[HTML][HTML] Integrated design of breeding blanket and ancillary systems related to the use of helium or water as a coolant and impact on the overall plant design

GA Spagnuolo, R Arredondo, LV Boccaccini… - Fusion Engineering and …, 2021 - Elsevier
Currently, for the EU DEMO, two Breeding Blankets (BBs) have been selected as potential
candidates for the integration in the reactor. They are the Water Cooled Lithium Lead and …

A novel approach to high-pressure gas releases simulations

A Moscatello, AC Uggenti, R Gerboni… - Journal of Loss …, 2021 - Elsevier
Risk-relevant plants like Oil & Gas (O&G) or nuclear ones are subjected to strict safety
regulations. Risk Assessment is mandatory for these plants, and the damage quantification …

Pressure wave behavior and its effects on structure under In-box LOCA in a helium-cooled lead lithium blanket of hydrogen fusion reactors

S Zhang, Z Wang, C Chen, J Jia, Z Chen - International Journal of …, 2021 - Elsevier
The helium-cooled lead lithium (PbLi) blanket is considered as one of the candidate blanket
concepts selected for the hydrogen fusion DEMO reactors and beyond, which has the …

Demonstration of RELAP5-3D for transient analysis of a dual coolant lead lithium fusion blanket concept

N Meehan, GI Maldonado, NR Brown - Fusion Engineering and Design, 2022 - Elsevier
Our research aims to build a multiphysics framework for transient analysis of the Dual-
Coolant Lead-Lithium (DCLL) blanket design of the proposed Fusion Nuclear Science …

Analysis of the effects of primary heat transfer system isolation valves in case of in-vessel loss-of-coolant accidents in the EU DEMO

A Froio, L Barucca, S Ciattaglia, F Cismondi… - Fusion engineering and …, 2020 - Elsevier
As DEMO is the first European device planned to produce electricity from fusion, the volume
of its Primary Heat Transfer Systems (PHTS) will be consistently larger if compared to …

3D transient CFD simulation of an in-vessel loss-of-coolant accident in the EU DEMO WCLL breeding blanket

M Sprò, A Froio, A Zappatore - Energies, 2023 - mdpi.com
The in-vessel Loss-of-Coolant Accident (LOCA) is one of the design basis accidents in the
design of the EU DEMO tokamak fusion reactor. System-level codes are typically employed …

[HTML][HTML] Deterministic analysis of residual heat removal from activated EU DEMO WCLL BB segments during ex-vessel LOCA

M Draksler, B Končar, C Bachmann, I Moscato… - Fusion Engineering and …, 2024 - Elsevier
The residual heat removal from the activated EU DEMO WCLL breeding blankets (BB) in the
event of impaired cooling due to an ex-vessel Loss of Coolant Accident (LOCA) is …

Phenomena Identification and Ranking Table for Thermal-Hydraulic Safety of China Fusion Engineering Test Reactor

J Jiang, Y Qin, L Tong, X Cao, S Liu… - Fusion Science and …, 2024 - Taylor & Francis
Abstract The China Fusion Engineering Test Reactor (CFETR) is presently in the
engineering design phase, and it is crucial to establish a thermal-hydraulic safety analysis …

Numerical analysis of supersonic jet flow and dust transport induced by air ingress in a fusion reactor

BE Wang, SC Zhang, Z Wang, JT Jia… - Nuclear Science and …, 2021 - Springer
During a loss of vacuum accident (LOVA), the air ingress into a vacuum vessel (VV) may
lead to radioactive dust resuspension, migration, and even explosion, thereby posing a …

Requirements for the EUCLID-F Integral Code for the Deterministic Analysis of Accidents in Fusion Reactors

RB Bahdanovich, AE Aksenova, VP Bereznev… - Physics of Atomic …, 2023 - Springer
Justification of fusion reactor safety is impossible without multiphysics codes that make it
possible to model many coupled physical and chemical phenomena. Currently, multimodule …