Validation of RESUS model against ORNL series-2 test experiments on aerosol resuspension
Creators
- 1. Universidad Politecnica de Madrid (Spain). Escuela Tecnica Superior de Ingenieros Industriales
Description
RESUS was selected as an appropriate model to study aerosol resuspension. It was chosen because of being statistical in character and based on a force balance criterion. The model has been applied by the Chair of Nuclear Technology (Polytechnical University of Madrid) as directed by its author in his thesis and modifiying the model where necessary. The model results have been compared with experimental data given by Series 2 Aerosol Resuspension Tests developed in 1986 at ORNL. From such comparison it can be deduced the adequacy of the model to explain resuspension. Nevertheless, the model is still not predictive; it needs the help of an experimental datum and a scan over a wide range of values of the parameters defining adhesive force distribution functions to produce results. An uncertainty and sensitivity analysis has been performed by making use of the Monte-Carlo methodology. It has shown that the most important variable in the model is the geometric standard deviation of the adhesive force distribution functions
Availability note (English)
MF available from INIS under the Report Number.
Files
Additional details
Publishing Information
- Imprint Pagination
- 54 p.
- Report number
- EUR--13788
INIS
- Country of Publication
- European Commission (EC), Brussels (Belgium)
- Country of Input or Organization
- European Commission (EC), Brussels (Belgium)
- INIS RN
- 23049009
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- BWR TYPE REACTORS; MELTDOWN; PARTICLE RESUSPENSION; PRIMARY COOLANT CIRCUITS; PWR TYPE REACTORS; R CODES; RADIOACTIVE AEROSOLS; SEDIMENTATION; VERIFICATION
- Descriptors DEC
- ACCIDENTS; AEROSOLS; COLLOIDS; COMPUTER CODES; COOLING SYSTEMS; DISPERSIONS; ENRICHED URANIUM REACTORS; POWER REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; SOLS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Contract/Grant/Project number
- Contract 3571-88-12 ELISPE