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Fission energy release#197

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ChasingNeutrons wants to merge 3 commits intoCambridgeNuclear:mainfrom
ChasingNeutrons:kappa_fission
Open

Fission energy release#197
ChasingNeutrons wants to merge 3 commits intoCambridgeNuclear:mainfrom
ChasingNeutrons:kappa_fission

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@ChasingNeutrons
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This PR is a near-clone of the one from @Esmae.

I made the minor name changes and made two slightly larger changes. First, MG can optionally include a Q-value for fission. This is 202.27 MeV by default. This allows tallying heating in MG as well as CE.

Second, I moved the Q-value and Heating value of U235 into the database. The Heating value can be modified as an optional input.

I welcome @Esmae to make a suggested change somewhere to get her name on the PR!

! Allocate and initialise test nuclearData
! Cross-sections: Total eScattering IeScatter Capture Fission nuFission
call this % xsData % build(6.0_defReal, 3.0_defReal, ZERO, 2.0_defReal, 1.0_defReal, 1.5_defReal)
! Cross-sections: Total eScattering IeScatter Capture Fission nuFission kappFission
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kappFission -> kappaFission


! Cross-sections: Total eScattering IeScatter Capture Fission nuFission
call this % xsData % build(6.0_defReal, 3.0_defReal, ZERO, 2.0_defReal, 1.0_defReal, 1.5_defReal)
! Cross-sections: Total eScattering IeScatter Capture Fission nuFission kappFission
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kappFission -> kappaFission

@Esmae
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Esmae commented Mar 3, 2026

Thanks for helping get this over the line @ChasingNeutrons. I have a few minor comments:

  1. Should the default MG fission energy release be 202.27MeV (as per comment above) or 200MeV (my understanding from the code)? I would vote for the former.
  2. It could be possible to add in mgXsClerk, a dump for the kappaXS, so later specific MG runs have a specific fission energy release number to read it.

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2 participants