Fission fragment trasport out of U-233

From New IAC Wiki
Jump to navigation Jump to search

U-233 Coating

The fission chamber has a fissionale material as a sensitive neutron target. The fission chambers have usually target material that make them sensitive for neutrons, them most commonly used material for detecting thermal neutron is U-235, in case of fast neutron Th-232 or U-238 represnt good target. in some cases the fission chamber may contain more than one taget to detect a wide range of emitted neutrons.<ref name= "Andriamonje"> Novel Micromegas Detector for In-Core Nuclear Reactor Neutron Flux Measurements </ref>

In this research, the neutron sensitive material used in the fission chamber is Uranium 233. U-233 has a relatively high neutron fission cross section in the energy range of 0.1-30 MeV as shown in the figure below.

U-233 fissionxsection 0.01-100MeV.gif


U-233 fissionxsection fullenergyrange.gif

The coating on a circular metal plate which is connected to the cathode. The coating of U-233 has a cirular shape of an inch in diameter,

=








<references/>

Retrieved from "https://wiki.iac.isu.edu/index.php?title=Fission_fragment_trasport_out_of_U-233&oldid=87193"