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A sample of thorium. Thorium-based nuclear power generation is fueled primarily by the nuclear fission of the isotope uranium-233 produced from the fertile element thorium.A thorium fuel cycle can offer several potential advantages over a uranium fuel cycle [Note 1] —including the much greater abundance of thorium found on Earth, superior physical and nuclear fuel properties, and reduced ...
The thorium fuel cycle is a nuclear fuel cycle that uses an isotope of thorium, 232. Th. , as the fertile material. In the reactor, 232. Th. is transmuted into the fissile artificial uranium isotope 233. U. which is the nuclear fuel. Unlike natural uranium, natural thorium contains only trace amounts of fissile material (such as 231.
For example, uranium-238 is weakly radioactive, but pitchblende, a uranium ore, is 13 times more radioactive than the pure uranium metal because of the presence of shorter-lived decay products, such as radium and the noble gas radon. Rock containing thorium and/or uranium (such as some types of granite) emits radon gas, which tends to ...
Two radiometric dating methods involve thorium isotopes: uranium–thorium dating, based on the decay of 234 U to 230 Th, and ionium–thorium dating, which measures the ratio of 232 Th to 230 Th. [e] These rely on the fact that 232 Th is a primordial radioisotope, but 230 Th only occurs as an intermediate decay product in the decay chain of ...
In the thorium fuel cycle thorium-232 absorbs a neutron in either a fast or thermal reactor. The thorium-233 beta decays to protactinium-233 and then to uranium-233, which in turn is used as fuel. Hence, like uranium-238, thorium-232 is a fertile material.
A molten-salt reactor (MSR) is a class of nuclear fission reactor in which the primary nuclear reactor coolant and/or the fuel is a mixture of molten salt with a fissile material. Two research MSRs operated in the United States in the mid-20th century. The 1950s Aircraft Reactor Experiment (ARE) was primarily motivated by the technology's ...
Uranium-233 (233U or U-233) is a fissile isotope of uranium that is bred from thorium-232 as part of the thorium fuel cycle. Uranium-233 was investigated for use in nuclear weapons and as a reactor fuel. [2] It has been used successfully in experimental nuclear reactors and has been proposed for much wider use as a nuclear fuel.
The liquid fuel for the molten salt reactor was a mixture of lithium, beryllium, thorium and uranium fluorides: LiF-BeF 2-ThF 4-UF 4 (72-16-12-0.4 mol%). It had a peak operating temperature of 705 °C in the experiment, but could have operated at much higher temperatures since the boiling point of the molten salt was in excess of 1400 °C.