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Analysis of three different types of blockage in a sodium flow path with the MATRA-LMR-FB code
- Source :
- Annals of Nuclear Energy. 36:583-589
- Publication Year :
- 2009
- Publisher :
- Elsevier BV, 2009.
-
Abstract
- A local blockage in a subassembly of an LMR is of particular importance because the local temperature of the coolant increases at the downstream of a blockage and the integrity of the fuel clad can be threatened when an obstacle or a blockage is formed in a flow path. To analyze a flow blockage in a nuclear reactor core, Korea Atomic Energy Research Institute developed a subchannel analysis computer code MATRA-LMR-FB. This code adopts several enhanced modeling features such as a distributed resistance model, state-of-the-art turbulent mixing models, a hybrid difference scheme, and a porous body pressure drop model, therefore, it is applicable to a flow path with a plate-type or a porous-type blockage. The effect of each model has been evaluated through an analysis for the THORS experiment, in which a plate-type blockage was located in a flow channel with wire-wrapped fuel rods. The overall capability of the code has also been evaluated for the KNS experiment with a plate-type blockage in a grid-spaced flow channel, and for the SCARLET-II experiments with a porous blockage in channels formed by wire-wrapped fuel rods. The code shows good predictions for the experiments with a wire-wrapped flow path with a plate-type or a porous type blockage. The analyses for the KNS experiments reveal that the code requires a precise blockage model related to a grid spacer model.
Details
- ISSN :
- 03064549
- Volume :
- 36
- Database :
- OpenAIRE
- Journal :
- Annals of Nuclear Energy
- Accession number :
- edsair.doi...........3087e127b45f4de2204712e579471ba8