Objective The theoretical work is composed of 2 distinct but complementary studies: a) Waste management options: The theoretical study continues to develop an existing methodology to aid decommissioning waste management decisions, and to demonstrate the improved methodology by applying it to the prototype AGR Windscale reactor decommissioning waste for which the final management option has not yet been chosen. The main extension to the existing methodology (see final report on contract FI1D0051) is to enable the incorporation of risks and uncertainties, rather than simply doses and environmental impact parameters. The improved methodology, like the existing one, will be applicable to decisions concerning the decommissioning of all types of nuclear reactors and could lead to reductions in radiation risks and financial costs, as well as promoting consistency between the approaches in various countries; b) Decommissioning strategies: The work will aim at developing a comprehensive methodology to evaluate radiological risks to the public and workers from decommissioning of non-reactor nuclear plants. Such a methodology will allow the comparison of different decommissioning strategies from a risk point of view so that the benefits associated with, for example, delay in decommissioning to more advanced stages could be assessed.The theoretical work is composed of two distinct but complementary studies:Waste management options: The theoretical study continues to develop an existing methodology to aid decommissioning waste management decisions, and to demonstrate the improved methodology by applying it to the prototype Windscale advanced gas cooled reactor (AGR) decommissioning waste for which the final management option has not yet been chosen. The main extension to the existing methodology is to enable the incorporation of risks and uncertainties, rather than simply doses and environmental impact parameters.Decommissioning strategies: The work will aim at developing a comprehensive methodology to evaluate radiological risks to the public and workers from decommissioning of nonreactor nuclear plants.Substantial progress has been made on the development of a methodology for evaluating risks; however, some of the work will not be finalised until the demonstration of methodology is underway. The identification of waste stream has been completed and the definition of waste inventory and the definition of waste management options are close to completion, subject to further data requirements as other tasks proceed. Work on the estimation of financial costs is underway, but cost estimates have not been finalised.The definition of decommissioning phases is complete. The identification of decommissioning techniques is ongoing; new data on dismantling and decontamination methods and their associated resuspension factors are being collected as they become available. The identification of risk assessment procedures, the evaluation of risk assessment procedures and risk aggregation are nearly complete. Work is well advanced on methodology application.WORK PROGRAMME 1.a. Development of a radiological risk evaluation methodology (NRPB) considering the uncertainties in models and modelling parameters. 2.a. Selection of the waste stream for an example application of the methodology (AEA) 3.a. Definition of the radionuclides inventory and their distribution in the selected waste stream. (AEA) 4.a. Definition of waste management options (AEA) 5.a. Estimation of financial costs for each of the management options. (AEA) 6.a. Calculation of doses and risks for individuals and the public. (NRPB) 7.a. Assessment of social and environmental impacts of waste management options. (NRPB) 8.a. Demonstration of the methodology by identifying the optimal management options. (NRPB) 9.a. Review of the results and check of their applicability to other decommissioning decisions. (all) 1.b. Definition of decommissioning phases of non-reactor nuclear plants. (AEA-Culcheth for the entire b-study) 2.b. Identification of techniques for carrying out decommissioning operations and their risk-bearing elements. 3.b. Identification of risk assessment procedures taking into account normal and possible accidental risks. 4.b. Evaluation of procedures for assessing the risks associated with leaving the plant under care and maintenance; 5.b. Examination of methods for the aggregation of risks associated with particular decommissioning strategies. 6.b. Demonstration of the identified methodologies to a non-reactor facility. 7.b. Final evaluation on the suitability and limitations of the identified methodologies. Fields of science engineering and technologyother engineering and technologiesnuclear engineeringnatural scienceschemical sciencesnuclear chemistryradiation chemistry Programme(s) FP2-DECOM 3C - Specific research and technological development programme (Euratom) in the field of decommissioning of nuclear installations, 1989-1993 Topic(s) A6 - Estimation of radioactive waste quantities arising from decommissioning Call for proposal Data not available Funding Scheme CSC - Cost-sharing contracts Coordinator AEA Technology plc EU contribution No data Address Culcheth Laboratory Wighsaw Lane WA3 4NE Warrington United Kingdom See on map Total cost No data Participants (2) Sort alphabetically Sort by EU Contribution Expand all Collapse all NATIONAL RADIOLOGICAL PROTECTION BOARD United Kingdom EU contribution No data Address OX11 0RQ DIDCOT,HARWELL,CHILTON See on map Total cost No data United Kingdom Atomic Energy Authority (UKAEA) United Kingdom EU contribution No data Address Sellafield Laboratory CA20 1PF Seascale See on map Total cost No data
