Results 41 to 50 of about 2,654 (112)

Design of the WCLL BB in view of the conceptual design phase

open access: yesFusion Engineering and Design
In view of the definition of the driver blanket for the EU-DEMO fusion reactor, three Breeding Blanket (BB) concepts are being studied in the framework of EUROfusion consortium activities. In mid-2020 two of these concepts, the Water Cooled Lead-Lithium (WCLL) and the Helium Cooled Pebble Bed (HCPB), were reviewed by a panel of external experts to ...
Pietro Arena   +36 more
openaire   +2 more sources

The effect of concrete strength and reinforcement on toughness of reinforced concrete beams [PDF]

open access: yes, 2005
The objective pursued with this work includes the evaluating of the strength and the total energy absorption capacity (toughness) of reinforced concrete beams using different amounts of steel-bar reinforcement.
Carneiro, Joaquim A. O.   +3 more
core   +1 more source

Dedicated thermal, thermal-hydraulic and thermal-mechanical analyses in support of DEMO WCLL BB design

open access: yes, 2023
Within the framework of the EUROfusion Work Package Breeding Blanket (WPBB), R&D activities are carried out since 2021 in CEA on the conceptual design of the DEMO Water-Cooled Lithium Lead Breeding Blanket (WCLL BB) for the inboard segment.Geometry optimizations have been performed to comply with the RCC-MRx rules (thermomechanicalstresses) and the ...
Chelihi, Brahim   +4 more
openaire   +1 more source

Validation of SIMMER-III code for in-box LOCA of WCLL BB: Pre-test numerical analysis of Test D1.1 in LIFUS5/Mod3 facility

open access: yesFusion Engineering and Design, 2019
Abstract One of the four breeding blanket concepts for European DEMO nuclear fusion reactor is the Water-Cooled Lithium Lead Breeding Blanket (WCLL BB). The WCLL in-box LOCA (Loss Of Coolant Accident) is a major safety concern of this component, therefore transient behavior shall be investigated to support the design, to evaluate the consequences and
Moghanaki, Samad Khani   +4 more
openaire   +2 more sources

Spartan Daily, May 11, 2016 [PDF]

open access: yes, 2016
Volume 146, Issue 41https://scholarworks.sjsu.edu/spartan_daily_2016/1039/thumbnail ...
San Jose State University, School of Journalism and Mass Communications
core   +2 more sources

Dose rate evaluation in the technical premises of the demo fusion reactor using the serpent Monte Carlo code [PDF]

open access: yesNuclear Technology and Radiation Protection
This paper presents a dose rate assessment within the DEMO fusion reactor's auxiliary premises, focusing on activated water and Activated Corrosion Products as primary radiation sources.
Sereda Svitlana   +4 more
doaj   +1 more source

Main Nuclear Responses of the DEMO Tokamak with Different In-Vessel Component Configurations

open access: yesApplied Sciences
Research and development of the DEMOnstration power plant (DEMO) breeder blanket (BB) has been performed in recent years based on a predefined DEMO tritium breeding ratio (TBR) requirement, which determines a loss of wall surface due to non-breeding in ...
Jin Hun Park, Pavel Pereslavtsev
doaj   +1 more source

Thermal-hydraulic analysis of WCLL BB First-Wall mock-up in Water Loop facility under transient conditions

open access: yesFusion Engineering and Design
The EUropean DEMOnstration Power Plant (EU-DEMO) represents a milestone in nuclear fusion research, serving as crucial step towards the realization of commercial fusion energy production by bridging the gap between current research efforts and future industrial-scale deployment.
Mongiardini, G.   +8 more
openaire   +1 more source

Optimized Water Distillation Layout for Detritiation Purpose

open access: yesApplied Sciences
Tritium permeation constitutes a key issue for the future EU-DEMO, especially in the Breeding Blanket (BB) where fusion energy must be delivered to the Primary Heat Transport System (PHTS) and where tritium must be bred.
Vincenzo Narcisi, Alessia Santucci
doaj   +1 more source

The chemical compatibility of oxide ceramic candidates in static PbLi for advanced breeding blanket channel components

open access: yesNuclear Materials and Energy
The use of a PbLi eutectic alloy is extended in the Dual Coolant Lead Lithium (DCLL) and Water Coolant Lead Lithium (WCLL) Breeding Blanket (BB) design concepts in future fusion reactors.
J. Patiño   +3 more
doaj   +1 more source

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