This project includes the MELCOR 1.8.6 model of the IFMIF-DONES main building (under development).
The International Fusion Materials Irradiation Facility – Demo Oriented NEutron Source (IFMIF-DONES) is a single-sited novel research infrastructure for testing, validation and qualification of the materials to be used in future fusion power plants like DEMO (a demonstration fusion reactor prototype). In relation to this international project, in December 2017, Fusion for Energy (F4E) evaluated positively the joint Spain - Croatia proposal to site the IFMIF-DONES in Granada (Spain).
MELCOR (portmanteu from “melting core”) is a fully integrated, engineering-level computer code developed by Sandia National Laboratories for the U.S. Nuclear Regulatory Commission to model the progression of severe accidents in nuclear power plants. A broad spectrum of severe accident phenomena in both boiling and pressurized water reactors is treated in MELCOR in a unified framework. Furthermore, its generalized framework and ability to track aerosol/vapor species makes it applicable for non-nuclear safety related applications. MELCOR applications include estimation of severe accident source terms, and their sensitivities and uncertainties in a variety of applications.
This project is based in MELCOR for fusion, a modified version of the MELCOR code under development at the Sandia National Laboratory in New Mexico for the U.S. Nuclear Regulatory Commission. A fully integrated, engineering level thermal-hydraulics computer code that models the progression of accidents in fusion power plants, including a spectrum of accident phenomena such as reactor cooling system and containment fluid flow, heat transfer, and aerosol transport. Used for accident analysis in ITER’s Preliminary Safety Analysis Report (RPrS) and ARIES Design Team safety analyses.
- Antonio Manjavacas (Universidad de Granada)
- Manuel A. Vázquez (Universidad de Granada)
- Manuel Pérez (CIEMAT)
- Claudio Torregrosa (Universidad de Granada)
- Francisco Martín-Fuertes (CIEMAT)