Results 51 to 60 of about 2,134 (206)

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

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

Design Features and Simulation of the New-Build HELOKA-US Facility for the Validation of the DEMO Helium-Cooled Pebble Bed Intermediate Heat Transport and Storage System

open access: yesJournal of Nuclear Engineering, 2022
For the EU-DEMO Helium-Cooled Pebble Bed (HCPB) concept, an indirect coupled design (ICD) with a molten salt (MS) loop as an intermediate heat transport and storage system (IHTS) is considered for the conceptual design phase.
Xiaoyang Gaus-Liu   +4 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

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

DERMA: A Melanoma Diagnosis Platform Based on Collaborative Multilabel Analog Reasoning

open access: yesThe Scientific World Journal, Volume 2014, Issue 1, 2014., 2014
The number of melanoma cancer‐related death has increased over the last few years due to the new solar habits. Early diagnosis has become the best prevention method. This work presents a melanoma diagnosis architecture based on the collaboration of several multilabel case‐based reasoning subsystems called DERMA.
Ruben Nicolas   +7 more
wiley   +1 more source

A Thermal Discrete Element Analysis of EU Solid Breeder Blanket subjected to Neutron Irradiation

open access: yes, 2014
Due to neutron irradiation, solid breeder blankets are subjected to complex thermo-mechanical conditions. Within one breeder unit, the ceramic breeder bed is composed of spherical-shaped lithium orthosilicate pebbles, and as a type of granular material ...
Annabattula, Ratna   +5 more
core   +1 more source

Use of Nuclear Data Sensitivity and Uncertainty Analysis for the Design Preparation of the HCLL Breeder Blanket Mockup Experiment for ITER

open access: yesScience and Technology of Nuclear Installations, Volume 2008, Issue 1, 2008., 2008
An experiment on a mockup of the test blanket module based on helium‐cooled lithium lead (HCLL) concept will be performed in 2008 in the Frascati Neutron Generator (FNG) in order to study neutronics characteristics of the module and the accuracy of the computational tools. With the objective to prepare and optimise the design of the mockup in the sense
I. Kodeli, Igor Jencic
wiley   +1 more source

Preliminary estimates of tritium permeation and retention in the first wall of DEMO due to ion bombardment

open access: yesNuclear Materials and Energy, 2021
Tritium self-sufficiency presents a critical engineering challenge for DEMO, requiring efficient breeding and extraction systems, as well as minimizing tritium losses to the surrounding systems, such as plasma-facing components, vacuum vessel, cooling ...
R. Arredondo   +3 more
doaj   +1 more source

Preliminary safety studies for the DEMO HCPB blanket concept

open access: yesFusion Engineering and Design, 2015
Abstract Helium Cooled Pebble Bed (HCPB) blanket concept is one of the DEMO (Demonstration Power Plant) blanket concepts running for the final design selection. Concept relevant safety needs to be addressed at the early stage of the design. In this paper the preliminary safety studies for the current concept have been performed with respect to the ...
Jin, X.   +5 more
openaire   +4 more sources

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