U233 immediate fission products ?

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The immediate fission products of U-233 are similar to those of U-235, producing isotopes like barium and krypton, but with two fewer neutrons. The fission reaction for U-233 involves the absorption of a neutron leading to U-234, which also generates 2 or 3 additional neutrons. U-233 can sustain a chain reaction, as it has a reproduction factor (η) of 2.30 for thermal neutrons, indicating breeding is possible. Various reactor designs, such as CANDU or graphite moderated systems, can optimize neutron absorption and enhance efficiency. Understanding these dynamics is crucial for effective nuclear fuel management.
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Hi, what are the immediate fission products of U233 ? Is the first fission reaction of U233 same as U235 producing Ba and Kr but just different isotopes than U235 ? I would appreciate any help.

Thanks
 
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Anuj06 said:
Hi, what are the immediate fission products of U233 ? Is the first fission reaction of U233 same as U235 producing Ba and Kr but just different isotopes than U235 ? I would appreciate any help.

Thanks
The fission product elements are much the same, however, one starts with 2 fewer neutrons.

U-235 + n => U-236* => f.p. + 2 or 3 n

U-233 + n => U-234* => f.p. + 2 or 3 n

http://www.nature.com/nature/journal/v161/n4092/pdf/161520a0.pdf

https://www.physicsforums.com/showpost.php?p=2546513&postcount=9
 
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Thank you ! But, then a small question, is U233 chain reaction self sustainable since it release fewer neutrons ?
 
One would be interested in

η = reproduction factor = number of neutrons produced per neutron absorbed in fuel
> 2 implies breeding is possible

ν (nu) = number of neutrons produced per fission


Code:
Isotope  Thermal η   Fast η
  U-235      2.07        2.30
  Pu-239     2.11        2.70
  U-233      2.30        2.45
Ref: http://www.if.uidaho.edu/~gunner/ME443-543/LectureNotes/LMFBR.pdf

http://energyfromthorium.com/2006/07/29/wash-1097-appendix-a-reactor-physics/
It's probably better to obtain a copy of WASH-1097.

One can also construct a tighter (hex or triangular) lattice similar to that of a VVER-1000. Or one could use a CANDU (deuterium moderated) system, or a graphite moderated system using SiC/C clad fuel. Flouride salt is another possibility.

And one can minimize the parastic absorption of neutrons by exclusing Ni-based alloys from the reactor internals, to the extent possible.

This might be of interest.
http://www.osti.gov/bridge/servlets/purl/4505731-QrJfWh/4505731.pdf
 
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