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Isotopes in high demand for medical research
Good read: Isotopes in high demand for medical research: http://www.pressenza.com/2013/03/isotopes-in-high-demand-for-medical-research/
..."So the question is, how to get the molybdenum-99 in the first
place? Well, one way is to use the fact that it is a fission product of
uranium-235. That means that inside every uranium-fuelled nuclear
reactor, Mo-99 is being produced all the time – but it is mixed in with
dozens of other fiercely radioactive fission products (such as
cesium-137, iodine-131, strontium-90), activation products (such as
cobalt-60, iron-55, niobium-93m) and transuranic actinides (such as
plutonium,
americium and curium). To get the Mo-99 you would have to
dissolve the fiercely radioactive irradiated fuel in boiling nitric
acid and separate out the tiny amount of Mo-99 by chemical means,
leaving a huge volume of highly radioactive liquid waste.
So to make
the job easier, research reactors are used – no electricity production –
and instead of “reprocessing” the irradiated fuel, special “targets”
are introduced into the core of the reactor made of highly-enriched
uranium (93.3 percent Uranium-235) and withdrawn at a predetermined
time so that the “target” can be dissolved in nitric acid etc. This has
several advantages: (1) you can limit the time the target is in the
reactor, cutting down on the superfluous inventory of other fission
products etc; (2) you can vastly reduce the mass of material that needs
to be dissolved
because the U-235 is so concentrated; (3) you can
control the schedule more easily and achieve a kind of “assembly-line”
procedure without shutting the reactor down.
Even if you use this
nasty method for producing Mo-99 inside a nuclear reactor, and then
reprocessing, you can use LEU (Low Enriched Uranium) instead of High
Enriched Uranium (HEU) – it just means it takes longer and is more
expensive mainly because there is a much larger mass of material to
“reprocess” in order to get out the Mo-99. Argentina has been doing it
this
way for quite some time.
The alternative to using a nuclear
reactor is to use a “particle accelerator” to produce Mo-99. There are
various ways to do this, using a cyclotron (a circular accelerator) or a
linear accelerator (arranged in a straight line). In an accelerator,
isotopes of various kinds can be produced by bombarding a “target” of
some kind with a “beam” of very energetic (high-speed) charged
particles. This is how a university or hospital can produce most if not
all of the isotopes it needs
without the need for a nuclear reactor. For many years, starting in 1949, McGill University got all of its isotopes this way,"
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