactive waste has to be repatriated to Germany. Due to the reprocessing of spent fuel elements with increased burnup and the repatriation after shorter cooling time the total activity and the Cm-244 content of the high-level-waste coquilles have increased since 2008. Consequently the heat output has increased to 2 kW/coquille. Therefore the new transport cask type CASTOR registered HAW28M was developed. The authors describe the design of the casks, the licensing according to the German transport regulations, loading procedures, radiation measurements and shipment completion. In autumn 2011 the repatriation of vitrified high-level waste from France is supposed to be completed with the transport of eleven CASTOR registered HAW28M.

  6. Winning Public Confidence in Sellafield

    International Nuclear Information System (INIS)

    Preece, J. A.

    1991-01-01

    BNF operates the nuclear fuel reprocessing and waste management centre of Sellafield in North West England. It is the largest nuclear site in Britain and perhaps the most famous nuclear plant in Western Europe. It is famous largely because it has long been the target of anti-nuclear interests. Well organised, well funded and well informed anti-nuclear organisations, notably including Green peace and Friends of the Earth, have made propaganda capital based on a number of controversial claims: - that by importing spent nuclear fuel from overseas for reprocessing at Sellafield, BNFL was turning Britain into a nuclear dustbin for the world. That discharges of low level radioactivity from Sellafield cause unacceptable nuclear pollution and endanger health, that the radioactivity in store in various forms on site at Sellafield, for which no permanent disposal routes are yet available, are a danger to the public and constantly threaten a major nuclear accident

  7. Design and operational experience of low level radioactive waste disposal in the United Kingdom

    International Nuclear Information System (INIS)

    Grimwood, P. D.

    1997-01-01

    Low level radioactive wastes have been disposed of at the Drigg near-surface disposal site for over 30 years. These are carried out under a disposal authorization granted by the UK Environment Agency. This is augmented by a three tier comprehensive system of waste controls developed by BNFL involving wasteform specification, consignor and waste stream qualification and waste consignment verification. Until 1988 wastes were disposed of into trench facilities. However, based on a series of integrated optioneering studies, new arrangements have since been brought into operation. Central to these is a wasteform specification based principally on high force compaction of wastes, grouting within 20 m 3 steel overpack containers to essentially eliminate associated voidage and subsequent disposal in concrete lined vaults. These arrangements ensure efficient utilisation of the Drigg site capacity and a cost-effective disposal concept which meets both national and international standards. (author). 7 figs

  8. EDRP public local inquiry, UKAEA/BNFL precognition on: Aspects of Dounreay safety and local liaison relevant to EDRP

    International Nuclear Information System (INIS)

    Blumfield, C.W.

    1986-01-01

    Aspects of safety at Dounreay Nuclear Establishment, including legislation, design safety, industrial safety and radiation monitoring procedures, are discussed. The arrangements for action in an emergency are outlined. Liaison between DNE and the local community, formal and informal, is summarised. (U.K.)

  9. Phase II test plan for the evaluation of the performance of container filling systems

    International Nuclear Information System (INIS)

    BOGER, R.M.

    1999-01-01

    The PHMC will provide tank wastes for final treatment by BNFL from Hanford's waste tanks. Concerns about the ability for ''grab'' sampling to provide large volumes of representative waste samples has led to the development of a nested, fixed-depth sampling system. Preferred concepts for filling sample containers that meet RCRA organic sample criteria were identified by a PHMC Decision Board. These systems will replace the needle based sampling ''T'' that is currently on the sampling system. This test plan document identifies cold tests with simulants that will demonstrate the preferred bottle filling concepts abilities to provide representative waste samples and will meet RCRA criteria. Additional tests are identified that evaluate the potential for cross-contamination between samples and the ability for the system to decontaminate surfaces which have contacted tank wastes. These tests will be performed with kaolidwater and sand/water slurry simulants in the test rig that was used by AEAT to complete Phase 1 tests in FY 1999

  10. Reactor decommissioning in a deregulated market

    International Nuclear Information System (INIS)

    Beverridge, George; Cooper, T.

    2002-01-01

    Full text: Deregulation of the electricity markets in North America and Western Europe has had many profound effects on the electric utilities and the nuclear industry. Deregulation has led to cost transparency, increased competition, and a drive by the utilities to reduce costs in order to maintain market share and margins. In the context of this more competitive and dynamic market having a clear picture of decommissioning liabilities and their successful discharge has a material impact on the financial performance of a utility. This paper will summarise BNFL Environmental Services' experience with regard to its experience in both the planning and implementation phases of a reactor decommissioning project. In particular it will demonstrate how commercial projects in crucial areas of strategy development, project implementation and site restoration, can be combined with an approach that is both commercial and innovative to reduce the risks to a utility. This paper sets out to demonstrate this viewpoint. (author)

  11. A model for the bioaccumulation of {sup 99}Tc in lobsters (Homarus gammarus) from the West Cumbrian coast

    Energy Technology Data Exchange (ETDEWEB)

    Olsen, Y.S.; Vives i Batlle, J. E-mail: jordi.vives@westlakes.ac.uk

    2003-07-01

    A biokinetic model is presented that simulates the uptake and release of {sup 99}Tc by the European lobster (Homarus gammarus). This organism is of significant radioecological interest since lobsters, in contrast to most other organisms, have a high affinity for {sup 99}Tc. The model is designed to represent annually averaged {sup 99}Tc concentrations in lobsters from the Cumbrian coast, where significant levels of {sup 99}Tc have been released under authorisation by the nuclear fuel reprocessing plant at BNFL Sellafield. This paper describes the construction of the model, how it was calibrated using data from published literature, and preliminary results indicating that model output agrees well with the available monitoring data. Given that this model successfully combines laboratory and field data, this research could potentially make a significant contribution to the field, as, to date, it has been difficult to predict and explain concentrations of {sup 99}Tc in lobsters.

  12. Development of a non-conservative radionuclides dispersion model in the ocean and its application to surface cesium-137 dispersion in the Irish Sea

    International Nuclear Information System (INIS)

    Kobayashi, Takuya; Otosaka, Shigeyoshi; Togawa, Orihiko; Hayashi, Keisuke

    2007-01-01

    A numerical simulation model system that consists of an ocean current model, Princeton Ocean Model (POM), and a particle random-walk model, SEA-GEARN, has been developed to describe the migration behavior of non-conservative radionuclides in a shallow water region. Radionuclides in the ocean are modeled in three phases, i.e., the dissolved phase in seawater, the adsorbed with large particulate matter (LPM) and the adsorbed with active bottom sediment. The adsorption and desorption processes between the dissolved and solid phases are solved by the stochastic method with the kinetic transfer coefficients. Deposition of the LPM and re-suspension from bottom sediment are also considered. The system was applied to simulate the long-term (24-year) dispersion of 137 Cs actually released from the BNFL spent nuclear fuel reprocessing plant at Sellafield in United Kingdom. The calculation well reproduced the main characteristics of migration of dissolved 137 Cs concentration in the Irish Sea. (author)

  13. The design of in-cell crane handling systems for nuclear plants

    International Nuclear Information System (INIS)

    Hansford, S.M.; Scott, R.

