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Bold application of the sNDM diffusion method to REA in a D2O/H2O-cooled thorium-fueled SMR core with azimuthal mesh.
- Source :
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Progress in Nuclear Energy . Oct2024, Vol. 175, pN.PAG-N.PAG. 1p. - Publication Year :
- 2024
-
Abstract
- Previously applied to REA (Rod Ejection Accident) in several PWR-like cores, the minimalistic Nodal Drift Method (NDM) has recently been generalized to sNDM (super NDM). Both developed and validated on a heat-up transient of the KRUSTY experiment made of a few homogeneous parts, sNDM basically feeds the one-group diffusion approximation with so-called corrective Surface Factors (SF) for internodal currents from MCNP F1 tallies. In order to specify its practical usefulness for exploratory design studies, sNDM at its turn is put to the demanding test of REA in a PWR-like core. The chosen test case is a 600 MW th D 2 O/H 2 O-cooled thorium-fueled Spectral Shift Control Reactor (SSCR) core retrieved from previous studies, whose main results on conversion (by our MC-based tool SMURE) and safety (by NDM) are first summed up. Enhanced MCNP core models at HFP, CZP and HZP (respectively Hot Full, Cold Zero and Hot Zero Power) are detailed that have been specially adapted to a 2D radial-azimuthal mesh of few large nodes towards an even simpler REA calculation by sNDM. Other settings, necessary at BOT (Beginning Of Transient from HZP), include fuel and coolant thermal feedbacks as well as the global conductance of a lumped thermal model. Last but not least, the special cases of a few SF found variable between BOT and EOL (End Of Launch at t = 0.05 s) are addressed by an iterative transient calculation based on their linear interpolation. This method is proven effective at the cost of accepting an irreducible discrepancy for the radial exchange rate of the ejected node, provided that a proper so-called global way of computing all SF is used. Finally, main transient results are given until EOT equilibrium (End Of Transient at t = 300 s), with various sanity checks (including a partial safety one). • D 2 O/H 2 O-cooled SSCR has interesting conversion and safety performance with thorium. • Enhanced PWR-like core is designed at all BOC's states and studied over full cycle. • Main sNDM settings include initial Surface Factors (SF) and a lumped thermal model. • Transient calculation requires two steps for the update of a few SF changed by REA. • Transient results and basic thermal criteria allow to partially assess SSCR safety. [ABSTRACT FROM AUTHOR]
- Subjects :
- *FOREIGN exchange rates
*THORIUM
*COOLANTS
*INTERPOLATION
*TALLIES
Subjects
Details
- Language :
- English
- ISSN :
- 01491970
- Volume :
- 175
- Database :
- Academic Search Index
- Journal :
- Progress in Nuclear Energy
- Publication Type :
- Academic Journal
- Accession number :
- 179030176
- Full Text :
- https://doi.org/10.1016/j.pnucene.2024.105344