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RD&D-Programme 2004 - SKB

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Transport casks for spent nuclear fuel (Type B packages)<br />

<strong>SKB</strong> owns ten transport casks for spent fuel assemblies of model TN17-2 and two casks for core<br />

components of model TN17-CC. The casks were made in 1982–84.<br />

Up to and including 2003, the fuel transport casks had been used 130 to 150 times and the casks<br />

for core components some 60 or so times each. The casks have served their purpose well. Other<br />

equipment in the transport chain has also proved to be reliable. Consumption of spare parts has<br />

not exhibited an appreciable increase over time.<br />

Terminal vehicles<br />

<strong>SKB</strong> owns five terminal vehicles. One is at SFR in Forsmark and the others stationed at Clab.<br />

The terminals vehicles are usually carried by m/s Sigyn to the nuclear power plants to be used<br />

for local overland transport of fuel and waste transport casks and containers.<br />

The terminal vehicles at Clab underwent a total renovation in 1997–2001, when diesel engines<br />

and cabs were replaced, among other things. The fifth vehicle is being renovated to the same<br />

standard as the others during <strong>2004</strong>. The vehicles work well and are expected to be able to be<br />

used for another ten years or so without the need for any major modifications.<br />

9.3.3 Transport of encapsulated fuel<br />

Canister transport casks<br />

A feasibility study was carried out in the mid-1990s regarding a transport cask for canisters.<br />

A more detailed design of a canister transport cask is being carried out during <strong>2004</strong>. The basic<br />

features are not expected to deviate from those proposed previously, which are described in brief<br />

below.<br />

The main function of the cask is to comprise a radiation shield for the enclosed canister so that<br />

it can be handled during transport without any additional radiation shielding. It must also satisfy<br />

the other requirements for Type B packages in accordance with the IAEA’s transport recommendations,<br />

see section 9.4, regarding for example strength and heat resistance, and must be able to<br />

dissipate the emitted decay heat so that neither the canister nor the surface of the cask get too<br />

hot. A transport cask with canister is shown in cross-section in Figure 9-2.<br />

The planned cask, which will have a diameter of about 1.6 metres, is made of cast iron with a<br />

thickness of between 250 and 300 millimetres. The wall thickness is determined by the required<br />

radiation shielding. Iron does not attenuate neutron radiation as well as gamma radiation, so<br />

the cask shell is provided with a number of channels that are filled with a plastic material that<br />

Shock absorber<br />

Transport cask<br />

Canister with spent nuclear fuel<br />

Figure 9-2. Canister transport cask in cross-section.<br />

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

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