Sensitivity and uncertainty analysis for predication of particulate debris bed self-leveling in prototypic Severe Accident (SA) conditions - 14329
Creators
- 1. Division of Nuclear Power Safety, Royal Institute of Technology - KTH, Roslagstullsbacken 21, SE-106 91, Stockholm (Sweden)
Description
Melt fragmentation, quenching and long term coolability in a deep pool of water under reactor vessel are employed as a severe accident mitigation strategy in several designs of light water reactors. Success of the strategy is contingent upon effectiveness of natural circulation in removing the decay heat generated by the porous debris bed. Geometrical configuration of the bed is one of the factors which affect coolability of the bed. Boiling and two-phase flow inside the bed serve as a source of mechanical energy which can change the geometry of the debris bed by so called 'self-leveling' phenomenon. The goals of this work are (i) to further develop self-leveling modeling approach and validate it against data produced in a new series of PDS-C (Particulate Debris Spreading Closures) experiments, and (ii) to carry out sensitivity-uncertainty analysis for the debris bed spreading for the selected cases of prototypic severe accident conditions. The model has been extended to predict spreading in both planar and axisymmetric geometries. The performed sensitivity analysis ranks the importance of different uncertain input parameters such as accident conditions, debris bed properties, modeling parameters and closures. The knowledge about the most influential parameters is important for further improvement of the model and for efficient reduction of output uncertainties through focused, separate-effect experimental studies. Finally, we report results for particulate debris spreading in prototypic severe accident scenarios with assessment of uncertainties. (authors)
Additional details
Publishing Information
- Publisher
- American Nuclear Society - ANS
- Imprint Place
- La Grange Park, IL (United States)
- ISBN
- 978-0-89448-776-7
- Imprint Pagination
- 10 p.
Conference
- Title
- International Congress on Advances in Nuclear Power Plants
- Acronym
- ICAPP 2014
- Dates
- 6-9 Apr 2014
- Place
- Charlotte, NC (United States)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- France
- INIS RN
- 54022649
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- AFTER-HEAT; AXIAL SYMMETRY; BOILING; COMPUTERIZED SIMULATION; GEOMETRY; NATURAL CONVECTION; POROUS MATERIALS; REACTOR DESIGN; REACTOR VESSELS; SENSITIVITY ANALYSIS; SEVERE ACCIDENTS; TWO-PHASE FLOW; WATER COOLED REACTORS; WATER MODERATED REACTORS
- Descriptors DEC
- ACCIDENTS; BEYOND-DESIGN-BASIS ACCIDENTS; CONTAINERS; CONVECTION; DESIGN; ENERGY TRANSFER; FLUID FLOW; HEAT TRANSFER; MASS TRANSFER; MATERIALS; MATHEMATICS; PHASE TRANSFORMATIONS; REACTOR LIFE CYCLE; REACTORS; SIMULATION; SYMMETRY
Optional Information
- Notes
- 14 refs.; Available on CD-ROM from American Nuclear Society - ANS, 555 North Kensington Avenue, La Grange Park, IL 60526 (US)