    1992-01-01

    The reprocessing and waste management facilities at (BNFL's) British Nuclear Fuels Limited's Sellafield site make extensive use of crane handling systems. These range from conventional mechanical handling operations as used generally in industry to high integrity applications through to remote robotic handling operations in radiation environments. This paper describes the design methodologies developed for the design of crane systems for remote handling operations - in-cell crane systems. In most applications the in-cell crane systems are an integral part of the plant process equipment and reliable and safe operations are a key design parameter. Outlined are the techniques developed to achieve high levels of crane system availability for operations in hazardous radiation environments. These techniques are now well established and proven through many years of successful plant operation. A recent application of in-cell crane handling systems design for process duty application is described. The benefits of a systematic design approach and a functionally-based engineering organization are also highlighted. (author)

  14. Superconducting bearings in flywheels

    Energy Technology Data Exchange (ETDEWEB)

    Coombs, T.A.; Campbell, A.M.; Ganney, I.; Lo, W. [Cambridge Univ. (United Kingdom). Interdisciplinary Research Centre in Superconductivity (IRC); Twardowski, T. [International Energy Systems, Chester High Road, Neston, South Wirral (United Kingdom); Dawson, B. [British Nuclear Fuels, Capenhurst, South Wirral (United Kingdom)

    1998-05-01

    Investigations are being carried out into the use of superconducting magnetic bearings to levitate energy storage flywheels. In a planned program of work, Cambridge University are aiming to produce a practical bearing system for Pirouette(TM). The Pirouette(TM) system is designed to provide 5 kWh of recoverable energy which is currently recoverable at a rate of 5 kW (future revisions will provide up to 50 kW). IES (a British Nuclear Fuels subsidiary) the owners of the Pirouette(TM) machine have supplied Cambridge with a flywheel. This flywheel weighs >40 kg and is being levitated using an Evershed-type arrangement in which the superconductor is being used to stabilize the interaction between two magnets. To date we have demonstrated stable levitation in static and low speed tests in a rig designed for low speeds of rotation in air. A second rig which is currently under construction at BNFL will run in vacuum at speeds of up to 50 (orig.) 5 refs.

  15. Studies of U(4) oxidation kinetics in nitric acid and TBP phases

    International Nuclear Information System (INIS)

    Taylor, R.J.; Denniss, I.S.; Koltunov, V.S.; Marchenko, V.I.; Dvoeglazov, K.N.; Savilova, O.A.; Broan, C.J.

    2000-01-01

    U(IV) is an important reagent in current reprocessing plants since it is used to reduce Pu(IV) to Pu(III), therefore, allowing the efficient separation of U and Pu in multi-stage counter-current solvent extraction contactors. The benefits of U(IV) are that it is a kinetically fast reductant and it is a salt free reagent, since U(IV) is oxidised to U(VI) and so does not add to the aqueous waste volumes. Many kinetic reactions of U(IV) have been studied in the past and these are used by BNFL to model the behaviour of U(IV) in process flowsheets. However, some reactions have either not been studied or have been studied many times without conclusive resolution. Therefore, to expand our understanding of U(IV) in the process and to generate data that underpins process models, we are studying a series of U(IV) reactions, and this paper will summarize the results of our kinetic and mechanistic studies. (authors)

  16. A second simulated criticality accident dosimetry experiment

    CERN Document Server

    Adams, N

    1973-01-01

    This experiment was undertaken to facilitate training in criticality dose assessment by UKAEA and BNFL establishments with potential criticality hazards. Personal dosemeters, coins, samples of hair, etc. supplied by the seven participating establishments were attached to a man-phantom filled with a solution of sodium nitrate (simulating 'body-sodium'), and exposed to a burst of radiation from the AWRE pulsed reactor VIPER. The neutron and photon doses were each several hundred rads. Participants made two sets of dose assessments. The first, made solely from the evidence of their routine dosemeters the activation of body-sodium and standard monitoring data, simulated the initial dose assessment that would be made before the circumstances of a real incident were established. The second was made when the position and orientation of the phantom relative to the reactor and the shielding (20 cm of copper) between the reactor core and the phantom were disclosed. Neutron and photon dose assessments for comparison wit...

  17. Evaluation of SuperLig 639 Ion Exchange Resin for the Removal of Rhenium from Hanford Envelope A Simulant

    International Nuclear Information System (INIS)

    King, W.D.

    2000-01-01

    Hanford Radioactive Waste materials have been categorized into four envelopes labeled A through D as specified in the Tank Waste Remediation Contract between BNFL and DOE. 1 Envelopes A, B and C contain only solubilized species and are specified as Low-Activity Waste (LAW). Each envelope is defined based on compositional maximums of chemical and radioactive constituents. Envelopes A and B contain low concentrations of organic species and the primary form of technetium is pertechnetate (TcO4-). Envelope C contains higher levels of organic species and technetium which is primarily in the nonpertechnetate form (presumably complexed TcO2). Envelope D is sludge which has been separated from the supernate and is referred to as High Activity Waste. The current plant design utilizes SuperLig ion exchange resins to remove cesium and technetium (the primary radioactive constituents) from the Hanford LAW. The process is designed to produce a decontaminated waste stream and a concentrated eluate waste stream for vitrification into low and high activity glasses, respectively

  18. Safety provisions for UF{sub 6} handling in the design of a new UF{sub 6} conversion plant

    Energy Technology Data Exchange (ETDEWEB)

    Bannister, S.P. [British Nuclear Fuels plc, Preston (United Kingdom)

    1991-12-31

    British Nuclear Fuels plc (BNFL) Fuel Division is currently undertaking the final design and construction of a new UF{sub 6} conversion plant at its production site at Springfields near Preston in the north of England. The Company has gained much experience in the handling of UF{sub 6} during operation of plants on site since 1961. The major hazard occurs during the liquefication cycle and the basis of the maximum credible incident scenario adopted for safety assessment and design purposes is discussed. This paper considers the design features which have been incorporated in the new plant to counter the hazards presented by the presence of UF{sub 6} in gaseous and liquid form and explains current thinking on operational procedures in areas of potential risk such as cylinder filling. The plant emergency response philosophy and systems are described and specific design provisions which have been included to satisfy the UK regulatory bodies are outlined in some detail.

  19. Nested, fixed-depth fluidic sampler supplementary testing - AEAT doc 2926-2-002

    International Nuclear Information System (INIS)

    REICH, F.R.

    1999-01-01

    This report summarizes the results of cold testing, completed by AEAT, as part of the proof-of-principle testing for a proposed nested, fixed-depth fluidic sampling system. This sampling system will provide waste samples from the PHMC feed tank to support the privatization contract with BNFL. Proof-of-principle tests were completed with 2 wt% and 10 wt% sand/water and 25 wt% kaolin clay/water simulants with a test setup that spanned the 24 ft to 57 ft height required in the feed tank. The tests demonstrated that the system could pump and sample waste materials with low and with high solids content. In addition, the tests demonstrated a need for some design upgrades to the sampling system, as there was material loss when the sample bottle was removed from the sampling needle. These were complementary tests, completed as part of an EM-50 Tank Focus Area (TFA) to develop a sampling system for validating LAW and HLW waste batches for the Privatization Contract

  20. Industrial Complex for Solid Radwaste Management at Chernobyle Nuclear Power Plant

    Energy Technology Data Exchange (ETDEWEB)

    Ahner, S.; Fomin, V. V.

