Depletion capabilities in the OpenMC Monte Carlo particle transport code

Annals of Nuclear Energy(2021)

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摘要
•A depletion solver has been implemented in the OpenMC code.•Multiple time integration methods can be used.•Comparisons to Serpent on two problems demonstrate that keff agrees to 20–30 pcm.•Predicted isotopic concentrations agree to within 1% when compared with Serpent.•A simplified depletion chain provides improved performance while retaining accuracy.
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关键词
Monte Carlo,Particle transport,Depletion,Transmutation
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