Results 171 to 180 of about 2,181 (197)
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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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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
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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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RAMI analysis for DEMO HCPB blanket concept cooling system
Fusion Engineering and Design, 2015Abstract 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 N. Dongiovanni +2 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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Tritium analysis for the european HCPB TBM in ITER
21st IEEE/NPS Symposium on Fusion Engineering SOFE 05, 2005Tritium inventory and permeation are important data for a breeding blanket of a fusion reactor. For the HCPB TBM in ITER a first attempt has been done to calculate these data at the design stage using available analysis tools.
Meyder, R. +2 more
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Non-linear failure analysis of HCPB Test Blanket Module
Fusion Engineering and Design, 2012Abstract For the European Helium Cooled Pebble Bed Test Blanket Module (HCPB-TBM) the reduced activation ferritic martensitic (RAFM) steel EUROFER 97 is selected as a structural material. During operation the TBM will be subjected to complex thermo-mechanical loadings which yield at certain positions of the structure to stresses beyond the design ...
Aktaa, J., Kecskes, S., Cismondi, F.
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