Pressure suppression system influence on vacuum vessel thermal-hydraulics and on source term mobilization during a multiple first Wall – Blanket pipe break

D’Onorio, Matteo; Caruso, Gianfranco

doi:10.1016/j.fusengdes.2020.112224

Cited by 9 publications

(9 citation statements)

References 20 publications

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“…As in the previous scenario, the reaction between steam and tungsten dust deposited on the FW surface and the divertor surface has not been considered in this simulation. Moreover, and as in the in-VV LOCA case, it is supposed that about 671.0 g of mobilizable tritium [12] in VV can chemically react with the catalytic layer of the PARs.…”

Section: Lofa Scenariomentioning

confidence: 95%

“…The VVPSS is connected with the VV by means of pipework's routing from the VV upper port area [12]. The preliminary VVPSS configuration is shown in Figure 1 and includes:…”

Section: Vv-vvpss Melcor Modelmentioning

confidence: 99%

“…• 1 ST for small leakages • 5 ST for DBA events • 5 Rupture Disks (break setpoint 150 kPa) in order to take into account a sufficient safety margin from the Design Pressure of 200 kPa [13][14]. • 6 Bleed Lines to avoid the burst of the RD in case of small leakage (opening setpoint 90 kPa)…”

Section: Vv-vvpss Melcor Modelmentioning

confidence: 99%

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Hydrogen explosion mitigation in DEMO vacuum vessel pressure suppression system using passive recombiners

Mazzini

D’Onorio

Caruso

2021

Fusion Engineering and Design

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Section: Lofa Scenariomentioning

confidence: 95%

“…The VVPSS is connected with the VV by means of pipework's routing from the VV upper port area [12]. The preliminary VVPSS configuration is shown in Figure 1 and includes:…”

Section: Vv-vvpss Melcor Modelmentioning

confidence: 99%

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Hydrogen explosion mitigation in DEMO vacuum vessel pressure suppression system using passive recombiners

Mazzini

D’Onorio

Caruso

2021

Fusion Engineering and Design

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“…A description of the MELCOR nodalization is summarized below, focusing on the PHTS and TCR components, which are relevant for this study. Nodalization details on other systems, such as the VV or the VVPSS, are reported in [33,34].…”

Section: Melcor 186 For Fusion Eu-demo Thermal-hydraulic Modelmentioning

confidence: 99%

Development of a Thermal-Hydraulic Model for the EU-DEMO Tokamak Building and LOCA Simulation

et al. 2023

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The EU-DEMO must demonstrate the possibility of generating electricity through nuclear fusion reactions. Moreover, it must denote the necessary technologies to control a powerful plasma with adequate availability and to meet the safety requirements for plant licensing. However, the extensive radioactive materials inventory, the complexity of the plant, and the presence of massive energy sources require a rigorous safety approach to fully realize fusion power’s environmental advantages. The Tokamak building barrier design must address two main issues: radioactive mass transport hazards and energy-related or pressure/vacuum hazards. Safety studies are performed in the frame of the EUROfusion Safety And Environment (SAE) work package to support design improvement and evaluate the thermal-hydraulic behavior of confinement building environments during accident conditions in addition to source term mobilization. This paper focuses on developing a thermal-hydraulic model of the EU-DEMO Tokamak building. A preliminary model of the heat ventilation and air conditioning system and vent detritiation system is developed. A loss-of-coolant accident is studied by investigating the Tokamak building pressurization, source term mobilization, and release. Different nodalizations were compared, highlighting their effects on source term estimation. Results suggest that the building design should be improved to maintain the pressure below safety limits; some mitigative systems are preliminarily investigated for this purpose.

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“…The main simulation purpose was assessing the hydrogen production and the radiological source term mobilization in order to demonstrate the consistency of the EU-DEMO design with the safety and environmental criteria. MELCOR code was also used for a parametrical study in support of the reactor Vacuum Vessel Pressure Suppression System design, as described in [13]. A preliminary analysis of the Loss Of Flow Accident (LOFA) is reported in [14].…”

Section: Introductionmentioning

confidence: 99%

Study of the EU-DEMO WCLL Breeding Blanket Primary Cooling Circuits Thermal-Hydraulic Performances during Transients Belonging to LOFA Category

et al. 2021

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The Breeding Blanket (BB) is one of the key components of the European Demonstration (EU-DEMO) fusion reactor. Its main subsystems, the Breeder Zone (BZ) and the First Wall (FW), are cooled by two independent cooling circuits, called Primary Heat Transfer Systems (PHTS). Evaluating the BB PHTS performances in anticipated transient and accident conditions is a relevant issue for the design of these cooling systems. Within the framework of the EUROfusion Work Package Breeding Blanket, it was performed a thermal-hydraulic analysis of the PHTS during transient conditions belonging to the category of “Decrease in Coolant System Flow Rate”, by using Reactor Excursion Leak Analysis Program (RELAP5) Mod3.3. The BB, the PHTS circuits, the BZ Once Through Steam Generators and the FW Heat Exchangers were included in the study. Selected transients consist in partial and complete Loss of Flow Accident (LOFA) involving either the BZ or the FW PHTS Main Coolant Pumps (MCPs). The influence of the loss of off-site power, combined with the accident occurrence, was also investigated. The transient analysis was performed with the aim of design improvement. The current practice of a standard Pressurized Water Reactor (PWR) was adopted to propose and study actuation logics related to each accidental scenario. The appropriateness of the current PHTS design was demonstrated by simulation outcomes.

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Pressure suppression system influence on vacuum vessel thermal-hydraulics and on source term mobilization during a multiple first Wall – Blanket pipe break

Cited by 9 publications

References 20 publications

Hydrogen explosion mitigation in DEMO vacuum vessel pressure suppression system using passive recombiners

Hydrogen explosion mitigation in DEMO vacuum vessel pressure suppression system using passive recombiners

Development of a Thermal-Hydraulic Model for the EU-DEMO Tokamak Building and LOCA Simulation

Study of the EU-DEMO WCLL Breeding Blanket Primary Cooling Circuits Thermal-Hydraulic Performances during Transients Belonging to LOFA Category

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