Analysis of information sources in references of the Wikipedia article "釷燃料發電" in Chinese language version.
The primary advantage of the U-233/thorium cycle in thermal reactors is that the average number of neutrons produced per atom of fissile fuel destroyed by neutron absorption is large enough for U-233 to permit breeding in a thermal reactor, whereas for either U-235 or Pu-239 this quantity is too small to permit breeding in a thermal reactor.
The goal is a self-sustaining reactor, meaning one that will produce and consume about the same amounts of fuel.
Chen Fu, a thermal physicist at the Harbin Institute of Technology involved in the development of new power generation systems for China’s navy, said the heat generated by a thorium molten salt reactor could be perfect to help generate power on a warship.
Chen Fu, a thermal physicist at the Harbin Institute of Technology involved in the development of new power generation systems for China’s navy, said the heat generated by a thorium molten salt reactor could be perfect to help generate power on a warship.
The goal is a self-sustaining reactor, meaning one that will produce and consume about the same amounts of fuel.
