Radiochemistry is the chemistry of radioactive materials, in which radioactive
isotopes of elements are used to study the properties and
chemical reactions of non-radioactive isotopes (often within radiochemistry the absence of radioactivity leads to a substance being described as being
inactive as the isotopes are
stable). For further details please see the page on
radiochemistry.
Radiation chemistry Radiation chemistry is the study of the chemical effects of radiation on matter; this is very different from radiochemistry as no radioactivity needs to be present in the material which is being chemically changed by the radiation. An example is the conversion of water into
hydrogen gas and
hydrogen peroxide. Prior to radiation chemistry, it was commonly believed that pure water could not be destroyed. Initial experiments were focused on understanding the effects of radiation on matter. Using an X-ray generator,
Hugo Fricke studied the biological effects of radiation as it became a common treatment option and diagnostic method.
Chemistry for nuclear power Radiochemistry, radiation chemistry and nuclear chemical engineering play a very important role for uranium and thorium fuel precursors synthesis, starting from ores of these elements, fuel fabrication, coolant chemistry, fuel reprocessing,
radioactive waste treatment and storage, monitoring of radioactive elements release during reactor operation and radioactive geological storage, etc.
Study of nuclear reactions A combination of radiochemistry and radiation chemistry is used to study nuclear reactions such as fission and
fusion. Some early evidence for nuclear fission was the formation of a short-lived radioisotope of
barium which was isolated from
neutron irradiated
uranium (139Ba, with a half-life of 83 minutes and 140Ba, with a half-life of 12.8 days, are major
fission products of uranium). At the time, it was thought that this was a new radium isotope, as it was then standard radiochemical practice to use a barium sulfate carrier precipitate to assist in the isolation of radium. More recently, a combination of radiochemical methods and nuclear physics has been used to try to make new 'superheavy' elements; it is thought that islands of relative stability exist where the nuclides have half-lives of years, thus enabling weighable amounts of the new elements to be isolated. For more details of the original discovery of nuclear fission see the work of
Otto Hahn.
The nuclear fuel cycle This is the chemistry associated with any part of the
nuclear fuel cycle, including
nuclear reprocessing. The fuel cycle includes all the operations involved in producing fuel, from mining, ore processing and enrichment to fuel production (
Front-end of the cycle). It also includes the 'in-pile' behavior (use of the fuel in a reactor) before the
back end of the cycle. The
back end includes the management of the
used nuclear fuel in either a
spent fuel pool or dry storage, before it is disposed of into an underground waste store or
reprocessed.
Normal and abnormal conditions The nuclear chemistry associated with the nuclear fuel cycle can be divided into two main areas, one area is concerned with operation under the intended conditions while the other area is concerned with maloperation conditions where some alteration from the normal operating conditions has occurred or (
more rarely) an accident is occurring. Without this process, none of this would be true.
Reprocessing Law In the United States, it is normal to use fuel once in a power reactor before placing it in a waste store. The long-term plan is currently to place the used civilian reactor fuel in a deep store. This non-reprocessing policy was started in March 1977 because of concerns about
nuclear weapons proliferation. President
Jimmy Carter issued a
Presidential directive which indefinitely suspended the commercial reprocessing and recycling of plutonium in the United States. This directive was likely an attempt by the United States to lead other countries by example, but many other nations continue to reprocess spent nuclear fuels. The Russian government under President
Vladimir Putin repealed a law which had banned the import of used nuclear fuel, which makes it possible for Russians to offer a reprocessing service for clients outside Russia (similar to that offered by
BNFL).
PUREX chemistry The current method of choice is to use the
PUREX liquid-liquid extraction process which uses a
tributyl phosphate/
hydrocarbon mixture to extract both uranium and plutonium from
nitric acid. This extraction is of the
nitrate salts and is classed as being of a
solvation mechanism. For example, the extraction of plutonium by an extraction agent (S) in a nitrate medium occurs by the following reaction. :Pu4+aq + 4NO3−aq + 2Sorganic → [Pu(NO3)4S2]organic A complex bond is formed between the metal cation, the nitrates and the tributyl phosphate, and a model compound of a dioxouranium(VI) complex with two nitrate anions and two triethyl phosphate ligands has been characterised by
X-ray crystallography. When the nitric acid concentration is high the extraction into the organic phase is favored, and when the nitric acid concentration is low the extraction is reversed (the organic phase is
stripped of the metal). It is normal to dissolve the used fuel in nitric acid, after the removal of the insoluble matter the uranium and plutonium are extracted from the highly active liquor. It is normal to then back extract the loaded organic phase to create a
medium active liquor which contains mostly uranium and plutonium with only small traces of fission products. This medium active aqueous mixture is then extracted again by tributyl phosphate/hydrocarbon to form a new organic phase, the metal bearing organic phase is then stripped of the metals to form an aqueous mixture of only uranium and plutonium. The two stages of extraction are used to improve the purity of the
actinide product, the organic phase used for the first extraction will suffer a far greater dose of radiation. The radiation can degrade the tributyl phosphate into dibutyl hydrogen phosphate. The dibutyl hydrogen phosphate can act as an extraction agent for both the actinides and other metals such as
ruthenium. The dibutyl hydrogen phosphate can make the system behave in a more complex manner as it tends to extract metals by an
ion exchange mechanism (extraction favoured by low acid concentration), to reduce the effect of the dibutyl hydrogen phosphate it is common for the used organic phase to be washed with
sodium carbonate solution to remove the acidic degradation products of the tributyl phosphatioloporus.
