Abstract
This thesis develops novel first-principle methods to correct homogenization errors in nodal cross sections and discontinuity factors. Its aim is to improve the accuracy of nodal diffusion simulations of heterogeneous core configurations. This research builds upon previous work conducted at Framatome (Paris, France). It is based on a modal reconstruction of variations in the neutron flux distribution (in space and energy) between the core environment and the infinite-medium approximation, which is typically used in lattice transport calculations for few-group constant generation. Focus is given to the correction of the nodal cross sections.
Original language | English |
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Awarding Institution |
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Supervisors/Advisors |
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Award date | 20 Nov 2018 |
Print ISBNs | 978-94-6186-961-6 |
DOIs | |
Publication status | Published - 2018 |
Keywords
- Neutron diffusion
- Nodal methods
- Homogenization
- Core environment
- Neutron leakage
- Spectral and spatial effects
- Cross-section model