A MELCOR-Based Model to Calculate Vapor Natural Circulation in Pressurized Water Reactor High-Pressure Severe Accidents
Author:
Affiliation:
1. Càtedra de Tecnología Nuclear0ETSII, Universidad Politžcnica de Madrid C. Josž Gutižrrez Abascal, 2, 28006, Madrid, Spain
Publisher
Informa UK Limited
Subject
Condensed Matter Physics,Nuclear Energy and Engineering,Nuclear and High Energy Physics
Link
https://www.tandfonline.com/doi/pdf/10.13182/NT99-A2990
Reference6 articles.
1. P. D. BAYLESS et al. “Severe Accident Natural Circulation Studies at the INEL,” NUREG/CR-6285, INEL-94/0016, Idaho National Engineering Laboratory (1995).
2. R. O. GAUNTT et al. “MELCOR Computer Code Manuals,” Version 1.8.4, July 1997, NUREG/CR-6119, Vol. 2, Rev. 1, SAND97-2398, Sandia National Laboratories (1997).
3. AEATECHNOLOGY, “CFX 4.1 Flow Solver User Guide,” Computational Fluid Dynamics Services (1995).
4. A Scenario of the Three Mile Island Unit 2 Accident
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1. Sensitivity study of thermal-hydraulic nodalization for MELCOR simulations of severe accidents in a pressurized water reactor;Annals of Nuclear Energy;2022-02
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