
Nuclear


From Uranium to Fuel
09/13/2010
Most nuclear power plants do not use natural uranium directly to produce electricity. The nuclear fuel cycle involves a number of processes: ore extraction, uranium conversion, and enrichment.
Extraction and Processing
Ore can be extracted in three different ways, depending on the deposit's depth and features :
• Underground mining: ore is accessed via a system of wells and galleries.
• Open pit mining: the rocky layer covering the ore is stripped back.
• In-situ extraction: an acid or alkaline solution is injected underground to dissolve the ore and the solution is then pumped out.
In conventional mines, blocks of ore are broken up, finely crushed, and subjected to chemical processing. After separation, washing, filtering, and drying, a concentrate called yellow cake is obtained (so called because of its color and cakey texture). It contains about 75% uranium, i.e. 750 kg per ton1. With in-situ extraction, the uranium is separated once it is brought back to the surface. The pulp obtained is dehydrated and converted into yellow cake2.
In 2009, a joint study by the OECD's Nuclear Energy Agency (NEA) and the International Atomic Energy Agency (IAEA) estimated that total conventional resources that could be extracted at less than $130 US per kg amounted to about 6.3 million tons. Uranium requirements are expected to rise to an annual amount of 80,000-100,000 tons by 2025. Therefore, the resources currently known about are sufficient3.
Enrichment - From One Form of Uranium to Another
Natural uranium contains 99.3% of uranium 238 (U238) and 0.7% of uranium 235 (U235). For fuel, most nuclear reactors (90% of reactors in operation worldwide) use uranium containing 3-5% of uranium 235. Therefore, natural uranium's concentration of U235 needs to be increased. To do this, it is first turned into gas - uranium hexafluoride or UF6 - this is conversion. Next, the proportion of U235 is increased - this is enrichment. To carry out this operation, there are two main industrial processes- gaseous diffusion and centrifugation. Both of these processes exploit the small difference in mass between molecules of uranium hexafluoride 235 and molecules of uranium hexafluoride 238
(U235 is lighter than U238).
Gaseous diffusion involves forcing the gas through porous membranes. The lighter molecules (U235) pass through faster than the U238 molecules. The operation is repeated over 1000 times to obtain uranium hexafluoride with the right concentration of U235.
Centrifugation uses centrifuges rotating at extremely high speed, into which UF6 is introduced. The heavier molecules (U238) are projected toward the outside of the centrifuge while the lighter molecules (U235) migrate towards the center. The gas enriched in the lighter U235 rises and is recovered at the very top of the centrifuge4.
Manufacturing Fuel
After enrichment, uranium hexafluoride (UF6) is converted into uranium oxide, a black powder.
This is then compressed into little pellets that are baked in a furnace at 1700°C to obtain the right density. A pellet of uranium oxide weighs 7 grams and releases as much energy as a ton of coal.
The pellets are then placed in 4m-long metal tubes. The tubes are sealed at both ends to obtain a fuel rod containing about 300 pellets. The rods are grouped into a metal square array to make fuel assemblies. Each assembly contains about 250 rods5. The fuel is finally ready to be placed inside the reactor core.
Managing and Recycling Radioactive Waste
Most radioactive waste comes from producing electricity in nuclear power plants (85% in France6). There are several categories of waste, depending on the intensity of the radiation they emit and their life span (length of time during which they remain radioactive).
Short-lived Low-activity Radioactive Waste
Given the speed of radioactive decay (i.e. the half-life), this waste will take 300 years to reach the level of natural radioactivity. Most of this waste is operational waste related to the maintenance of nuclear power plants; such as tools or cloths used in the nuclear zone to carry out maintenance tasks, or replaced parts, such as valves and filters.
In France, the volume of waste has been considerably reduced (by a factor of three in ten years) and it now represents about 100m3 per reactor per year.
This waste is bundled together and encased in steel or concrete. The waste is encased in a matrix, a material whose purpose is to render it inert and contain radioactivity. The containers isolate waste from the environment.
Long-lived Intermediate- and High-activity Waste
This is waste from spent nuclear fuel, which represents 10% of nuclear waste. The spent fuel is highly radioactive and will remain so for a very long time. It can be reprocessed to recycle its energy material. To do this, the various components are separated.
• The metal tube containing the fuel
• The energy material (uranium and plutonium) i.e. 95% of the spent fuel
• The waste generated by fission: fission products and minor actinides (elements formed through the absorption of neutrons by uranium nuclei)
Reprocessing involves recovering material that still contains energy to reduce the volume of waste to be stored by a factor of three. The final high-activity waste is vitrified, i.e. poured into glass, a material that is heat- and radiation-resistant. This glass is packed into stainless steel tanks and stored in concrete wells that are ventilated to keep them cool.
This temporary storage solution can last another few decades pending a definitive solution. Because of reprocessing, volumes are low. Finland and Sweden use deep geological storage - a site is currently under construction in Finland (scheduled to open in 2020) and another is in the study phase in Sweden. The United States has had a storage center for military waste since 1996. Spent civil fuel is currently stored in nuclear power plants.
[1] AREVA: http://areva.com
[2] American Uranium: http://americanuraniumcorp.com/french/isr.php
[3] NEA: http://www.nea.fr/press/2006/2006-02.html
[4] Société Française d'Energie Nucléaire: http://sfen.org/
[5] Société Française d'Energie Nucléaire: http://sfen.org/ ; AREVA http://areva.com/
[6] CEA











