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Architecture and management of a geological repository - Andra

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11 – Operational Safety11.2.2.2 Radiological risksRadiological risks (external exposure risks, internal exposure risk <strong>and</strong> potentially criticality risk) likelyto be encountered during the course <strong>of</strong> the disposal process could be associated with radiologicalprotection failures, interventions carried out close to a source <strong>of</strong> radioactivity or a fire or fall affectingwaste packages.Having taken account <strong>of</strong> their specific characteristics, these risks are analysed individually <strong>and</strong>emphasis is placed on measures to reduce the risks envisaged.• Failure <strong>of</strong> the radiological protection provided by the doors, vents <strong>and</strong> shieldedwindows <strong>of</strong> nuclear cells in surface installations, transfer transfer casks, accessports <strong>of</strong> the C <strong>and</strong> spent fuel disposal cells <strong>and</strong> doors <strong>of</strong> the B disposal cellsThese events could be the result, for example, <strong>of</strong> clearance between moving parts that is not compliantwith the initial dimensioning. Measures required to counter this risk would be a specific maintenanceprogramme for moving parts associated with radiation detection monitoring <strong>of</strong> the nuclear cells,transfer transfer casks <strong>and</strong> disposal cells.• Failure <strong>of</strong> radiological protection during the course <strong>of</strong> an interventionEquipment malfunction may lead to its immobilisation when being used to carry or h<strong>and</strong>le a package(primary package or disposal package) <strong>and</strong> intervention by maintenance personnel may be required torepair the equipment in question. This situation would result in the external exposure <strong>of</strong> personnel ifthe latter had to operate near the source <strong>of</strong> radiation.Preventive measures would be those conventionally used in nuclear facilities currently in operation,namely, appropriate maintenance <strong>of</strong> the equipment used <strong>and</strong> redundancy <strong>of</strong> certain component parts(motorisation, etc.).Where intervention carried out on equipment in cells is concerned, the existence <strong>of</strong> emergencysystems enabling the waste package to be put down <strong>and</strong> the equipment returned unloaded to itsmaintenance area would remove all risk <strong>of</strong> the exposure <strong>of</strong> personnel. In the latter case, it would,however, be necessary to ensure there is no malfunction <strong>of</strong> the closure system <strong>of</strong> the irradiating zone<strong>of</strong> the cell 156 by first monitoring the level <strong>of</strong> radiation in the maintenance area prior to any operation.• Fire in a nuclear cell <strong>of</strong> the surface installationsA fire in the disposal package manufacturing cell would have a fairly insignificant heat rating giventhe low calorific load <strong>of</strong> the equipment installed.Taking feedback from the experience <strong>of</strong> nuclear facilities into account in the design <strong>of</strong> installations,limiting the calorific loads present <strong>and</strong> possibly installing thermal protections around some equipmentshould be sufficient to limit the power <strong>of</strong> a fire <strong>and</strong> prevent it from spreading <strong>and</strong> affecting thepackages resulting in radiological consequences.• Waste transportation or h<strong>and</strong>ling vehicle fireThe fire <strong>of</strong> a transport transfer cask vehicle (containing primary packages from waste producers), atransfer transfer cask vehicle (containing waste disposal packages) or B waste emplacement equipmentin the disposal cell could have radiological consequences in addition to the direct consequences <strong>of</strong> thefire (cf. Section 11.4).156 The system usually employed consists <strong>of</strong> locking in the opening <strong>of</strong> the maintenance area with the closure <strong>of</strong> the irradiating cell <strong>and</strong>, ifpossible, locating the maintenance area at some distance from a potential field <strong>of</strong> radiation from the sources <strong>of</strong> radioactivity present inthe cell.DOSSIER 2005 ARGILE -ARCHITECTURE AND MANAGEMENT OF A GEOLOGICAL DISPOSAL SYSTEM446/495

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