https://github.com/manjavacas/melcor-ifmif-dones

MELCOR fusion (1.8.6) model of the IFMIF-DONES main building.
https://github.com/manjavacas/melcor-ifmif-dones

fusion ifmif-dones melcor melcor-fusion safety simulation

Last synced: about 2 months ago
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MELCOR fusion (1.8.6) model of the IFMIF-DONES main building.

• Host: GitHub
• URL: https://github.com/manjavacas/melcor-ifmif-dones
• Owner: manjavacas
• Created: 2022-07-18T10:40:06.000Z (over 2 years ago)
• Default Branch: main
• Last Pushed: 2023-11-13T09:27:01.000Z (over 1 year ago)
• Last Synced: 2024-11-06T04:37:35.429Z (3 months ago)
• Topics: fusion, ifmif-dones, melcor, melcor-fusion, safety, simulation
• Language: Python
• Homepage: https://ifmif-dones.es/
• Size: 104 MB
• Stars: 3
• Watchers: 2
• Forks: 0
• Open Issues: 0
• Metadata Files:
  • Readme: README.md

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README

        
## 📝 About

This project includes the [MELCOR 1.8.6 model](https://energy.sandia.gov/programs/nuclear-energy/nuclear-energy-safety-security/melcor/) of the [IFMIF-DONES](https://ifmif-dones.es/) main building (**under development**).

## ⚛️ IFMIF-DONES

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](https://www.euro-fusion.org/programme/demo/) (a demonstration fusion reactor prototype). In relation to this international project, in December 2017, [Fusion for Energy](https://fusionforenergy.europa.eu/) (F4E) evaluated positively the joint Spain - Croatia proposal to site the IFMIF-DONES in **Granada** (Spain).

## 🖥️ MELCOR

**MELCOR** (portmanteu from “melting core”) is a fully integrated, engineering-level computer code developed by [Sandia National Laboratories](https://www.sandia.gov/) 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](https://fusionsafety.inl.gov/SitePages/Fusion%20Safety%20Codes.aspx), 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](https://www.iter.org/)’s Preliminary Safety Analysis Report (RPrS) and ARIES Design Team safety analyses.

## 👥 Contributors

* [Antonio Manjavacas](mailto:[email protected]) (Universidad de Granada)

* [Manuel A. Vázquez](mailto:[email protected]) (Universidad de Granada)

* [Manuel Pérez](mailto:[email protected]) (CIEMAT)

* [Claudio Torregrosa]([email protected]) (Universidad de Granada)

* [Francisco Martín-Fuertes]([email protected]) (CIEMAT)