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Architecture and management of a geological repository - Andra

Architecture and management of a geological repository - Andra

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11 – Operational Safety11.7.1.3 Consequences <strong>of</strong> a cage falling in a shaftAfter an analysis <strong>of</strong> the fall’s energy balance, the primary package’s condition is examined to find outwhether the damages caused by the fall on the shock absorber are or aren’t liable to be evidenced inthe end by a loss <strong>of</strong> containment <strong>and</strong> a release <strong>of</strong> radionuclides.• Energy balanceThe energy balance illustrated by the fall <strong>of</strong> the C waste transfer cask (cf. Figure 11.7.2) shows thatthe largest part <strong>of</strong> the incident kinetic energy was transformed during the impact into internaldeformation energy in a very short time.800700600Global energy balance7%Breakdown <strong>of</strong> energy absorbedduring the fallEnergy (MJ)5004003002001000Kinetic energyAbsorbed energy0 20 40 60 80 100 120Time (ms)53%40%SHOCK ABSORBERCAGECASK + PACKAGEFigure 11.7.2Energy balance <strong>of</strong> a fall in a shaft <strong>of</strong> a cage transporting a transfer cask with CwastesMore than 99 % <strong>of</strong> the shock’s energy is absorbed by the shock absorber, the cage <strong>and</strong> the transfercask. The disposal package absorbs less than 1 % <strong>of</strong> the energy. This distribution remains valid for thefalls <strong>of</strong> B waste <strong>and</strong> spent fuel packages.• Mechanical consequences <strong>of</strong> the fall on the primary waste packagesThe estimation <strong>of</strong> the deformations observed on the primary packages allows underst<strong>and</strong>ing the risk <strong>of</strong>a loss <strong>of</strong> containment <strong>of</strong> radioactive materials through the following two elements <strong>of</strong> estimation:- The maximum value <strong>of</strong> the deformation coefficient <strong>of</strong> the primary package, which is only anindication (because a high deformation value limited to a few mesh elements is not significant),- The surface <strong>of</strong> the primary package for which the deformation coefficient is greater than theacceptable characteristic value (ACV), which means a risk <strong>of</strong> breakage.The results <strong>of</strong> the simulations (cf. Table 11.7.2) show that for all the B, C <strong>and</strong> spent fuel packagesthere isn’t any risk <strong>of</strong> loss <strong>of</strong> containment <strong>of</strong> the radioactive materials since no deformation value isgreater than the ACV <strong>of</strong> the materials making up the primary package. However, it should be notedthat the B waste packages are the primary packages which undergo the greatest deformations <strong>and</strong> therepersists an uncertainty particularly for the type B2 waste packages on the behaviour <strong>of</strong> their crimpedlid to the shock.DOSSIER 2005 ARGILE -ARCHITECTURE AND MANAGEMENT OF A GEOLOGICAL DISPOSAL SYSTEM474/495

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