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ICEM11 Final Program 9.7.11pm_ICEM07 Final Program ... - Events

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Session 32 Abstracts<br />

3) CHARACTERISATION OF BEDROCK HYDROGEOLOGY AT THE OLKILUOTO<br />

SITE USING SURFACE BASED AND UNDERGROUND DATA (w/oP-59095)<br />

Lee Hartley, Dave Swan, Steven Baxter, SERCO (UK)<br />

Posiva Oy is responsible for implementing the programme for geological disposal of spent nuclear fuel in Finland. Olkiluoto<br />

in Eurajoki has been selected as the primary site for the repository, subject to further detailed characterisation which is currently<br />

focused on the construction of an underground rock characterisation and research facility (the ONKALO). An essential part of the<br />

site investigation programme is analysis of groundwater flow and solute transport to depth by means of numerical flow modelling<br />

as part of the 2011 site descriptive model. Groundwater flow in the crystalline rocks at Olkiluoto takes place predominantly in the<br />

void space of the interconnected fractures in the bedrock. Many of the hydraulic characteristics of flow through such a system can<br />

be represented by hydrogeological Discrete Fracture Network (DFN) models, since they capture some of the details of fracture<br />

geometry, size, connectivity and openings. The paper describes how field data is used to derive such models, ultimately for use in<br />

safety assessment.<br />

Surface based site investigations at Olkiluoto include 53 sub-vertical deep core drilled boreholes and 27 shallower sub-vertical<br />

boreholes. The characterisation of fractures is a key objective. Fracture geometrical data (fracture positions and orientations)<br />

are determined from drill core mapping and/or borehole ...<br />

4) SELF-DISPOSAL OPTION FOR HEAT-GENERATING WASTE (wP-59182)<br />

Michael Ojovan, University of Sheffield; Pavel Poluektov, Vladimir Kascheev, A.A. Bochvar’s VNIINM (UK/Russia)<br />

Self-descending heat generating capsules can be used for disposal of dangerous radioactive wastes in extremely deep layers of<br />

the Earth preventing any release of radionuclides into the biosphere. Self-disposal option for heat-generating radioactive waste such<br />

as spent fuel, high level reprocessing waste or spent sealed radioactive sources, known also as rock melting concept, was considered<br />

in the 70s as a viable alternative disposal option by both Department of Energy in the USA and Atomic Industry Ministry in<br />

the USSR. Self-disposal is currently reconsidered as a potential alternative route to existing options for solving the nuclear waste<br />

problem and is associated with the renaissance of nuclear industry. Self-disposal option utilises the heat generated by decaying<br />

radionuclides of radioactive waste inside a heavy and durable capsule to melt the rock on its way down. As the heat from radionuclides<br />

within the capsule partly melts the enclosing rock, the relatively low viscosity and density of the silicate melt allow capsule<br />

to be displaced upwards past the heavier capsule as it sinks. Eventually the melt cools and solidifies (e.g. vitrifies or crystallizes),<br />

sealing the route along which the capsule passed. Descending or self-disposal continues until enough heat is generated by radionuclides<br />

to provide partial ...<br />

5) NUMOS APPROACH FOR LONG-TERM SAFETY ASSESSMENT (wP-59404)<br />

Takeshi Ebashi, Kenichi Kaku, Katsuhiko Ishiguro, Nuclear Waste Management Organization of Japan (NUMO) (Japan)<br />

In Japan, the Act on <strong>Final</strong> Disposal of Specified Radioactive Waste specifies that the repository siting process shall consist of<br />

three stages. The Nuclear Waste Management Organization of Japan (NUMO) is responsible for geological disposal of vitrified<br />

high-level waste and some types of TRU waste. NUMO has chosen to implement a volunteer approach to siting.<br />

NUMO decided to prepare the 2010 Technical Report, which sets out three policies for ensuring safety. One of these is staged<br />

project implementation and decision-making based on iterative confirmation of safety. Based on this, NUMO will gradually integrate<br />

relevant interdisciplinary knowledge to build a safety case once a formal volunteer application is received that would allow<br />

site investigations to be initiated. The safety assessment takes the central role in multiple lines of reasoning and argumentation by<br />

providing a quantitative evaluation of long-term safety, a key aspect of which is uncertainty management.<br />

This paper presents NUMOs basic strategy for long-term safety assessment, based on the above policy.<br />

In concrete terms, safety assessment procedures are described in the context of the staged implementation programme, based<br />

on integration of knowledge obtained from site investigation/evaluation and engineering studies and reflection of the safety assessment<br />

results in the planning of ...<br />

6) MODELING APPROACHES FOR EVALUATING THE EFFECT OF HETEROGENEITY ON<br />

TWO-PHASE FLOW ASSOCIATED WITH THE MIGRATION OF WASTE GENERATED GAS<br />

FROM SF/HLW- AND L/ILW REPOSITORIES IN LOW-PERMEABILITY FORMATIONS (wP-59196)<br />

Alexandros Papafotiou, Rainer Senger, Intera Inc. Swiss Branch; Andrés Alcolea, TK Consult AG;<br />

William Lanyon, Fracture-Systems Ltd; John Ewing, Intera Inc. Swiss Branch (Switzerland/UK)<br />

Different low-permeability formations are considered as potential host rocks for Low / Intermediate Level waste (L/ILW) and<br />

spent fuel / high-level / long-lived intermediate-level waste (SF/HLW/ILW) in Switzerland. As part of a generic site evaluation<br />

process, emphasis is on the assessment of Mesozoic limestones, marls and claystones in six potential siting areas in Northern and<br />

Central Switzerland. An important aspect in the site evaluation process is the characterization of the low-permeability formations<br />

in terms of spatial variability of the relevant transport properties (porosity, permeability, clay content), as they may affect the migration<br />

of waste-generated gas from L/ILW and SF/HLW/ILW repositories.<br />

Numerical modeling studies are presented, aimed at quantifying the impact of spatial variability of rock properties on gas<br />

release through the host rock on a deca- to hectometer scale. For this purpose, 2-D models of an emplacement tunnel embedded in<br />

a low-permeability host rock are developed for both a sequence of limestones and marls with distinct lithological variability (Effingen<br />

Beds) and a claystone of moderate spatial variability (Opalinus Clay). For the Effingen Beds, a composite geological model is<br />

implemented, comprising stochastic representations of the different facies and the fracture systems. The facies model displays spatial<br />

variations in clay content, porosity ...<br />

96

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