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Architecture and management of a geological repository - Andra

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2 – General DescriptionHLLL waste packages are usually divided into the following categories, each with its own disposalissues (or questions):- Class B waste has low to medium β-γ activity <strong>and</strong> therefore releases little or no heat. It regroupsthe longest number <strong>of</strong> waste. Their total radioisotope inventory is relatively small compared toother packages waste, <strong>and</strong> is distributed over a large volume.- Class C waste consists <strong>of</strong> fission products <strong>and</strong> minor actinides separated out during fuelreprocessing. Their high β-γ activity causes considerable heat release, which declines over timemainly due to the radioactive decay <strong>of</strong> the medium-lived fission products (cesium-137, strontium-90). This waste is conditioned by incorporating it in a glass matrix. Glass has a particularly high<strong>and</strong> long-lasting confinement capacity provided the physical-chemical properties <strong>of</strong> theenvironment are favourable. Because <strong>of</strong> the high concentration <strong>of</strong> long-lived radionuclides invitrified C waste packages, the high temperature <strong>and</strong> the physical-chemical behaviour <strong>of</strong> theimmobilisation material, disposal conditions need to be specially adapted. Existing <strong>and</strong> possiblefuture C packages are divided into sub-groups C0, C1, C2, C3 <strong>and</strong> C4 depending on theircomposition. C0 (old waste such as that stored at the Marcoule site) is markedly less exothermicthan the others.Spent fuel is also highly radioactive <strong>and</strong> therefore releases considerable heat. This is due to thepresence <strong>of</strong> fission products having average half-lives, as well as that <strong>of</strong> plutonium <strong>and</strong> americium(stemming mainly from plutonium decay), in the bother two responsible for a slower decline if heatrelease. Other features are the large size <strong>of</strong> fuel rods unloaded from nuclear power reactors if they areto be disposed <strong>of</strong> as they are, <strong>and</strong> a larger amount <strong>of</strong> fissile products, raising the question <strong>of</strong> criticalityrisk. There are two types <strong>of</strong> commercial spent fuel, CU1 (UOX fuel) <strong>and</strong> CU2 (MOX fuel) which arehighly exothermic. Fuel that might come from research <strong>and</strong> defence reactors (CU3 type fuel) areconsiderably less exothermic.Chapter 3 gives a more detailed description <strong>of</strong> primary HLLL waste packages, their radiologicalcontent, heat release <strong>and</strong> physical-chemical properties.In each <strong>of</strong> the above waste classes, the different families <strong>of</strong> HLLL wate packages have been groupedinto a smaller number <strong>of</strong> representative "waste package types". This is in order (i) to make a morethorough study by limiting the number <strong>of</strong> cases to be specifically addressed, while not ignoring thediversity <strong>of</strong> the packages, (ii) to propose as far as possible a st<strong>and</strong>ardisation <strong>of</strong> the engineeredstructures <strong>and</strong> means employed in a disposal facility. Using this approach it is possible to study adisposal solution for each package inventoried, irrespective <strong>of</strong> whether other types <strong>of</strong> waste are beingdisposed <strong>of</strong>.2.2 Functions <strong>of</strong> a reversible disposal facilityThe functions <strong>of</strong> a <strong>repository</strong> have been identified by a functional analysis perfomed by conventionalmethods [4]. This ensures that all expected functions are taken into account.The basic purpose <strong>of</strong> long-term <strong>management</strong> <strong>of</strong> high-level, long-lived waste (HLLL waste) is toprotect human health <strong>and</strong> the environment against the associated risks. The solution <strong>of</strong>fered by a<strong>repository</strong> is to confine the waste to the <strong>geological</strong> formation studied. The waste is passively confinedfor a long period <strong>of</strong> time; periods studied extend to millions <strong>of</strong> years.Strong dem<strong>and</strong> has been expressed for reversible disposal if a <strong>repository</strong> were to be constructed.<strong>Andra</strong> has taken this into account in its <strong>repository</strong> concepts, particularly by designing a flexiblemethod <strong>of</strong> <strong>repository</strong> <strong>management</strong>.Operating a <strong>repository</strong> would involve several industrial activities. These could concern a time scale onthe other <strong>of</strong> a century, with is not uncommon to other human endeavors. As with any other industrialfacility, they must be performed in such a way as to protect man <strong>and</strong> the environment.The ability <strong>of</strong> a <strong>repository</strong> to protect man from the risks associated with the waste can be assessed inrelation to particular safety objectives. These objectives have been defined both for the industrialoperating phase <strong>and</strong> for the long term.DOSSIER 2005 ARGILE -ARCHITECTURE AND MANAGEMENT OF A GEOLOGICAL DISPOSAL SYSTEM32/495

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