New methods being considered for future use The PUREX process can be modified to make a UREX (
URanium
EXtraction) process which could be used to save space inside high level
nuclear waste disposal sites, such as
Yucca Mountain nuclear waste repository, by removing the uranium which makes up the vast majority of the mass and volume of used fuel and recycling it as
reprocessed uranium. The UREX process is a PUREX process which has been modified to prevent the plutonium being extracted. This can be done by adding a plutonium reductant before the first metal extraction step. In the UREX process, ~99.9% of the uranium and >95% of
technetium are separated from each other and the other fission products and actinides. The key is the addition of acetohydroxamic acid (AHA) to the extraction and scrubs sections of the process. The addition of AHA greatly diminishes the extractability of plutonium and
neptunium, providing greater proliferation resistance than with the plutonium extraction stage of the PUREX process. Adding a second extraction agent, octyl(phenyl)-
N,
N-dibutyl carbamoylmethyl phosphine oxide (CMPO) in combination with
tributylphosphate, (TBP), the PUREX process can be turned into the TRUEX (
TRans
Uranic
EXtraction) process this is a process which was invented in the US by Argonne National Laboratory, and is designed to remove the transuranic metals (Am/Cm) from waste. The idea is that by lowering the alpha activity of the waste, the majority of the waste can then be disposed of with greater ease. In common with PUREX this process operates by a solvation mechanism. As an alternative to TRUEX, an extraction process using a malondiamide has been devised. The DIAMEX (
DIAMide
EXtraction) process has the advantage of avoiding the formation of organic waste which contains elements other than
carbon,
hydrogen,
nitrogen, and
oxygen. Such an organic waste can be burned without the formation of acidic gases which could contribute to
acid rain. The DIAMEX process is being worked on in Europe by the French
CEA. The process is sufficiently mature that an industrial plant could be constructed with the existing knowledge of the process. In common with PUREX this process operates by a solvation mechanism. Selective Actinide Extraction (SANEX). As part of the management of minor actinides, it has been proposed that the
lanthanides and trivalent minor
actinides should be removed from the PUREX
raffinate by a process such as DIAMEX or TRUEX. In order to allow the actinides such as americium to be either reused in industrial sources or used as fuel the
lanthanides must be removed. The lanthanides have large neutron cross sections and hence they would poison a neutron-driven nuclear reaction. To date, the extraction system for the SANEX process has not been defined, but currently, several different research groups are working towards a process. For instance, the French
CEA is working on a bis-triazinyl pyridine (BTP) based process. Other systems such as the dithiophosphinic acids are being worked on by some other workers. This is the
UNiversal EXtraction process which was developed in Russia and the Czech Republic, it is a process designed to remove all of the most troublesome (Sr, Cs and
minor actinides)
radioisotopes from the raffinates left after the extraction of uranium and plutonium from used
nuclear fuel. The chemistry is based upon the interaction of
caesium and
strontium with poly
ethylene oxide (poly
ethylene glycol) and a
cobalt carborane anion (known as chlorinated cobalt dicarbollide). The actinides are extracted by CMPO, and the
diluent is a polar
aromatic such as
nitrobenzene. Other diluents such as
meta-nitrobenzotri
fluoride and phenyl trifluoromethyl
sulfone have been suggested as well.
Absorption of fission products on surfaces Another important area of nuclear chemistry is the study of how fission products interact with surfaces; this is thought to control the rate of release and migration of fission products both from waste containers under normal conditions and from power reactors under accident conditions. Like
chromate and
molybdate, the
99TcO4 anion can react with steel surfaces to form a
corrosion resistant layer. In this way, these metaloxo anions act as
anodic corrosion inhibitors. The formation of 99TcO2 on steel surfaces is one effect which will retard the release of 99Tc from nuclear waste drums and nuclear equipment which has been lost before decontamination (e.g.
submarine reactors lost at sea). This 99TcO2 layer renders the steel surface passive, inhibiting the
anodic corrosion reaction. The radioactive nature of technetium makes this corrosion protection impractical in almost all situations. It has also been shown that 99TcO4 anions react to form a layer on the surface of activated carbon (
charcoal) or
aluminium. A short review of the biochemical properties of a series of key long lived radioisotopes can be read on line. 99Tc in nuclear waste may exist in chemical forms other than the 99TcO4 anion, these other forms have different chemical properties. Similarly, the release of iodine-131 in a serious power reactor accident could be retarded by absorption on metal surfaces within the nuclear plant. == Education ==