Difference between revisions of "Fission fragment trasport out of U-233"

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[[File:U-233_fissionxsection_fullenergyrange.gif |200px]]
 
[[File:U-233_fissionxsection_fullenergyrange.gif |200px]]
  
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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, 
  
 
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Revision as of 17:46, 25 August 2013

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,

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