Understanding Nuclear Fission Yields: U-233, U-235, Pu-239, and Pu-241

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Discussion Overview

The discussion centers on the thermal fission products of U-233, U-235, Pu-239, and Pu-241, specifically focusing on the concepts of cumulative and independent fission yields. Participants explore definitions, values, and discrepancies in reported data related to these yields.

Discussion Character

  • Technical explanation
  • Debate/contested

Main Points Raised

  • One participant seeks clarification on the cumulative and independent fission yields, noting discrepancies in values from different sources.
  • Another participant suggests that independent yields should total 200%, questioning the definition of cumulative yields.
  • A participant defines cumulative yield as including yields from fission, decay, and transmutation, providing examples of fission product chains.
  • Further clarification is offered that independent yields represent immediate yields, while cumulative yields encompass all possible nuclei produced during the reaction process.
  • Another participant emphasizes the importance of cumulative yields in reactor operations and waste management, indicating that they define the isotopic vector at shutdown and influence subsequent fuel cycles.

Areas of Agreement / Disagreement

Participants express differing views on the definitions and implications of cumulative and independent fission yields, with no consensus reached on the correct interpretations or the numerical values involved.

Contextual Notes

There are unresolved questions regarding the definitions of cumulative and independent yields, as well as discrepancies in reported values from various sources. The discussion highlights the complexity of tracking fission products and their implications for nuclear waste management.

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I'm looking for the most common thermal fission products for U-233, U-235, Pu-239 and Pu-241. As far as I understand it there are two quantities of interest, the cumulative fission yield and the independent fission yield. The latter being "number of atoms of a specific nuclide produced directly by a fission event (not via radioactive decay of the precursors)," whilst the former does include the precursors. This is defined http://www-nds.iaea.org/sgnucdat/safeg2008.pdf" .

I have found some values http://www-nds.iaea.org/sgnucdat/c3.htm" . Unless I've misunderstood both the cumulative fission yield and the independent fission yield columns should add up to 100% yet the cumulative fission yield sums to considerably more than that and the independent fission yield less than that.

Wikipedia gives a list of products in order of yield for U-235 http://en.wikipedia.org/wiki/Fission_product_yield" . This is apparently based on the link above but the two don't seem to correspond and I don't know where the numbers have come from.
 
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I think the independent yields should add to 200%. No idea about the cumulative, and in fact I am rescuing this thread to ask what is exactly the definition of cummulative... Should not be only the final stable nuclei?
 
Cumulative yield for a given nuclide includes it's yield from fission, from decay and from transmutation, since fission products absorbs neutrons, e.g., Te-134 > I-134 > Xe-134 > Cs-134 > Ba-134 . . . and e.g., I-133 + n => I-134, Xe-133 + n => Xe-134, . . . .
 
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Ok, to fix it:

independent yields are the immediate yields
cumulative yields are all the possible nuclei during the reaction process
chain yields are the final stable nuclei, or very long term.

I guess cumulative is for radatiation in the reactor and chain for the nuclear waste.
 
Cumulative is what we have to deal with in the reactor, and later on in either reprocessing or spent fuel. Certainly the cumulative yields provide the isotopic vector at shutdown. The reinsert fuel will go back in and the fission products will again change. Depletion codes have to track production, transmutation and decay. The discharge fuel will define the waste, with it's from recycling or from direct burial of spent/used fuel.
 

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