    2002-02-26

    In the framework of the preparation for the decommissioning of the Chernobyl Nuclear Power Plant (ChNPP) an Industrial Complex for Solid Radwaste Management (ICSRM) will be built under the EC TACIS Program in the vicinity of ChNPP. The paper will present the proposed concepts and their integration into existing buildings and installations. Further, the paper will consider the safety cases, as well as the integration of Western and Ukrainian Organizations into a cohesive project team and the requirement to guarantee the fulfillment of both Western standards and Ukrainian regulations and licensing requirements. The paper will provide information on the status of the interim design and the effects of value engineering on the output of basic design phase. The paper therefor summarizes the design results of the involved design engineers of the Design and Process Providers BNFL (LOT 1), RWE NUKEM GmbH (LOT 2 and General) and INITEC (LOT 3).

  1. Environmental impact assessment relating to the proposed siting of the European Demonstration Fast Reactor Fuel Reprocessing Plant (EDRP) at Dounreay, Caithness

    Energy Technology Data Exchange (ETDEWEB)

    1985-01-01

    This Report assesses the likely environmental impact of the European Demonstration Fast Reactor Fuel Reprocessing Plant (EDRP) which the United Kingdom Atomic Authority (UKAEA) and British Nuclear Fuels plc (BNFL) are proposing to build at the Dounreay Nuclear Power Development Establishment (DNE), Caithness and for which they have sought outline planning permission. The format of the report has been designed to meet the guidelines set out in the European Economic Community's Directive (85/337/EEC) concerning the assessment of the environmental effects of certain public and private projects. The Report is presented in four parts: Part A gives information on the present environment at DNE and explains in detail the environmental monitoring which has been carried out there since 1956. Part B describes the proposed development. Part C assesses the likely effects of the proposed development on the environment. Part D lists all the references quoted in this Report together with a bibliography of other sources of information relevant to the proposed development.

  2. Experience of ALARA in controlling radiocaesium discharges to the Irish Sea

    International Nuclear Information System (INIS)

    Hunt, G.J.

    1984-01-01

    Radiocaesium discharges to the Irish Sea, which primarily originate from corrosion of magnox fuel in the Sellafield storage ponds, are a source of public radiation exposure mainly through the fish and shellfish consumption pathway. Experience of ALARA in the context of reducing these discharges is described. The operators, British Nuclear Fuels Limited (BNFL), in consultation with Government Departments, decided to install an ion exchange plant to remove radioactivity from pond effluents. This plant is scheduled for commissioning in 1984 and optimisation will play a major part in determining its operating regime. Meanwhile, measures have been taken to reduce discharges using skips of zeolite installed in the ponds. Experience of ALARA in determining the optimum replacement rate of skips is described. A major consideration was differential cost-benefit analysis. Following installation of skips at the rate thereby indicated, discharges are being reduced by about half. A further major reduction is expected when the ion exchange plant becomes available. (author)

  3. International co-operation in the supply of nuclear fuel cycle services

    International Nuclear Information System (INIS)

    Allday, C.

    1977-01-01

    The paper draws on B.N.F.L.'s wide experience of international collaboration in nuclear fuel process activities to examine the pros and cons of international agreements. Initially, the factors that influence the need to co-operate, the extent of possible co-operation and the alternative types of agreement are reviewed. Next, the benefits, problems and risks associated with each function, such as managmenet, financial, R and D, marketing and operations that could be covered within the scope of an international agreement, are examined in detail. The paper continues by calling upon specific experience obtained by B.N.F.L. in co-operation with other organisations over several years in operating both major and much smaller agreements illustrating the rationale behind the co-operation, the resolution of 'teething' troubles and the current status of these organisations. In conclusion, the paper comments upon the effectiveness of collaboration agreements and identifies several requirements for internation co-operation to succeed

  4. Knitmesh And Duplex-Nylon Type Coalescence Aids Use In Phase Disengagement

    Directory of Open Access Journals (Sweden)

    Hamit Topuz

    2017-10-01

    Full Text Available This study shows how dispersions consisted of droplet sizes ranging from 100 microns and above of immiscible liquids in agitated vessels coalesced and settled back to their phases by employing commercially known as knit-mesh made from stainless steel and nylon. These components known as higher surface energy and lower surface energy contained coalesce aids respectively. In addition to compare coalesce aid made purely from commercially known as duplex-nylon also used. The experimental set up was 13 scale of a single stage mixer-settler unit of the already existing unit which was in use at BNFL Springfield Works. The liquid liquid system made from 20 tri-butyl-phosphate TBP technical grade of odorless kerosene forming the light organic phase or solvent phase and 5 M nitric acid forming the heavy aqueous phase. The solvent phase contained 70 gram of uranium per liter. Uranium contained phase was supplied by above mentioned company.

  5. Developments in shielding and criticality assessment for cask design

    International Nuclear Information System (INIS)

    Watmough, M.H.; Cooper, A.J.; Croxford, R.W.

    1993-01-01

    This paper presents recent highlights from the shielding and criticality methods development programme that are of relevance to cask design. Specifically, the following points emerge: 1) the preparation of a licence application based upon UK methods and data used in a standardized fissile depletion and plutonium production model has been completed; 2) the assumptions used in the modelling of granules of broken fuel within the transport package following a postulated impact accident have been revised thereby allowing less pessimistic assessments to be performed; 3) enhancements are being made to the software used for shielding and criticality analysis enabling a more cost effective design service to be provided. These ongoing developments clearly show the activity to extend the scope of assessments while increasing the physical realism of the models. Through these developments BNFL continues to offer a comprehensive and cost effective shielding and criticality analysis service as part of its worldwide fuel transport business. (J.P.N.)

  6. 15 years return transport of vitrified high-level waste from France. The long way from La Hague to Gorleben

    International Nuclear Information System (INIS)

    Horn, Thomas

    2012-01-01

    The operators of German nuclear power plants have contracts since 1977 with the French company AREVA NC (former COGEMA) and since 1980 with the British company NDA (former BNFL) for reprocessing of spent nuclear fuel. Since July 2005 the delivery of irradiated fuel element into a reprocessing plant is prohibited. Until 2005 fuel elements with about 6.080 tSM were shipped abroad, about 5.309 tSM to France. The contribution deals with the history of the transports from La Hague to Gorleben, including the contamination problems in 1988 that caused restrictions by the German authorities. A catalogue of safety requirements had to be fulfilled for the allowance of further return transports. The development of appropriate transport casks to cope with changing heat generation of the high-level waste is described. During the complete transport cycle extensive radiological measurements were performed. By the end of 2011 the HAW (high-level waste) glass coquilles were completely returned to Gorleben.

  7. Calibrating the input accountancy tanks on THORP

    International Nuclear Information System (INIS)

    Whyte, C.G.; Hillier, A.P.; Temple, A.

