. After use, the spent fuel is delivered to a reprocessing plant (2) or to a final repository (3). In
nuclear reprocessing, 95% of spent fuel can potentially be recycled to be returned to use in a power plant (4). The
nuclear fuel cycle starts with
uranium mining. The
uranium ore is then converted into a compact
ore concentrate, known as
yellowcake (U3O8), to facilitate transport. Fission reactors generally need
uranium-235, a
fissile isotope of uranium. The concentration of uranium-235 in natural uranium is low (about 0.7%). Some reactors can use this natural uranium as fuel, depending on their
neutron economy. These reactors generally have graphite or
heavy water moderators. For light water reactors, the most common type of reactor, this concentration is too low, and it must be increased by a process called
uranium enrichment. After some time in the reactor, the fuel have reduced fissile material and increased fission products, until its use becomes impractical. Uranium is present in trace concentrations in most rocks, dirt, and ocean water, but is generally economically extracted only where it is present in relatively high concentrations. As of 2011 the world's known resources of uranium, economically recoverable at the arbitrary price ceiling of US$130/kg, were enough to last for between 70 and 100 years in current reactors. Light water reactors (which account for almost all operational reactors) make relatively inefficient use of nuclear fuel, mostly using only the very rare uranium-235 isotope. Limited uranium-235 supply may inhibit substantial expansion with the current nuclear technology.
Nuclear reprocessing can make this waste reusable, and newer reactors also achieve a more efficient use of the available resources than older ones. These advanced fuel cycles and nuclear reprocessing are currently not widely used because the price of uranium is very low compared to the cost of nuclear plants, so it's more economically viable to mine new uranium rather than reprocess it. Nuclear reprocessing also carries higher risk of nuclear proliferation, as it separates material that can be used to manufacture nuclear weapons. Unconventional uranium resources also exist. Uranium is naturally present in seawater at a concentration of about 3
micrograms per liter, with 4.4 billion tons of uranium considered present in seawater at any time. Over geological timescales, uranium extracted on an industrial scale from seawater would be replenished by both river erosion of rocks and the natural process of uranium
dissolved from the surface area of the ocean floor, both of which maintain the
solubility equilibria of seawater concentration at a stable level. Some commentators have argued that this strengthens the case for
nuclear power to be considered a renewable energy.
Waste fuel before and after approximately three years in the
once-through nuclear fuel cycle of a
LWR The normal operation of nuclear power plants and facilities produce
radioactive waste, or nuclear waste. This type of waste is also produced during plant decommissioning. There are two broad categories of nuclear waste: low-level waste and high-level waste.
High-level waste over time The fission products are responsible for the bulk of the short-term radioactivity, whereas the plutonium and other transuranics are responsible for the bulk of the long-term radioactivity. High-level waste must be stored isolated from the
biosphere with sufficient shielding so as to limit radiation exposure. After being removed from the reactors, used fuel bundles are stored for six to ten years in
spent fuel pools, which provide cooling and shielding against radiation. After that, the fuel is cool enough that it can be safely transferred to
dry cask storage. The radioactivity decreases exponentially with time, such that it will have decreased by 99.5% after 100 years. The more intensely radioactive short-lived
fission products (SLFPs) decay into stable elements in approximately 300 years, and after about 100,000 years, the spent fuel becomes less radioactive than natural uranium ore. Commonly suggested methods to isolate long-lived fission product (LLFP) waste from the biosphere include separation and
transmutation,
Thermal-neutron reactors, which presently constitute the majority of the world fleet, cannot burn up the
reactor grade plutonium that is generated during the reactor operation. This limits the life of nuclear fuel to a few years. In some countries, such as the United States, spent fuel is classified in its entirety as a nuclear waste. In other countries, such as France, it is largely reprocessed to produce a partially recycled fuel, known as mixed oxide fuel or
MOX. For spent fuel that does not undergo reprocessing, the most concerning isotopes are the medium-lived
transuranic elements, which are led by reactor-grade plutonium (with a
half-life 24,000 years). Some proposed reactor designs, such as the
integral fast reactor and
molten salt reactors, can use as fuel the plutonium and other actinides in spent fuel from light water reactors, thanks to their
fast fission spectrum. This offers a potentially more attractive alternative to deep geological disposal. The
thorium fuel cycle results in similar fission products, though creates a much smaller proportion of transuranic elements from
neutron capture events within a reactor. Spent thorium fuel, although more difficult to handle than spent uranium fuel, may present somewhat lower proliferation risks.
Low-level waste The nuclear industry also produces a large volume of
low-level waste, with low radioactivity, in the form of contaminated items like clothing, hand tools, water purifier resins, and (upon decommissioning) the materials of which the reactor itself is built. Low-level waste can be stored on-site until radiation levels are low enough to be disposed of as ordinary waste, or it can be sent to a low-level waste disposal site.
