High to low pellet cladding gap heat transfer modeling methodology in an uncertainty quantification framework for a PWR rod ejection accident with best estimate coupling
- 1. DEN - Service d'etudes des reacteurs et des mathematiques appliquees - SERMA, CEA - Centre de Saclay, Universite Paris-Saclay, F-91191 Gif-Sur-Yvette (France)
- 2. Centre de Mathematiques Appliquees, Ecole Polytechnique, 91128 Palaiseau Cedex (France)
Description
High to Low modeling approaches can alleviate the computationally expensive fuel modeling in nuclear reactor's transient uncertainty quantification. This is especially the case for Rod Ejection Accident (REA) in Pressurized Water Reactors (PWR) were strong multi-physics interactions occur. In this work, we develop and propose a pellet cladding gap heat transfer (Hgap) High to Low modeling methodology for a PWR REA in an uncertainty quantification framework. The methodology involves the calibration of a simplified Hgap model based on high fidelity simulations with the fuel-thermomechanics code ALCYONE1. The calibrated model is then introduced into the CEA developed CORPUS Best Estimate (BE) multi-physics coupling between APOLLO3R and FLICA4. This creates an Improved Best Estimate (IBE) coupling that is then used for an uncertainty quantification study. The results indicate that with IBE the distance to boiling crisis uncertainty is decreased from 57% to 42%. This is reflected to the decrease of the sensitivity of Hgap. In the BE coupling Hgap was responsible for 50% of the output variance while in IBE it is close to 0. These results show the potential gain of High to Low approaches for Hgap modeling in REA uncertainty analyses. (authors)
Availability note (English)
Available from doi: http://dx.doi.org/10.1051/epjn/2020018Additional details
Identifiers
- DOI
- 10.1051/epjn/2020018;
Publishing Information
- Journal Title
- EPJ Nuclear Sciences and Technologies
- Journal Volume
- 6
- Journal Page Range
- p. 56.1-56.17
- ISSN
- 2491-9292
INIS
- Country of Publication
- France
- Country of Input or Organization
- France
- INIS RN
- 52071229
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- A CODES; COMPUTERIZED SIMULATION; COUPLING; F CODES; FUEL RODS; HEAT TRANSFER; PWR TYPE REACTORS; ROD EJECTION ACCIDENTS; VALIDATION
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; FUEL ELEMENTS; POWER REACTORS; REACTIVITY-INITIATED ACCIDENTS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; SIMULATION; TESTING; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 27 refs.