Results 91 to 100 of about 905 (186)

A methodology for thermo-mechanical assessment of in-box LOCA events on fusion blankets and its application to EU DEMO HCPB breeding blanket

open access: yes, 2017
Within the framework of EUROfusion research activities, the Karlsruhe Institute of Technology (KIT) is developing the Helium Cooled Pebble Bed (HCPB) breeding blanket (BB) for European demonstration fusion power plant (DEMO), with the support of BME and ...
Zeile, Christian   +8 more
core   +2 more sources

Experimental and Numerical Analysis of a Pd-Ag Membrane Unit for Hydrogen Isotope Recovery in a Solid Blanket. [PDF]

open access: yesMembranes (Basel), 2023
Narcisi V   +5 more
europepmc   +1 more source

Preliminary accident analysis of the loss of vacuum in vacuum vessel for the European DEMO HCPB blanket concept

open access: yesNuclear Fusion
Design basis accidents are investigated continuously for the European DEMO reactor accompanying its development. One selected postulated initial event (PIE) is a loss of vacuum (LOVA) in vacuum vessel (VV) with large ingress of air induced by rupture in ...
Xue Zhou Jin, Wolfgang Raskob
doaj   +1 more source

Hyperfine interactions of paramagnetic radiation-induced defect centres in advanced ceramic breeder pebbles

open access: yesNuclear Materials and Energy
Advanced ceramic breeder (ACB) pebbles consisting of 65 mol% lithium orthosilicate (Li4SiO4) and 35 mol% lithium metatitanate (Li2TiO3) are developed for tritium breeding in the European Union’s (EU) helium cooled pebble bed (HCPB) breeder blanket ...
Andris Antuzevics   +7 more
doaj   +1 more source

Design of a multi-isotopic hydrogen co- and counter-permeation experiment for HCPB related tritium mitigation studies

open access: yes, 2022
A safe operation of the HCPB breeding blanket requires tritium permeation from the breeder into the coolant to be kept as low as possible. Previous studies could identify co- and counter-permeation of different hydrogen isotopes as a method to affect the
Molla, J.   +4 more
core  

Implications of T loss in first wall armor and structural materials on T-self-sufficiency in future burning fusion devices

open access: yesNuclear Fusion
Future fusion reactors will have to breed enough tritium (T) to sustain continuous operation and to produce excess T to power up other fusion reactors. Therefore, T is a scarce resource that must not be lost inside the fusion power plants systems.
K. Schmid   +4 more
doaj   +1 more source

Experimental tests on Li-ceramic breeders for the helium cooled pebble bed (HCPB) blanket design

open access: yes, 2003
The Helium Cooled Pebble Bed (HCPB) Test Blanket Module (TBM) to be tested in ITER (International Thermonuclear Experimental Reactor) Reactor foresees the utilization of Lithiate ceramics as Tritium breeder in form of pebble beds.
DELL'ORCO, G   +5 more
core   +1 more source

Dedicated thermo-mechanical analyses in support of DEMO HCPB BB design

open access: yesFusion Engineering and Design
Within the framework of the EUROfusion Work Package Breeding Blanket for the fusion reactor DEMO, several concepts of Breeding Blanket (BB) are considered. One of the concepts being investigated is the Helium Cooled Pebble Bed (HCPB) BB. The present study focuses on the assessment of this component from the steady-state thermal and thermo-mechanical ...
Brahim Chelihi   +3 more
openaire   +4 more sources

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