CFX simulations of ROCOM slug mixing experiments
- 1. DIMNP, University of Pisa, Pisa (Italy)
- 2. Forschungszentrum Dresden-Rossendorf, Dresden (Germany)
Description
The present paper documents the CFD code validation activity carried out at the University of Pisa. In particular, the ANSYS CFX-10.0 code was used to simulate one of the experiments conducted at the ROCOM mixing test facility (FZD, Germany), that reproduced the injection of a de-borated slug in one cold leg of a pressurized water reactor (simulated by a salt tracer) with all circulation pumps at steady-state operation. The calculations were run on several grids obtained through different meshing strategies and having different sizes. The numerical results, in terms of normalized concentration of the transported passive scalar in the downcomer and at the core inlet, were compared against corresponding values obtained through experimental measurements of electrical conductivity in the ROCOM facility. Such comparison resulted in a general good qualitative agreement between simulations and experiments, while some discrepancies were evidenced from a quantitative point of view. (author)
Additional details
Identifiers
- DOI
- 10.1299/jpes.2.720;
Publishing Information
- Journal Title
- Journal of Power and Energy Systems
- Journal Volume
- 2
- Journal Issue
- 2
- Journal Page Range
- p. 720-733
- ISSN
- 1881-3062
Conference
- Title
- 15. international conference on nuclear engineering
- Acronym
- ICONE-15
- Dates
- 22-26 Apr 2007
- Place
- Nagoya, Aichi (Japan)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 39106762
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- A CODES; BORON; COMPUTERIZED SIMULATION; DILUTION; ECCS; FLUID FLOW; FLUID MECHANICS; INJECTION; MIXING; PWR TYPE REACTORS; THERMAL HYDRAULICS; TRANSIENTS; TURBULENCE; VALIDATION
- Descriptors DEC
- COMPUTER CODES; ELEMENTS; ENGINEERED SAFETY SYSTEMS; ENRICHED URANIUM REACTORS; FLUID MECHANICS; HYDRAULICS; INTAKE; MECHANICS; POWER REACTORS; REACTOR PROTECTION SYSTEMS; REACTORS; SEMIMETALS; SIMULATION; TESTING; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- Available from doi: http://dx.doi.org/10.1299/jpes.2.720; 7 refs., 23 figs., 2 tabs.