ALLEGRO Core Degradation Study using MELCOR 2.1
Petr Vacha, Ladislav Belovsky

TL;DR
This study uses MELCOR 2.1 to analyze core degradation in the ALLEGRO GFR reactor under various accident scenarios, providing data crucial for safety design improvements.
Contribution
It extends previous analyses by evaluating core degradation at reduced power levels and specific accident scenarios using MELCOR 2.1.
Findings
Core degradation timing and extent identified
Data supports core catcher design in ALLEGRO
Analysis of accident scenarios with primary coolant loss
Abstract
ALLEGRO is an experimental high-temperature gas (He)-cooled fast reactor (GFR) under development by the European Consortium V4G4 Centre of Excellence on basis of the concept ALLEGRO presented by CEA in 2009. Its main purpose is to demonstrate the viability of GFR in pilot scale and simultaneously serve as a test bed for GFR-related technologies, above all the high-temperature resistant refractory fuel in the conventional oxide fuel driver core. Severe accident studies of the concept with the first core (oxide fuel in stainless steel claddings) are an important part of safety analyses leading to improves in reactor design and safety. This paper extends our previous study using the MELCOR code. Major difference between the previous and this work is decrease of thermal power and power density to 50 MWth and 66,6 MWth/m3 respectively. Analyses are focused on protected scenarios based on…
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Taxonomy
TopicsNuclear Materials and Properties · Nuclear reactor physics and engineering · Nuclear Engineering Thermal-Hydraulics
