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Tritium permeation through the first wall of the EU-HCPB blanket
Fusion Engineering and Design, 2000The Helium Cooled Pebble Bed (HCPB) blanket is one of the two concepts to be further developed for a European DEMO power reactor. Tritium leakage due to the permeation through the main structural materials constitutes one of the main problems of the fusion technology.
Michael A Fütterer
exaly +2 more sources
Preliminary structural analysis of the new HCPB blanket for EU DEMO reactor
International Journal of Hydrogen Energy, 2016Abstract Currently the HCPB blanket concept is one of the four breeding blankets concepts under development for the European DEMO. This work reports on the results of an investigation of the thermal and structural performances of a new design of this blanket, proposed in 2015 by the KIT HCPB Team aimed at establishing a baseline design of the HCPB ...
Guangming Zhou, Hong-Li Chen, Minyou Ye
exaly +3 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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Tritium Extraction Systems for the European HCLL/HCPB TBMs
Fusion Science and Technology, 2008One of the most challenging issues for the TBM (Test Blanket Module) testing campaign foreseen in ITER is the operation of TES (Tritium Extraction Systems).
Ricapito, I. +3 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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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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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
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Helium loop for the HCPB Test Blanket Module
Fusion Engineering and Design, 2007The primary loop for the Helium Cooled Pebble Bed Test Blanket Module (HCPB-TBM) has been investigated with regard to layout definition, selection and dimensioning of components including piping and mechanical integration of the circuit into the different sections of ITER.
Neuberger, H. +4 more
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Numerical benchmark of SuperMC3.2 with HCPB mock-up experiment
Fusion Engineering and Design, 2019Abstract In fusion reactors, the blanket is one of the crucial components which play the key role of breeding tritium. This is necessary because there sufficient external tritium supply is not available for fusion reactors. Furthermore, blankets have to provide shielding for ex-vessel components, which are sensitive to the radiation (e.g., Toroidal ...
Bin Li +5 more
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Helium loops of an ITER HCPB test blanket module
17th IEEE/NPSS Symposium Fusion Engineering (Cat. No.97CH36131), 2002The operation of a He cooled pebble bed (HCPB) test blanket module for ITER requires three helium loops which are being designed for (a) tritium extraction, (b) heat removal, and (c) coolant purification. The main design data as well as flow diagrams of the loops are presented.
Albrecht, H. +3 more
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