    1995-01-01

    BNFL's Thermal Oxide Reprocessing Plant (THORP), at Sellafield in the UK, processes oxide fuels from customers around the world. The fuel moves through the plant from shearing and dissolution in the Head End and subsequently to solvent extraction in the Chemical Plant. Clarified dissolver liquor is accumulated in three large buffer storage tanks (each of approximately 75 m 3 capacity), in the Head End prior to feeding to the Chemical Plant. The amount of dissolver liquor being passed to these tanks is accurately measured in one of two Input Accountancy Tanks, which are each of 23 m 3 working capacity, and are equipped with high accuracy weight and level measurement systems. Several papers have been published which describe the principles applied to achieve the Safeguarding of THORP. This paper describes the setting to work of a key measurement point in the THORP process and details the complex trials that were begun during the early commissioning phases, to ensure that these accountancy systems would eventually be fully characterized

  8. Radioactive waste discharges from UKAEA establishments during 1996 and associated monitoring results

    International Nuclear Information System (INIS)

    Morton, A.K.M.; Forbes, S.A.; Hughes, B.; Richardson, E.

    1997-08-01

    This annual report is published by the Safety Directorate of the United Kingdom Atomic Energy Authority (UKAEA) and provides information on radioactive discharges from its sites. The Culcheth site was closed and then redeveloped during the end of 1993 and the Springfields site became part of BNFL in October 1994. No operations involving the need to discharge radioactivity are undertaken at the Risley site. After discussions with the Authorising Departments at that time, the discharge authorisations were revoked on 1 July 1994. These sites are therefore no longer included in this report. UKAEA has published annual radioactive waste discharges and associated monitoring results since 1963. This report is intended to give a relatively short factual overview of UKAEA waste discharge and disposal, and its impact on the environment. Additional information may be found in annual discharge reports published by the individual UKAEA establishments and the UKAEA Report on Safety and the Environment 1996-97 due to be issued at the end of September 1997. (UK)

  9. Partnership for success: solving the problems together

    International Nuclear Information System (INIS)

    Ion, S.E.

    2000-01-01

    First is detailed the situation of nuclear industry in United Kingdom and also the authority and its links with the research laboratories and universities. Then the question of knowledge is tackled. The situation in nuclear courses has remained at least constant but one deplores that the number of undergraduates has fallen. Once employed people need training. At BNFL, like the other UK nuclear companies, training is designed for both graduates and experienced staff with the aim of increasing the competence of the trainees in their specific functions within the Company as well as supporting continuous professional development. While training can provide good personnel for a daily operation of nuclear facilities, research and development needs graduates well educated both in depth and in breadth from nuclear programmes.By working in partnership, nation to nation, industry with academia, industry with the regulator, we have a chance of reversing what otherwise must be a very worrying trend in order to maintain a high level nuclear education. (N.C.)

  10. Nested, fixed-depth fluidic sampler supplementary testing - AEAT doc 2926-2-002

    Energy Technology Data Exchange (ETDEWEB)

    REICH, F.R.

    1999-03-11

    This report summarizes the results of cold testing, completed by AEAT, as part of the proof-of-principle testing for a proposed nested, fixed-depth fluidic sampling system. This sampling system will provide waste samples from the PHMC feed tank to support the privatization contract with BNFL. Proof-of-principle tests were completed with 2 wt% and 10 wt% sand/water and 25 wt% kaolin clay/water simulants with a test setup that spanned the 24 ft to 57 ft height required in the feed tank. The tests demonstrated that the system could pump and sample waste materials with low and with high solids content. In addition, the tests demonstrated a need for some design upgrades to the sampling system, as there was material loss when the sample bottle was removed from the sampling needle. These were complementary tests, completed as part of an EM-50 Tank Focus Area (TFA) to develop a sampling system for validating LAW and HLW waste batches for the Privatization Contract.

  11. 15 years return transport of vitrified high-level waste from France. The long way from La Hague to Gorleben; 15 Jahre Rueckfuehrung von verglasten hochaktiven Abfaellen aus Frankreich. Der lange Weg von La Hague nach Gorleben

    Energy Technology Data Exchange (ETDEWEB)

    Horn, Thomas [GNS Gesellschaft fuer Nuklear Service mbH, Essen (Germany)

    2012-11-01

    The operators of German nuclear power plants have contracts since 1977 with the French company AREVA NC (former COGEMA) and since 1980 with the British company NDA (former BNFL) for reprocessing of spent nuclear fuel. Since July 2005 the delivery of irradiated fuel element into a reprocessing plant is prohibited. Until 2005 fuel elements with about 6.080 tSM were shipped abroad, about 5.309 tSM to France. The contribution deals with the history of the transports from La Hague to Gorleben, including the contamination problems in 1988 that caused restrictions by the German authorities. A catalogue of safety requirements had to be fulfilled for the allowance of further return transports. The development of appropriate transport casks to cope with changing heat generation of the high-level waste is described. During the complete transport cycle extensive radiological measurements were performed. By the end of 2011 the HAW (high-level waste) glass coquilles were completely returned to Gorleben.

  12. Safety criteria for nuclear chemical plants

    International Nuclear Information System (INIS)

    Ball, P.W.; Curtis, L.M.

    1983-01-01

    Safety measures have always been required to limit the hazards due to accidental release of radioactive substances from nuclear power plants and chemical plants. The risk associated with the discharge of radioactive substances during normal operation has also to be kept acceptably low. BNFL (British Nuclear Fuels Ltd.) are developing risk criteria as targets for safe plant design and operation. The numerical values derived are compared with these criteria to see if plants are 'acceptably safe'. However, the criteria are not mandatory and may be exceeded if this can be justified. The risk assessments are subject to independent review and audit. The Nuclear Installations Inspectorate also has to pass the plants as safe. The assessment principles it uses are stated. The development of risk criteria for a multiplant site (nuclear chemical plants tend to be sited with many others which are related functionally) is discussed. This covers individual members of the general public, societal risks, risks to the workforce and external hazards. (U.K.)

  13. Statement of nuclear incidents at nuclear installations

    International Nuclear Information System (INIS)

    1993-10-01

    Three incidents were reported in April-June 1993. The first was on the British Nuclear Fuel plc (BNFL) site at Sellafield and concerned leakage of 0.5 TBq of alpha activity from plutonium contaminated waste stored in a steel drum. This was subsequently double contained and moved so it could be inspected regularly. No contamination of personnel occurred. The second concerned the leakage of thorium liquor from a pipe at the UKAEA's Thorium reprocessing plant at Dounreay. Two temporary repairs were made and no personnel were contaminated. The third was at the Sellafield site where a small quantity (5 mls) of plutonium containing liquor had leaked from a package and released alpha activity. The bags were temporary containment of engineering debris which may have had sharp edges. The bags had been piled up and one of the bags had torn. Recommendations were made following inquiries into each of the incidents to improve procedures and prevent similar incidents occurring. (UK)

  14. Technocrats and nuclear politics. The influence of professional experts in policy-making

    International Nuclear Information System (INIS)

    Massey, Andrew

    1988-01-01

    The role of technical experts, especially scientists and engineers, in the development of Britain's civil nuclear energy policy is analysed. It is proposed that civil initiatives came from the integration of technical professions within the bureaucracy of government and quasi-governmental organisations involved in the formulation and implementation of policy. Organisational logic and professional motivation encouraged policies which would lead to occupational autonomy. The first three chapters develop the concept of technical professionalism, Chapters 4-7 then focus on the technocrat's role in providing a spur from their positions within the policy community's bureaucracies that drives top-level policy decisions. These functions are examined in more detail using two case studies, the first concerned with the evolution of British Nuclear Fuels Ltd., the second with the Inquiry (in 1977) into the proposal by BNFL to extend its Windscale site (now known as Sellafield) to build the Thermal Oxide Reprocessing Plant. (U.K.)