Waste relative to other types In countries with nuclear power, radioactive wastes account for less than 1% of total industrial toxic wastes, much of which remains hazardous for long periods. Coal-burning plants, in particular, produce large amounts of toxic and mildly radioactive ash resulting from the concentration of
naturally occurring radioactive materials in coal. A 2008 report from
Oak Ridge National Laboratory concluded that coal power actually results in more radioactivity being released into the environment than nuclear power operation, and that the population
effective dose equivalent from radiation from coal plants is 100 times that from the operation of nuclear plants. Although coal ash is much less radioactive than spent nuclear fuel by weight, coal ash is produced in much higher quantities per unit of energy generated. It is also released directly into the environment as
fly ash, whereas nuclear plants use shielding to protect the environment from radioactive materials. Nuclear waste volume is small compared to the energy produced. For example, at
Yankee Rowe Nuclear Power Station, which generated 44 billion
kilowatt hours of electricity when in service, its complete spent fuel inventory is contained within sixteen casks. It is estimated that to produce a lifetime supply of energy for a person at a western
standard of living (approximately 3
GWh) would require on the order of the volume of a
soda can of
low enriched uranium, resulting in a similar volume of spent fuel generated.
Waste disposal generated by the United States during the Cold War are stored underground at the
Waste Isolation Pilot Plant (WIPP) in
New Mexico. The facility is seen as a potential demonstration for storing spent fuel from civilian reactors. Following interim storage in a
spent fuel pool, the bundles of used fuel rod assemblies of a typical nuclear power station are often stored on site in
dry cask storage vessels. Disposal of nuclear waste is often considered the most politically divisive aspect in the lifecycle of a nuclear power facility. The lack of movement of nuclear waste in the 2 billion year old
natural nuclear fission reactors in
Oklo,
Gabon is cited as "a source of essential information today". Experts suggest that centralized underground repositories which are well-managed, guarded, and monitored, would be a vast improvement. refinement is conducted within remote-handled
hot cells. There are no commercial scale purpose built underground high-level waste repositories in operation. However, in Finland the
Onkalo spent nuclear fuel repository of the
Olkiluoto Nuclear Power Plant was under construction as of 2015.
Reprocessing Most
thermal-neutron reactors run on a
once-through nuclear fuel cycle, mainly due to the low price of fresh uranium. However, many reactors are also fueled with recycled fissionable materials that remain in spent nuclear fuel. The most common fissionable material that is recycled is the
reactor-grade plutonium (RGPu) that is extracted from spent fuel. It is mixed with uranium oxide and fabricated into mixed-oxide or
MOX fuel. Because thermal LWRs remain the most common reactor worldwide, this type of recycling is the most common. It is considered to increase the sustainability of the nuclear fuel cycle, reduce the attractiveness of spent fuel to theft, and lower the volume of high level nuclear waste. Spent MOX fuel cannot generally be recycled for use in thermal-neutron reactors. This issue does not affect
fast-neutron reactors, which are therefore preferred in order to achieve the full energy potential of the original uranium. The main constituent of spent fuel from LWRs is slightly
enriched uranium. This can be recycled into
reprocessed uranium (RepU), which can be used in a fast reactor, used directly as fuel in
CANDU reactors, or re-enriched for another cycle through an LWR. Re-enriching of reprocessed uranium is common in France and Russia. Reprocessed uranium is also safer in terms of nuclear proliferation potential. Reprocessing has the potential to recover up to 95% of the uranium and plutonium fuel in spent nuclear fuel, as well as reduce long-term radioactivity within the remaining waste. However, reprocessing has been politically controversial because of the potential for
nuclear proliferation and varied perceptions of increasing the vulnerability to
nuclear terrorism. While reprocessing can reduce the volume of high-level waste by 80%, it does not reduce the
fission products that are the primary causes of residual heat generation and radioactivity for the first century outside the reactor. Thus, reprocessed waste still requires an almost identical treatment to spent nuclear fuel at least for the first hundred years, after which the radioactivity of reprocessed waste may decline more rapidly. It produces MOX fuel from spent fuel derived from several countries. More than 32,000 tonnes of spent fuel had been reprocessed as of 2015, with the majority from France, 17% from Germany, and 9% from Japan.
Breeding assemblies being inspected before entering a
pressurized water reactor in the United States Breeding is the process of converting non-fissile material into fissile material that can be used as nuclear fuel. The non-fissile material that can be used for this process is called
fertile material, and constitute the vast majority of current nuclear waste. This breeding process occurs naturally in
breeder reactors. As opposed to light water thermal-neutron reactors, which use uranium-235 (0.7% of all natural uranium), fast-neutron breeder reactors use uranium-238 (99.3% of all natural uranium) or thorium. A number of fuel cycles and breeder reactor combinations are considered to be sustainable or renewable sources of energy. In 2006 it was estimated that with seawater extraction, there was likely five billion years' worth of uranium resources for use in breeder reactors. Breeder technology has been used in several reactors, but as of 2006, the high cost of reprocessing fuel safely requires uranium prices of more than US$200/kg before becoming justified economically. Breeder reactors are however being developed for their potential to burn all of the actinides (the most active and dangerous components) in the present inventory of nuclear waste, while also producing power and creating additional quantities of fuel for more reactors via the breeding process. As of 2017, there are two breeders producing commercial power,
BN-600 reactor and the
BN-800 reactor, both in Russia. The
Phénix breeder reactor in France was powered down in 2009 after 36 years of operation. with plans to build more. Another alternative to fast-neutron breeders are thermal-neutron breeder reactors that use uranium-233 bred from
thorium as fission fuel in the
thorium fuel cycle.
India's three-stage nuclear power programme features the use of a thorium fuel cycle in the third stage, as it has abundant thorium reserves but little uranium. == Decommissioning ==