Results 41 to 50 of about 905 (186)

Statistical Analysis of Tritium Breeding Ratio Deviations in the DEMO Due to Nuclear Data Uncertainties

open access: yesApplied Sciences, 2021
For the stable and self-sufficient functioning of the DEMO fusion reactor, one of the most important parameters that must be demonstrated is the Tritium Breeding Ratio (TBR).
Jin Hun Park   +3 more
doaj   +1 more source

Validation of Multi-Physics Integrated Procedure for the HCPB Breeding Blanket

open access: yesInternational Journal of Computational Methods, 2019
The wide range of requirements and constraints involved in the design of nuclear components for fusion reactors makes the development of multi-physics analysis procedures of utmost importance. In the framework of the European DEMO project, the Karlsruhe Institute of Technology (KIT) is dedicating several efforts to the development of a multi-physics ...
R. Favetti   +3 more
openaire   +7 more sources

Activation Analyses of Disposal Options for Irradiated Be12Ti

open access: yesApplied Sciences, 2023
The activity and disposal options for irradiated Be12Ti were assessed for the HCPB DEMO blankets making use of a code system that enables performing 3D activation calculations by linking the Monte Carlo transport code MCNP and the fusion inventory code ...
Pavel Pereslavtsev   +2 more
doaj   +1 more source

Fabrication technologies implemented for the European test blanket modules: Status for HCPB and WCLL

open access: yes, 2021
International audienceWithin the framework of the European fusion strategy, two tritium Breeder Blankets concepts are developed to be tested in ITER as Test Blanket Modules (TBM): the Water-Cooled Lithium-Lead (WCLL) which uses the liquid Pb-16Li as a ...
Simon-Perret, Melchior   +11 more
core   +1 more source

NUCLEAR DATA SENSITIVITY/UNCERTAINTY PRE-ANALYSIS OF FNG WCLL FUSION BENCHMARK [PDF]

open access: yesEPJ Web of Conferences, 2021
To assure tritium self-sufficiency in future fusion reactors such as DEMO the accuracy of TRP calculations has to be demonstrated within the design uncertainties.
Kodeli Ivan A.   +2 more
doaj   +1 more source

Activities in Divertor Reflector and Linear Plates Using WCLL and HCPB Breeding Blanket Concepts

open access: yesEnergies, 2021
In fusion devices, such as European Demonstration Fusion Power Reactor (EU DEMO), primary neutrons can cause material activation due to the interaction between the source particles and the targeting material.
Simona Breidokaite, Gediminas Stankunas
doaj   +1 more source

Design update, thermal and fluid dynamic analyses of the EU-HCPB TBM in vertical arrangement

open access: yes, 2009
In the frame of the activities of the EU Breeder Blanket Programme and of the Test Blanket Working Group of ITER, the Helium Cooled Pebble Bed Test Blanket Module (HCPB TBM) is developed in Forschungszentrum Karlsruhe (FZK) to investigate DEMO relevant ...
Dolensky, B.   +12 more
core   +1 more source

Exploratory tritium breeding performance study on a water cooled lead ceramic breeder blanket for EU DEMO using Serpent-2

open access: yesNuclear Materials and Energy, 2021
Innovative Water cooled Lead Ceramic Breeder (WLCB) blanket concepts are being developed at Karlsruhe Institute of Technology (KIT) to explore alternative options for the European demonstration fusion power plant (DEMO).
Yudong Lu   +5 more
doaj   +1 more source

Post-Test Numerical Analysis of a Helium-Cooled Breeding Blanket First Wall under LOFA Conditions with the MELCOR Fusion Code

open access: yesApplied Sciences, 2021
The validation of numerical tools employed in the analysis of incidental transients in a fusion reactor is a topic of main concern. KIT is taking part in this task providing both experimental data and by performing numerical analysis in support of the ...
Michela Angelucci   +6 more
doaj   +1 more source

Normal and Accidental Scenarios Analyses with MELCOR 1.8.2 and MELCOR 2.1 for the DEMO Helium‐Cooled Pebble Bed Blanket Concept

open access: yesScience and Technology of Nuclear Installations, Volume 2015, Issue 1, 2015., 2015
As for Light Water Reactors (LWRs), one of the most challenging accidents for the future DEMOnstration power plant is the Loss of Coolant Accident, which can trigger the pressurization of the confinement structures and components. Hence, careful analyses have to be executed to demonstrate that the confinement barriers are able to withstand the pressure
Bruno Gonfiotti   +2 more
wiley   +1 more source

Home - About - Disclaimer - Privacy