Yes, we can get more electricity from thorium, if you are asking about the supply. When 232Th is used in a nuclear reactor, it is bred to become 233U. This isotope of uranium has about as much energy available as 235U, so the amount of energy per fission event is about the same for thorium as it is for uranium. Aside from that, however, there are important differences. Thorium does not need to be enriched, so all of it can be used. The amount of thorium we have is a multiple of the amount of uranium. The combination means that, where we only have a few decades supply of uranium, we have enough thorium to last thousands of years.
The amount of saturation tells how much solute is present compared to the amount of solvent..!!
10-15 percent
Though both Hafnium and Zirconium are in the periodic table's fourth group, Hafnium is generally more associated with Zirconium. In terms of electron shells, Thorium has an extra shell of 18 electrons much like Hafnium, so there probably is some relation in behaviour. In other words, yes Hafnium may be mistaken for Thorium, but mistaking it for Zirconium is much more likely.
After 24,10(3) days (the half-time of this isotope) the mass is 50 %.
Bitumen has not thorium.
Yes, we can get more electricity from thorium, if you are asking about the supply. When 232Th is used in a nuclear reactor, it is bred to become 233U. This isotope of uranium has about as much energy available as 235U, so the amount of energy per fission event is about the same for thorium as it is for uranium. Aside from that, however, there are important differences. Thorium does not need to be enriched, so all of it can be used. The amount of thorium we have is a multiple of the amount of uranium. The combination means that, where we only have a few decades supply of uranium, we have enough thorium to last thousands of years.
The amount of saturation tells how much solute is present compared to the amount of solvent..!!
After 48,2 days the amount of Th-234 will be 25 g.
Thorium is not expensive; for thorium dioxide (99,99 %) the price is cca. 0,1 USD/g.
After 48,2 days the amount of Th-234 will be 25 g.
Ceramic bowls for kitchen, with thorium, doesn't exist.
Approx. 50 USD/pound for thorium dioxide (99,99 %).
Thorium-234 has a half-life of 24.1 days. How much of a 100-g sample of thorium-234 will be unchanged after 48.2 days?
Uranium deposits are much larger in the US compared to India, and all power operation in the US is currently based on enriched uranium with a straight-through cycle, the fuel is enriched, loaded, unloaded and stored with no further use. Large deposits of uranium are also found in Australia and Canada. In India the reserves of indigenous uranium are not great, but there are considerable reserves of thorium. This can be used for power production but the process is much more complicated and involves some chemical handling of the spent fuel which is not carried out in the US at present, because there is no need. India is not a signatory to the NPT and threfore wants to have its own indigenous supply of fuel, and this has prompted intereest in the thorium cycle. With the new US/India deal this emphasis could change. The following description of India's involvement with thorium is taken from 'www.world-nuclear.com'.In India, both Kakrapar-1 and -2 units are loaded with 500 kg of thorium fuel in order to improve their operation when newly-started. Kakrapar-1 was the first reactor in the world to use thorium, rather than depleted uranium, to achieve power flattening across the reactor core. In 1995, Kakrapar-1 achieved about 300 days of full power operation and Kakrapar-2 about 100 days utilising thorium fuel. The use of thorium-based fuel was planned in Kaiga-1 and -2 and Rajasthan-3 and -4 (Rawatbhata) reactors. With about six times more thorium than uranium, India has made utilisation of thorium for large-scale energy production a major goal in its nuclear power program, utilising a three-stage concept: * Pressurised Heavy Water Reactors (PHWRs, elsewhere known as CANDUs) fuelled by natural uranium, plus light water reactors, produce plutonium. * Fast Breeder Reactors (FBRs) use this plutonium-based fuel to breed U-233 from thorium. The blanket around the core will have uranium as well as thorium, so that further plutonium (ideally high-fissile Pu) is produced as well as the U-233. Then * Advanced Heavy Water Reactors burn the U-233 and this plutonium with thorium, getting about 75% of their power from the thorium. The used fuel will then be reprocessed to recover fissile materials for recycling. This Indian program has moved from aiming to be sustained simply with thorium to one "driven" with the addition of further fissile uranium and plutonium, to give greater efficiency.
4000
A high amount