Results 151 to 160 of about 905 (186)
Tritium transport analysis in HCPB DEMO blanket with the FUS-TPC code
Fusion Engineering and Design, 2013 Abstract In the breeding areas a significant fraction of the tritium produced is extracted out from the Breeding Zone by the He gas purging the breeding ceramic in the helium cooled pebble bed (HCPB) blanket concept or transported in solution by the flowing liquid metal alloy in the helium cooled lead lithium (HCLL) blanket concept and then extracted
L V Boccaccini +2 more
exaly +7 more sources
RAMI analysis for DEMO HCPB blanket concept cooling system
Fusion Engineering and Design, 2015 Abstract A preliminary RAMI (reliability, availability, maintainability and inspectability) assessment for the HCPB (helium cooled pebble bed) blanket cooling system based on currently available design for DEMO fusion power plant is presented. The following sub-systems were considered in the analysis: blanket modules, primary cooling loop including ...
Danilo Nicola Dongiovanni, Tonio Pinna
exaly +3 more sources
An enhanced, near-term HCPB design as driver blanket for the EU DEMO
Fusion Engineering and Design, 2019 Abstract The Helium Cooled Pebble Bed (HCPB) breeding blanket is a candidate as driver blanket for the EU DEMO. The reference design of the HCPB is based on a cooling plate “sandwich” arrangement built in Multi-Module Segments. This architecture significantly improved the tritium breeding performance (TBR = 1.15) and the plant circulating power (≈130
FRANCISCO A Hernández +2 more
exaly +4 more sources
Fusion Engineering and Design, 2020 Abstract From 2014 to 2020, the Pre-Conceptual Design phase (PCD) of the EU DEMO has taken place. The activities in the PCD phase differ from past exercises in their strong Systems Engineering methodology, as well as for the pragmatic approach in their technology choices.
FRANCISCO A Hernández +2 more
exaly +7 more sources
Tritium modelling in HCPB breeder blanket at a system level
Fusion Engineering and Design, 2017 Abstract Tritium behavior in a DEMO reactor is a key design issue because of its self-sufficiency and impact on safety. Considering the difficulty in handling tritium, and that the transport, diffusion and permeation phenomena involve a large number of physical properties and parameters, it is intended to prepare a simulation tool to predict its ...
E Carella, C Moreno, F R Urgorri
exaly +3 more sources
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Tritium transport analysis of HCPB blanket for CFETR
Fusion Engineering and Design, 2016Abstract Based on the HCPB (Helium-Cooled Pebble Bed) blanket of CFETR (Chinese Fusion Engineering Testing Reactor), a more detailed tritium cycle model of HCPB blanket was developed by modeling the breeding parts inside the blanket separately. Utilizing the detailed model, tritium transport analysis of HCPB blanket was carried out.
Lei Pan, Hongli Chen, Qin Zeng
exaly +2 more sources
Developments on the tritium extraction and recovery system for HCPB
Fusion Engineering and Design, 2020Abstract The tritium release from the ceramic materials of the DEMO Breading Blanket (BB) is a complex mechanism due mainly to the chemistry of the interface between the breeder material and the purge gas. The tritium atomic form produced inside the ceramics structure is converted into tritiated water at the surface of the breeder material due to ...
Cristescu, I., Draghia, M.
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Analyses of the shielding options for HCPB DEMO blanket
Fusion Engineering and Design, 2020Abstract The enhancement of the HCPB DEMO blanket shielding capability is a challenging issue that assumes complex studies involving numerous neutronics analyses based on the Monte Carlo simulations with MCNP code. To this end very detailed, fully heterogeneous MCNP geometry models were developed for the latest designs of the HCPB and WCLL DEMO ...
Pereslavtsev, Pavel +2 more
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Conceptual design of a hybrid HCPB blanket
Fusion Engineering and Design, 2001Abstract Following previous studies on helium cooled pebble bed (HCPB) blanket concepts based on different structural materials, a hybrid HCPB blanket has been proposed to combine the high load capability of the steel concepts with the high thermal efficiency of the SiC f /SiC ones.
Boccaccini, L. V. +3 more
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Comparative activation analyses for the HCPB breeding blanket in DEMO
Fusion Engineering and Design, 2021Abstract The Helium Cooled Pebble Bed (HCPB) breeding blanket is one out of two concepts considered as driver blanket for the European DEMOnstration fusion power plant. The latest design, developed within the Breeding Blanket project of EUROfusion’s Power Plant Physics and Technology (PPPT) programme, assumes a fission-like breeder pin arrangement ...
Park, Jin Hun, Pereslavtsev, Pavel
openaire +2 more sources