Analysis of Dracs and DRACS-RVACS decay heat removal experiments
- Argonne National Lab., Reactor Engineering Div., Argonne, IL (US)
This paper reports on two large-scale decay heat removal experiments analyzed to support the validation of the thermal-hydraulic code COMMIX and the design of advanced liquid metal reactors (ALMRs). The experiments were performed in the reactor vessel auxiliary cooling system (RVACS) test facility, which provides a scaled simulation of the passive decay heat removal paths of a pool ALMR with the core simulated by electrically heated rods. The first experiment simulates a transient where decay heat is removed by the direct reactor auxiliary cooling system (DRACS) only. In the second experiment, heat is removed by both the DRACS and RVACS. These experiments are characterized by (a) three-dimensional in-pool sodium flows of very low velocity, driven by sodium density differences, (b) a significant pool thermal stratification, and (c) a complex heat sink.
- DOE Contract Number:
- W-31109-ENG-38
- OSTI ID:
- 5559594
- Journal Information:
- Nuclear Technology; (United States), Vol. 95:3; ISSN 0029-5450
- Country of Publication:
- United States
- Language:
- English
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