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Projected Costs of Generating Electricity - OECD Nuclear Energy ...

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Light water reactors require enriched uranium fuel (containing more 235 U, the fissile isotope, than<br />

natural uranium) in order to maintain a chain reaction in spite <strong>of</strong> the absorption <strong>of</strong> neutrons by the<br />

moderator. Fuels used in light water reactors <strong>of</strong> current generation use uranium enriched at some 3 to 5%<br />

in 235 U while natural uranium contains 0.71% <strong>of</strong> 235 U. Light water reactors also can use fuel containing<br />

recycled materials, plutonium and uranium, recovered through reprocessing <strong>of</strong> spent fuel. Pressurised<br />

heavy water reactors use heavy water (deuterium oxide) as coolant and moderator. This choice makes it<br />

possible to utilise natural uranium as fuel. The use <strong>of</strong> pressure tubes rather than a single large pressure<br />

vessel around the core facilitates refuelling while the reactor is in operation.<br />

For light water reactors the main front-end (before fuel loading in the reactor) fuel cycle steps are:<br />

uranium mining and milling; conversion; enrichment; and fuel fabrication. For PHWRs the enrichment<br />

step is not necessary. As enrichment accounts for some 30% <strong>of</strong> total fuel cycle cost (NEA, 2002), fuel<br />

cycle costs are lower for PHWRs than for light water reactors. At the back-end <strong>of</strong> the fuel cycle, after<br />

unloading <strong>of</strong> spent fuel from the reactor, two options are available: direct disposal <strong>of</strong> spent fuel (oncethrough<br />

cycle); and reprocessing (closed cycle). In the first option, spent fuel is conditioned after a period<br />

<strong>of</strong> cooling into a form adequate for final disposal in a high-level radioactive waste repository. In the second<br />

option, spent fuel is separated into materials that can be used again in reactor fuel and waste material<br />

(fission products) which are conditioned, after interim storage for cooling, to be disposed <strong>of</strong> in a high-level<br />

waste repository. There appears to be little difference in overall cost between the once-through and<br />

recycling options (NEA, 1994). For all reactor types and fuel cycle options, radioactive waste arising at<br />

each step <strong>of</strong> the fuel cycle are sorted and conditioned for disposal according to their level <strong>of</strong> radioactivity.<br />

Most countries provided nuclear fuel cost estimates for reactors operating on once-through fuel cycles,<br />

i.e. with direct disposal <strong>of</strong> spent fuel. Three countries provided cost estimates for closed cycle, i.e. with<br />

reprocessing <strong>of</strong> spent fuel and recycling <strong>of</strong> fissile materials.<br />

Advanced reactor designs<br />

New generations <strong>of</strong> nuclear power plants are being developed building upon the experience acquired<br />

through the commissioning and operation <strong>of</strong> existing units. Advanced nuclear power plant designs share<br />

common goals: improved economic competitiveness; enhanced safety; better use <strong>of</strong> natural resources; and<br />

strengthened security and proliferation resistance. Advanced designs pertain to two main categories: evolutionary<br />

and innovative (IAEA, 2004). Evolutionary designs, such as the Korean standard nuclear power<br />

plant (KSNP) and European pressurised water reactor (EPR), achieve improvements through relatively<br />

modest modifications, maintaining strong reliance on a proven design to minimise technological risks.<br />

Innovative designs, on the other hand, incorporate radical conceptual changes requiring extensive R&D<br />

programmes, including in most cases the construction and operation <strong>of</strong> a prototype or demonstration plant<br />

to demonstrate industrial feasibility.<br />

Several nuclear power plants already commissioned, under construction, ordered or planned pertain to<br />

the evolutionary advanced design category. Examples are the Kashiwasaki Kariwa units 6 and 7 ABWR<br />

in operation in Japan, the Olkiluoto-3 EPR under construction in Finland, the Sin-Kori units 1 and 2<br />

(KSNP) being implemented in the Republic <strong>of</strong> Korea and the EPR project in France. Most <strong>of</strong> the units for<br />

which cost estimates were provided for the present study fall within the category <strong>of</strong> evolutionary<br />

advanced reactors.<br />

Advanced light water reactors under development cover a large range <strong>of</strong> capacity from less than<br />

100 MWe to more than 1 500 MWe. Some examples <strong>of</strong> large size advanced LWR designs, beyond those<br />

already in operation or under construction mentioned above, include the ABWR, the BWR 90+, the simplified<br />

BWR (ESBWR), the AP-1000 and the VVER-1000/V-392. Small- and medium-size advanced<br />

LWR under development include AP-600, VVER-640/V-407, IRIS and SMART (IAEA, 2004).<br />

Advanced heavy water reactors are developed mainly in Canada, building upon the experience acquired<br />

through the operation <strong>of</strong> existing CANDU reactors.<br />

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