  15. Proceedings of the Topical Meeting on the safety of nuclear fuel cycle intermediate storage facilities

    International Nuclear Information System (INIS)

    1998-01-01

    The CSNI Working Group on Fuel Cycle Safety held an International Topical Meeting on safety aspects of Intermediate Storage Facilities in Newby Bridge, England, from 28 to 30 October 1997. The main purpose of the meeting was to provide a forum for the exchange of information on the technical issues on the safety of nuclear fuel cycle facilities (intermediate storage). Titles of the papers are: An international view on the safety challenges to interim storage of spent fuel. Interim storage of intermediate and high-level waste in Belgium: a description and safety aspects. Encapsulated intermediate level waste product stores at Sellafield. Safety of interim storage facilities of spent fuel: the international dimension and the IAEA's activities. Reprocessing of irradiated fuel and radwaste conditioning at Belgoprocess site: an overview. Retrieval of wastes from interim storage silos at Sellafield. Outline of the fire and explosion of the bituminization facility and the activities of the investigation committee (STAIJAERI). The fire and explosion incident of the bituminization facility and the lessons learned from the incident. Study on the scenario of the fire incident and related analysis. Study on the scenario of the explosion incident and related analysis. Accident investigation board report on the May 14, 1997 chemical explosion at the plutonium reclamation facility, Hanford site, Richland, Washington. Dry interim storage of spent nuclear fuel elements in Germany. Safe and effective system for the bulk receipt and storage of light water reactor fuel prior to reprocessing. Receiving and storage of glass canisters at vitrified waste storage center of Japan Nuclear Fuel Ltd. Design and operational experience of dry cask storage systems. Sellafield MOX plant; Plant safety design (BNFL). The assessment of fault studies for intermediate term waste storage facilities within the UK nuclear regulatory regime. Non-active and active commissioning of the thermal oxide

  16. The behaviour of radiocaesium in woodland ecosystems. Measurement and modelling

    International Nuclear Information System (INIS)

    Toal, M.

    1999-02-01

    In order to better quantify risk to non-human biota from environmental radioactivity, our understanding of the behaviour of radionuclides in the biosphere needs to be increased. Hence the aims of the present study were threefold: 1) Review Ecological Risk Assessment (ERA) methodologies, 2) Quantify radiocaesium distribution in woodland biota in the vicinity of BNFL Sellafield, 3) Use this information to develop radiocaesium food-chain and dosimetry models for terrestrial invertebrates and small-mammals. A review of ERA literature concluded that of the two main methodologies available (individual receptor and holistic ERA), individual receptor based analysis is the most credible method given in today's level of scientific understanding. lt was also concluded that the use of modelling techniques in ERA will increase in future years. Two study sites were sampled, a Picea sitchensis monoculture (Lady Wood) and a mixed deciduous site (Longrigg Wood). Mean levels of Cs-137 (all activities quoted in Bq/kg dry weight) in soils:leaf litter were 473:408 (Lady Wood) and 142:32 (Longrigg Wood). The activity of understorey vegetation varied with ranges of 17-508 and 4-48 Bq/kg in Lady Wood and Longrigg, respectively. No vegetation species had concentration ratios (CRs) > 1. The greatest range in Cs-137 activity (2-5242 Bq/kg DW, Lady Wood) was found in fungi, with Mycena galariculata and Hypholoma fasciculare attaining the highest biomagnifications (CRs = 2.6, 2.0 respectively). Due to radioanalytical constraints, only 'mixed invertebrate' samples were measured for Longrigg Wood (yearly average = 8.5 Bq/kg). No significant invertebrate body-burden differences were found between taxa or between seasons for each invertebrate group in Lady Wood. Mean yearly Cs-137 body-burdens (Bq/kg DW) were 94 (Diplopoda), 104 (Isopoda), 54 (Chilopoda), 120 (Araneae), 91 (Opilionidae) and 41 (Carabidae). No invertebrates had CRs > 1. Seasonal Cs-137 body-burdens were also measured for the

  17. Progress report for 1984/85 from the Waste Treatment and Disposal Working Party covering joint BNFL/DOE funded work

    International Nuclear Information System (INIS)

    Claxton, D.G.S.A.

    1985-01-01

    The progress report from the waste treatment and disposal working party is concerned with the management of intermediate-level radioactive waste arising from dismantled fuel assemblies, cladding removed from fuel cans, sludges from fuel cladding corrosion, flocs from liquid waste, ion exchange resins and solid wastes generated during reprocessing. It is proposed that these wastes be incorporated in a matrix for safe transport, storage and disposal and the objectives of the study are to evaluate waste products arising from the treatment of ILWS and to develop techniques to check the quality of the finished waste product. (UK)

  18. Progress report for 1983/84 from the Waste Treatment and Disposal Working Party covering joint BNFL/DOE funded work

    International Nuclear Information System (INIS)

    Higson, S.G.

    1984-01-01

    The subject is covered in paragraphs: introduction (arisings of intermediate-level radioactive waste); organisation and role of the Waste Treatment and Disposal Working Party; main objectives (to provide data on intermediate-level waste treatment systems and allow assessment of alternative processes); ILW process and flowsheeting studies; ILW product evaluation. (U.K.)

  19. EDRP public local inquiry, UKAEA/BNFL precognition on: The transport of the plutonium and uranium products from the EDRP

    International Nuclear Information System (INIS)

    Wilson, P.W.

    1986-02-01

    Details are given of the design of a container for plutonium transport. The handling of the containers, and their transport, from the proposed EDRP at Dounreay, including security and emergency arrangements, are described. The arrangements for the transport of depleted uranium are briefly outlined. (UK)

  20. A UK perspective on recycling

    International Nuclear Information System (INIS)

    Williams, T.

    1991-01-01

    The United Kingdom, through the recycling of depleted uranium from Magnox reactors into Advanced Gas-cooled Reactor (AGR) fuel, has already recycled significant quantities of reprocessed material in reactors owned by Nuclear Electric plc and Scottish Nuclear Limited. This AGR fuel has been satisfactorily irradiated and discharged over a decade or more, and will be reprocessed in the new Thermal Oxide Reprocessing Plant (THORP), currently under construction in the UK. British Nuclear Fuels plc (BNFL) and the UK Atomic Energy Authority (UKAEA) have also been exploiting the potential of plutonium recycled in mixed oxide (MOX) fuel, which they have been making since 1963. All of the UK nuclear companies are committed to further recycling of Magnox depleted uranium during the 1990s, and it is anticipated that oxide recycling will also become firmly established during the next decade. British Nuclear Fuels and Urenco Ltd, as the providers of fuel cycle services, are developing an infrastructure to close the fuel cycle for oxide nuclear fuel, using both the uranium and plutonium arising from reprocessing. (author)

  1. Radioactive substances monitoring programme. Report for 1995

    International Nuclear Information System (INIS)

    1995-01-01

    The Radioactive Substances Act 1993 provides for controls to be exercised over the use and keeping of radioactive materials and the accumulation and disposal of radioactive wastes. The Environment Agency (the Agency) has been responsible for administration and enforcement of the Act in England and Wales since its formation on 1 April 1996. Prior to this date the work was undertaken by Her Majesty's Inspectorate of Pollution (HMIP). In support of its regulatory functions HMIP commissioned independent monitoring. This report presents the results from monitoring undertaken in 1995. The 1995 HMIP programme required operators of certain sites to provide samples of their liquid effluents for independent radiochemical analysis. The results provide checks on site operators' returns and insights into their quality assurance (QA) procedures and analytical techniques. The analyses were undertaken by the Laboratory of the Government Chemist (LGC) at its laboratories in Teddington, Middlesex. The programme also included checks on solid low level radioactive waste destined for land disposal at the site operated by British Nuclear Fuels plc (BNFL) at Drigg in Cumbria. (author)

  2. Case law

    International Nuclear Information System (INIS)

    Anon.

