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RD&D-Programme 2004 - SKB

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15 Fuel<br />

The spent fuel that will be emplaced (deposited) in the repository comes from nuclear power<br />

plants. For an alternative with 40 years of reactor operation, the quantity of BWR fuel is<br />

estimated to be 7,200 tonnes and the quantity of PWR fuel 2,300 tonnes /15-1/. In addition,<br />

23 tonnes of Mox fuel, 20 tonnes of fuel from the Ågesta reactor and some residues from fuel<br />

investigations at Studsvik will be deposited. The fuel’s burnup can vary from approximately<br />

15 to 60 MWd/kgU. Differences in radionuclide content between PWR and BWR fuel are<br />

marginal viewed from a safety assessment perspective. Mox fuel has a higher decay heat than<br />

uranium fuel, which means that less fuel can be deposited in each canister. The differences<br />

between different fuel types are more important when it comes to assessing criticality. The<br />

assessments are therefore made with the fuel types that are least favourable with respect to<br />

criticality.<br />

15.1 Initial state in fuel/cavity<br />

15.1.1 Variables<br />

For the safety assessment, the fuel is described by means of a set of variables which together<br />

characterize the fuel in a suitable manner for the assessment. The description applies not only<br />

to the fuel itself, but also the cavities in the canister, into which water can penetrate if there is<br />

a defect in the copper canister. Processes such as fuel dissolution and corrosion of the cast iron<br />

insert will then take place in the cavity. The cavities could thus be included in either the fuel<br />

or the canister subsystem, and have been included in the fuel here. The variables are defined in<br />

Table 15-1.<br />

The initial state, i.e. the value these variables were assumed to have at the time of deposition,<br />

was described in the main report of SR 97, section 9.2 /15-2/. The research programme around<br />

the initial state for the different variables in the fuel is described in the following.<br />

Table 15-1. Variables in the fuel.<br />

Variable<br />

Geometry<br />

Radiation intensity<br />

Temperature<br />

Hydrovariables<br />

Mechanical stresses<br />

Total radionuclide inventory<br />

Gap inventory<br />

Material composition<br />

Water composition<br />

Gas composition<br />

Definition<br />

Geometric dimensions of all components of the fuel assembly, such as fuel pellets and<br />

Zircaloy cladding. Also includes the detailed geometry, including cracking, of the fuel<br />

pellets.<br />

Intensity of α, β, γ and neutron radiation as a function of time and space in the fuel<br />

assembly.<br />

Temperature as a function of time and space in the fuel assembly.<br />

Flows and pressures for water and gas as a function of time and space in the cavities in<br />

the fuel and the canister.<br />

Mechanical stresses as a function of time and space in the fuel assembly.<br />

Total occurrence of radionuclides as a function of time and space in the different parts<br />

of the fuel assembly.<br />

Occurrence of radionuclides as a function of time and space in the gap and grain<br />

boundaries.<br />

The materials of which the different components in the fuel assembly are composed,<br />

excluding radionuclides.<br />

Composition of water (including any radionuclides and dissolved gases)in the cavities in<br />

the fuel and canister.<br />

Composition of gas (including any radionuclides) in the cavities in the fuel and canister.<br />

RD&D-<strong>Programme</strong> <strong>2004</strong> 163

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