BB LOCA analysis for the reference design of the EU DEMO HCPB blanket concept

Jin, Xue Zhou

doi:10.1016/j.fusengdes.2018.04.046

Cited by 19 publications

(11 citation statements)

References 5 publications

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“…In view of this assumption, a first simplification is to neglect the gaps and keep only the main plasma chamber as fluid domain. Then, as the up-down asymmetry is limited to the divertor region, to further reduce the size of the domain a simplified, up-down symmetric geometry is built, according to Figure 2, keeping the same total volume (divided by four, due to up-down and left-right symmetry) of the VV (~ 3000 m 3 ).…”

Section: Scenario and Geometry Descriptionmentioning

confidence: 99%

3D transient CFD simulation of an in-vessel Loss-Of-Coolant Accident in the EU DEMO fusion reactor

Zappatore

Froio

Spagnuolo³

et al. 2020

Nucl. Fusion

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Accidental transients in fusion reactors, such as the in-vessel Loss-of-Coolant Accident (LOCA) considered here, are generally analyzed using system-level codes. However, because of their lumped nature, such tools cannot predict local pressure and temperature values, which are instead of interest to assess the integrity of the Vacuum Vessel (VV) structures. It is then fundamental to prove that the system-level tools' predictions are at least conservative. In this work, we analyze the helium flow inside the VV following a LOCA in the helium-cooled blanket of the EU DEMO, using a 3D transient CFD model implemented in the commercial STAR-CCM+ code. In view of the large pressure ratio, a hypersonic flow regime (Ma > 5) develops, with the formation of shock fronts requiring a high time and space resolution. The model is applied to compute the evolution of the pressure distribution inside the VV and then to compare it with the information provided by the system-level GETTHEM model. The predictions by the two models of the intervention time of the VV pressure suppression system are compared, showing that the 0D model is conservative.

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Section: Scenario and Geometry Descriptionmentioning

confidence: 99%

3D transient CFD simulation of an in-vessel Loss-Of-Coolant Accident in the EU DEMO fusion reactor

Zappatore

Froio

Spagnuolo³

et al. 2020

Nucl. Fusion

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“…More recently, the MELCOR Fusion adapted version 1.8.6-2017 computer code [12] has been exploited for the analysis of integrated HTS containment as part of preliminary safety assessments in pre-conceptual designs of European DEMO concepts [27][28][29][30] as well as in Korean DEMO [31]. Being able to model phenomena relevant for fusion safety applications such as radionuclide transport (e.g., tritiated water) in the presence of a variety of cooling fluids (helium, water, liquid metals) as well as pressure conditions (e.g., vacuum), the MELCOR code has been considered for deterministic safety analyses aimed at the licensing of the DONES plant [5,6], showing good agreement with RELAP5 results [7,32,33].…”

Section: Simulation Models and Approachesmentioning

confidence: 99%

Loss of Liquid Lithium Coolant in an Accident in a DONES Test Cell Facility

Dongiovanni

D’Onorio

2021

Energies

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A Demo-Oriented early NEutron Source (DONES) facility for material irradiation with nuclear is currently being designed. DONES aims to produce neutrons with fusion-relevant spectrum and fluence by means of D–Li stripping reactions occurring between a deuteron beam impacting a stable liquid lithium flowing film implementing the target. Given the hazard constituted by the liquid lithium inventory and the potential risk of reactions with water, air, and concrete eventually resulting in fire events, the Target Test Cell (TTC) is filled with helium and the reinforced concrete walls forming the bio-shield are covered with steel liners. A loss of Li in TTC, due to a large break in the Quench Tank, is postulated, and consequences are deterministically studied. With the TTC liner being water-cooled, the impact of the liner temperature rise following a leakage event is evaluated. Two separate MELCOR code models have been defined for the liquid lithium loop and water-cooled loop and are numerically coupled. The amount of leaked inventory dependent on the implemented safety logic and impact on TTC containment is evaluated. The water pressurization pattern within the liner cooling loop is studied to highlight possible risks of lithium–water/concrete reactions.

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“…In the last years, a large experience was matured in this field. Analyses were performed considering both BB options and using different system codes [6][7][8][9]. Within the framework of EUROfusion Work Package Breeding Blanket, a simulation activity was carried out by Department of Astronautical, Electrical and Energy Engineering (DIAEE) of Sapienza University of Rome in collaboration with ENEA research center of Brasimone.…”

Section: Introductionmentioning

confidence: 99%