    2002-01-01

    Several judgements are carried: Supreme Administrative Court Judgement rejecting an application to prevent construction of a new nuclear power plant (Finland); judgement of the Council of State specifying the law applicable to storage facilities for depleted uranium (France); Supreme Court Decision overturning for foreign spent fuel (Russian federation); Court of Appeal Judgement on government decision to allow the start up of a MOX fuel plant ( United Kingdom); judgement on lawfulness of authorizations granted by the Environment Agency: Marchiori v. the Environment Agency; (U.K.); Kennedy v. Southern California Edison Co. (U.S.A); Judgement concerning Ireland ' s application to prevent operation of BNFL ' s MOX facility at Sellafield: Ireland v. United Kingdom; At the European Court of Human Rights Balmer-Schafroth and others have complained v. Switzerland. Parliamentary decision rescinding the shutdown date for Barseback - 2 (Sweden); Decision of the International trade Commission regarding imposition of countervailing and anti-dumping duties on imports of low enriched uranium from the European Union, Yucca Mountain site recommendation (USA). (N.C.)

  3. Low level tank waste disposal study

    Energy Technology Data Exchange (ETDEWEB)

    Mullally, J.A.

    1994-09-29

    Westinghouse Hanford Company (WHC) contracted a team consisting of Los Alamos Technical Associates (LATA), British Nuclear Fuel Laboratories (BNFL), Southwest Research Institute (SwRI), and TRW through the Tank Waste Remediation System (TWRS) Technical Support Contract to conduct a study on several areas concerning vitrification and disposal of low-level-waste (LLW). The purpose of the study was to investigate how several parameters could be specified to achieve full compliance with regulations. The most restrictive regulation governing this disposal activity is the National Primary Drinking Water Act which sets the limits of exposure to 4 mrem per year for a person drinking two liters of ground water daily. To fully comply, this constraint would be met independently of the passage of time. In addition, another key factor in the investigation was the capability to retrieve the disposed waste during the first 50 years as specified in Department of Energy (DOE) Order 5820.2A. The objective of the project was to develop a strategy for effective long-term disposal of the low-level waste at the Hanford site.

  4. The UK shielding Forum. Best Practice through consensus

    International Nuclear Information System (INIS)

    Hobson, J.; Gunston, K.; Gunston, K.

    2000-01-01

    The UK national shielding Forum has been established to represent all key industry groups in the UK (including the Nuclear Installations Inspectorate (NII), the national regulatory authority). The Forum's aim is to increase awareness and confidence in the range of professional practice within the UK shielding community, with a view to having a coherent and dynamic role within the international shielding community. In the past, no comprehensive representative body covering the whole UK nuclear industry has existed, and the different industry shielding groups have developed local ways of working to address their particular requirements. Inevitably, there are common issues arising from these requirements which benefit from a wider consensus. As a result of the formation of the Forum (initiated by the NII and subsequently chaired by BNFL as an industry key player), expertise, experience and best working practice are now being actively shared between shielding professionals, and there has been a strong and successful drive to achieving consensus on key issues, which is also reflected in the increasing quality of industry-regulator relationships. (author)

  5. Fisheries Research. Report of the Director of Fisheries Research 1981-82

    International Nuclear Information System (INIS)

    1984-01-01

    The Fisheries Research Laboratory, Lowestoft report on extensive programme of environmental monitoring in the region of major liquid radioactive waste discharges at Sellafield, Cardiff, Hartlepool and Heysham. Exposure pathways are identified and a possible increase in radiation exposure from mollusc consumption near Sellafield investigated. The AEP group advise BNFL and the CEGB on the discharge of wastes into the sea and possible effects on the aquatic environment. The distribution in the sea of cesium 137, strontium 90, plutonium 239/240 from Sellafield discharges is investigated. Detailed studies of the oxidation states of the transuranium elements in seawater at different depths have been initiated and compared with oxidation states at the time of discharge. Seabed cores have been analysed to investigate the incorporation of americium and plutonium and their adsorption onto deep sea sediments. The accumulation of radionuclides in algae and lobsters is studied and the effects of different doses arising from radionuclides on the growth of fish populations were investigated. Cytological studies of fish gonads and testes revealed chromosomal aberrations. (U.K.)

  6. Pretreatment status report on the identification and evaluation of alternative processes. Milestone Report No. C064

    Energy Technology Data Exchange (ETDEWEB)

    Sutherland, D.G. [Westinghouse Hanford Co., Richland, WA (United States); Brothers, A.J. [Pacific Northwest Lab., Richland, WA (United States); Beary, M.M.; Nicholson, G.A. [Science Applications International Corp., San Diego, CA (United States)

    1993-09-01

    The purpose of this report is to support the development and demonstration of a pretreatment system that will (1) destroy organic materials and ferrocyanide in tank wastes so that the wastes can be stored safely, (2) separate the high-activity and low-activity fractions, (3) remove radionuclides and remove or destroy hazardous chemicals in LLW as necessary to meet waste form feed requirements, (4) support development and demonstration of vitrification technology by providing representative feeds to the bench-scale glass melter, (5) support full-scale HLW vitrification operations, including near-term operation, by providing feed that meets specifications, and (6) design and develop pretreatment processes that accomplish the above objectives and ensure compliance with environmental regulations. This report is a presentation of candidate technologies for pretreatment of Hanford Site tank waste. Included are descriptions of studies by the Pacific Northwest Laboratory of Battelle Memorial Institute; Science Applications International Corporation, an independent consultant; BNFL, Inc. representing British technologies; Numatec, representing French technologies; and brief accounts of other relevant activities.

  7. Barrow hazards survey

    International Nuclear Information System (INIS)

    1980-06-01

    Following a series of public meetings at which PERG presented the results of a literature review and site specific accident study of the hazards of the maritime transport of spent nuclear reactor fuel to Barrow (en route to the Windscale reprocessing works), PERG was requested by the Planning Committee of Barrow Town Council to prepare an assessment of the interaction of the hazards arising from the concentration of nuclear activities in the area with those of a proposed gas-terminal. This report presents a preliminary review of the Environmental Impact Assessments prepared by the Borough Surveyor and a critical appraisal of the hazard analyses undertaken by the Health and Safety Executive, and the consultants to Cumbria County Council on this matter, the Safety and Reliability Directorate of the United Kingdom Atomic Energy Authority. After a general and historical introduction, the document continues under the following headings: a description of the hazards (BNFL spent fuel shipments; the gas terminal; gas condensate storage; the Vickers shipyard (involving nuclear powered submarines)); the interaction of hazards; planning implications and democratic decisions; recommendations. (U.K.)

