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Validation of mox core reactivity versus flux variation feedback on delayed neutron data

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Academic year: 2021

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Table I. Delayed neutron Yields  d  and average Lifetime  for  239 Pu and  238 U fissions.
Table II. Calculated vs Experimental  eff  values in the MISTRAL2 100%MOX core: (C-E)/E in %  Experiment  Measurement   eff  in pcm  TRIPOLI-4  JEFF-3.1.1   TRIPOLI-4  ENDF/B-VII.0  APOLLO2.8 JEFF-3.1.1  APOLLO2.8  ENDF/B-VII.0  MISTRAL-2   eff  = 370.3
Table III summarizes the T d  measured values corresponding to the residual reactivities of the MISTRAL2  cores, with and without 6 ppm boron poisoning
Table IV. Soluble boron worth (6 ppm) in MISTRAL2 100%MOX core.

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