  8. Pretreatment status report on the identification and evaluation of alternative processes

    International Nuclear Information System (INIS)

    Sutherland, D.G.; Brothers, A.J.; Beary, M.M.; Nicholson, G.A.

    1993-09-01

    The purpose of this report is to support the development and demonstration of a pretreatment system that will (1) destroy organic materials and ferrocyanide in tank wastes so that the wastes can be stored safely, (2) separate the high-activity and low-activity fractions, (3) remove radionuclides and remove or destroy hazardous chemicals in LLW as necessary to meet waste form feed requirements, (4) support development and demonstration of vitrification technology by providing representative feeds to the bench-scale glass melter, (5) support full-scale HLW vitrification operations, including near-term operation, by providing feed that meets specifications, and (6) design and develop pretreatment processes that accomplish the above objectives and ensure compliance with environmental regulations. This report is a presentation of candidate technologies for pretreatment of Hanford Site tank waste. Included are descriptions of studies by the Pacific Northwest Laboratory of Battelle Memorial Institute; Science Applications International Corporation, an independent consultant; BNFL, Inc. representing British technologies; Numatec, representing French technologies; and brief accounts of other relevant activities

  9. THORP steps up the concrete action

    International Nuclear Information System (INIS)

    Hayward, D.

    1987-01-01

    The construction of the THORP reprocessing plant at the BNFL Sellafield site is complex and made more so by design modifications. Over 100 huge concrete cells, each enclosed by heavily reinforced 1.5m thick walls will eventually be clad in metal sheeting to make one vast long building 285m long and 50m tall. The quality assurance tolerances required are tight. Currently the building is behind schedule so the construction is now going throughout the night as well as the day. As well as the demands made by building complexities the requirements of nuclear engineering must be met. Also, this is the first building in the UK which will have to comply with the Nuclear Installations Inspectorate demands for seismic safety. An idea of the scale of the building in the UK which will have to comply with the Nuclear Installations Inspectorate demands for seismic safety. An idea of the scale of the building, the logistical problems, their solutions and the timescale of the construction are given. (UK)

  10. Annual report and accounts 1991/92

    International Nuclear Information System (INIS)

    1992-01-01

    The primary objective of British Nuclear Fuels plc (BNFL) is to supply a safe and efficient nuclear fuel cycle service. Springfields near Preston is the site of our fuel manufacturing operations, while Capenhurst near Chester is responsible for uranium enrichment. We reprocess irradiated nuclear fuel at Sellafield in West Cumbria, the site also of our multi-million pound investment programme which includes the Thermal Oxide Reprocessing Plant (THORP) and a range of facilities for the treatment and storage of waste produced during reprocessing operations. We also operate two nuclear power stations -Calder Hall on the Sellafield site and Chapelcross in Southern Scotland. Risley in Cheshire is the focus for our engineering design activities and the Company's Central Services Unit. The Head Office is also based at Risley. Fuel cycle services associated with the production of nuclear-generated electricity accounts for around 90% of our work. The report includes the chairman's review of the year, the Chief Executive's Report and summaries of the activities of the UK Group, International Group, Engineering Group and the Central Services Unit. The accounts are presented. (author)

  11. 5 steps to delivering safe, secure and reliable rail solutions for the nuclear industry

    Energy Technology Data Exchange (ETDEWEB)

    Connelly, C. [Direct Rail Services, Warrington (United Kingdom)

    2004-07-01

    Direct Rail Services (DRS) has been operating since October 1995, following the decision by parent company, British Nuclear Fuels (BNFL), to create a strategic rail transport service. The decision came after the privatisation of the rail network in the UK, when the former British Rail was superseded by a range of private organisations responsible for separate areas of the industry. Individual companies became responsible for aspects such as the operation and maintenance of the network infrastructure and for passenger and freight train services. Rather than enter into contractual arrangements with third party contractors, DRS was formed - securing both the access and reliability of transport routes and availability of the rail network, providing greater guarantees about the levels of service delivery. The strategy of bringing this area of transport in house was concurrent with that of international transport, utilising its own fleet of ships for overseas fuel movements. Freight operations began in October 1995, with the first services operating between Sellafield and the low level radioactive waste facility at Drigg.

  12. 5 steps to delivering safe, secure and reliable rail solutions for the nuclear industry

    International Nuclear Information System (INIS)

    Connelly, C.

    2004-01-01

    Direct Rail Services (DRS) has been operating since October 1995, following the decision by parent company, British Nuclear Fuels (BNFL), to create a strategic rail transport service. The decision came after the privatisation of the rail network in the UK, when the former British Rail was superseded by a range of private organisations responsible for separate areas of the industry. Individual companies became responsible for aspects such as the operation and maintenance of the network infrastructure and for passenger and freight train services. Rather than enter into contractual arrangements with third party contractors, DRS was formed - securing both the access and reliability of transport routes and availability of the rail network, providing greater guarantees about the levels of service delivery. The strategy of bringing this area of transport in house was concurrent with that of international transport, utilising its own fleet of ships for overseas fuel movements. Freight operations began in October 1995, with the first services operating between Sellafield and the low level radioactive waste facility at Drigg

  13. Hematite nuclear fuel cycle facility decommissioning

    International Nuclear Information System (INIS)

    Hayes, K.

    2004-01-01

    Westinghouse Electric Company LLC ('Westinghouse') acquired a nuclear fuel processing plant at Hematite, Missouri ('Hematite', the 'Facility', or the 'Plant') in April 2000. The plant has subsequently been closed, and its operations have been relocated to a newer, larger facility. Westinghouse has announced plans to complete its clean-up, decommissioning, and license retirement in a safe, socially responsible, and environmentally sound manner as required by internal policies, as well as those of its parent company, British Nuclear Fuels plc. ('BNFL'). Preliminary investigations have revealed the presence of environmental contamination in various areas of the facility and grounds, including both radioactive contamination and various other substances related to the nuclear fuel processing operations. The disparity in regulatory requirements for radiological and nonradiological contaminants, the variety of historic and recent operations, and the number of previous owners working under various contractual arrangements for both governmental and private concerns has resulted in a complex project. This paper discusses Westinghouse's efforts to develop and implement a comprehensive decontamination and decommissioning (D and D) strategy for the facility and grounds. (author)

  14. R. v. Secretary of State for the Environment and others ex parte Greenpeace Limited and others

    International Nuclear Information System (INIS)

    Potts, J.

    1994-01-01

    When in April 1992, British Nuclear Fuels Limited (BNFL) applied for authorization to discharge radioactive wastes into sea and air as a result of starting to operate its newly constructed thermal oxide reprocessing plant (THORP) at Sellafield Cumbria, a legal challenge to the Secretary of State's authorization was made by Greenpeace Limited, the environmental campaign group, and Lancashire County Council. They sought to show that the Secretary of State for the Environment had acted illegally in granting authority, because it had not been shown that the nuclear waste emission would produce a net benefit to the public, because no public inquiry had been held into whether the economic benefits outweighed the perceived detrimental effects, and because no authorization can occur without an environmental impact assessment to comply with European Community rules. While these points were proved at the judicial review, administrative law principals meant that the decision went against the complainants, but no costs were awarded showing the courts distaste for the judgement it was obliged to make. (UK)

  15. Swedish encapsulation station review

    International Nuclear Information System (INIS)

    Andersson, Sven Olof; Brunzell, P.; Heibel, R.; McCarthy, J.; Pennington, C.; Rusch, C.; Varley, G.

    1998-06-01

    In the Encapsulation Station (ES) Review performed by NAC International, a number of different areas have been studied. The main objectives with the review have been to: Perform an independent review of the cost estimates for the ES presented in SKB's document 'Plan 1996'. This has been made through comparisons between the ES and BNFL's Waste Encapsulation Plant (WEP) at Sellafield as well as with the CLAB facility. Review the location of the ES (at the CLAB site or at the final repository) and its interaction with other parts of the Swedish system for spent fuel management. Review the logistics and plant capacity of the ES. Identify important safety aspects of the ES as a basis for future licensing activities. Based on NAC International's experience of casks for transport and storage of spent fuel, review the basic design of the copper/steel canister and the transport cask. This review insides design, manufacturing, handling and licensing aspects. Perform an overall comparison between the ES project and the CLAB project with the objective to identify major project risks and discuss their mitigation

  16. Radial power density distribution of MOX fuel rods in the IFA-651

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Byung Ho; Koo, Yang Hyun; Joo, Hyung Kook; Cheon, Jin Sik; Oh, Je Yong; Sohn, Dong Seong [Korea Atomic Energy Research Institute, Taejeon (Korea)

    2002-04-01

    Two MOX fuel rods, which were fabricated in the Paul Scherrer Institute (PSI), Switzerland in cooperation with Korea Atomic Energy Research Institute, have been irradiated in the HBWR from June, 2000 in the framework of OECD-HRP together with a reference MOX fuel rod supplied by the BNFL. Since fuel temperature, which is influenced by radial power distribution, is basic in analyzing fuel behavior, it is required to consider radial power distribution in the HBWR. A subroutine FACTOR{sub H}BWR that calculates radial power density distribution for three MOX fuel rods has been developed based on neutron physics results and DEPRESS program. The developed subroutine FACTOR{sub H}BWR gives good agreement with the physics calculation except slight under-prediction at the outer part of the pellet above the burnup of 20 MWd/kgHM. The subroutine will be incorporated into a computer code COSMOS and used to analyze the in-reactor behavior of the three MOX fuel rods during the Halden irradiation test. 24 figs., 4 tabs. (Author)

  17. Remobilisation of artificial radionuclides from the sediment of the Irish Sea

    International Nuclear Information System (INIS)

    Hunt, G.J.; Kershaw, P.J.

    1990-01-01

    The past decade has seen significant decreases in discharges of radioactivity in liquid wastes from the British Nuclear Fuels plc (BNFL) plant at Sellafield. Concentrations of many Sellafield-derived radionuclides in the water of the Irish Sea have decreased as a result. This will result in the return of previously contaminated sediment to the sediment surface and enhanced seawater/pore-water mixing by bio-irrigation, and may be responsible for higher rates of particle exchange across the sediment-seawater interface. In these circumstances, the decrease in seawater concentrations might be expected to be accompanied by the remobilisation of sediment-bound radionuclides into the water column. We have tested this hypothesis in the Sellafield situation in two ways. First, the differences were examined between measured concentrations of radionuclides in sea water and the concentrations which are to be expected on the basis of extrapolation from the conditions of steadier discharge rates experienced in the past. Secondly, modelling studies have shown that migration of radionuclides into the water phase is likely under these conditions. (author)

  18. Fabrication of a CANFLEX-RU designed bundle for power ramp irradiation test in NRU

    International Nuclear Information System (INIS)

    Cho, Moon Sung

    2000-11-01

    The BDL-443 CANFLEX-RU bundle AKW was fabricated at Korea Atomic Energy Research Institute (KAERI) for power ramp irradiation testing in NRU reactor. The bundle was fabricated with IDR and ADU fuel pellets in adjacent elements and contains fuel pellets enriched to 1.65 wt% 235 U in the outer and intermediate rings and also contains pellets enriched to 2.00 wt% 235 U in the inner ring. This bundle does not have a center element to allow for insertion on a hanger bar. KAERI produced the IDR pellets with the IDR-source UO 2 powder supplied by BNFL. ADU pellets were fabricated and supplied by AECL. Bundle kits (Zircaloy-4 end plates, end plugs, and sheaths with brazed appendages) manufactured at KAERI earlier in 1996 were used for the fabrication of the bundle. The CANFLEX bundle was fabricated successfully at KAERI according to the QA provisions specified in references and as per relevant KAERI drawings and technical specification. This report covers the fabrication activities performed at KAERI. Fabrication processes performed at AECL will be documented in a separate report

  19. Radial power density distribution of MOX fuel rods in the HBWR

    International Nuclear Information System (INIS)

    Koo, Yang Hyun; Joo, Hyung Kook; Lee, Byung Ho; Sohn, Dong Seong

    1999-07-01

    Two MOX fuel rods, which ar being fabricated in the Paul Scherrer Institute (PSI), Switzerland in cooperation with the Korea Atomic Energy Research Institute (KAERI), are going to be irradiated in the HBWR (Halden Boiling Water Reactor) from the beginning of 2000 in the framework of OECD Halden Reactor Programme (HRP) together with a reference MOX fuel rod supplied by the BNFL. Since fuel temperature, which is influenced by radial power distribution, is a basic property in analyzing fuel behavior, it is required to consider radial power distribution in the HBWR. A subroutine FACTOR H BWR that calculates radial power density distribution for three MOX fuel rods have been developed subroutine FACTOR H BWR gives good agreement with the physics calculation except slight underprediction in the central part and a little overprediction at the outer part of the pellet. The subroutine will be incorporated into a computer code COSMOS and used to analyze the in-reactor behavior of the three MOX fuel rods during the Halden irradiation test. (author). 5 refs., 3 tabs., 24 figs

  20. Committed to the growth of the NP industry

    International Nuclear Information System (INIS)

    Agnihotri, Newal K.

    2004-01-01

    Mr. Stephen Tritch, President and Chief Executive Officer of Westinghouse Electric Company is responsible for al Westinghouse commercial nuclear operations, including the BNFL fuel business group in the United Kingdom. In this interview, he discusses economic aspects of bringing new power plants online, including waste disposal and investment issues. Also discussed are public relation activities to encourage public acceptance and what is needed from a practical and policy perspective to make new plant development happen in the U.S. Regarding the best available technology, he states that the AP1000 is the advanced nuclear power plant best-suited for new construction programs in the U.S. and elsewhere. It features passive and inherent safety systems, superior economics (3 to 3.5 cents per kilowatt hour) and modular design and construction that will help ensure highly predictable construction timetables. Lastly, Mr. Tritch discusses issues related to where the next generation of nuclear professionals will come from, including the knowledge transfer process, worldwide training standardization, utilizing retired professionals, and encouraging public schools to offer nuclear-based curriculum materials and intern programs