X
Search Filters
Format Format
Subjects Subjects
Subjects Subjects
X
Sort by Item Count (A-Z)
Filter by Count
nuclear science & technology (90) 90
hcll (62) 62
lithium (43) 43
demo (37) 37
tritium (34) 34
analysis (31) 31
helium (30) 30
iter (30) 30
design (24) 24
nuclear reactors (22) 22
breeding blanket (21) 21
blanket (19) 19
hcll blanket (19) 19
fusion (18) 18
tbm (16) 16
blanketing (15) 15
magnetohydrodynamics (13) 13
neutronics (12) 12
hcll-tbm (11) 11
hcpb (11) 11
modules (11) 11
mathematical models (10) 10
neutron (10) 10
permeation (10) 10
design engineering (9) 9
fluid dynamics (9) 9
hcll tbm (9) 9
magnetic fields (9) 9
physics, fluids & plasmas (9) 9
nuclear engineering (8) 8
nuclear safety (8) 8
test blanket module (8) 8
fusionsreaktor (7) 7
monte carlo method (7) 7
solubility (7) 7
tritium breeding (7) 7
cooling (6) 6
druckabfall (6) 6
finite element method (6) 6
kühlmittel (6) 6
reaktor (6) 6
strategy (6) 6
systems (6) 6
breeder reactors (5) 5
computer simulation (5) 5
elektrizität (5) 5
finite elements (5) 5
flüssiges metall (5) 5
forschungsprogramm (5) 5
hydrogen (5) 5
lead (5) 5
lithium lead (5) 5
mechanical engineering (5) 5
mhd (5) 5
pb-17li (5) 5
schreckplatte (5) 5
stahl (5) 5
wärmeabfuhr (5) 5
betriebsanlage (4) 4
civil and structural engineering (4) 4
demonstrationsmodell (4) 4
diffusion (4) 4
european demo (4) 4
flows (4) 4
fusion reactors (4) 4
integration (4) 4
materials science (4) 4
mathematical analysis (4) 4
mechanical properties (4) 4
mhd-strömung (4) 4
model (4) 4
neutron flux (4) 4
nuclear energy and engineering (4) 4
nuclear power plants (4) 4
numerical analysis (4) 4
plasmas (4) 4
pressure drop (4) 4
radiation (4) 4
safety (4) 4
settore ing-ind/19 - impianti nucleari (4) 4
testsystem (4) 4
thermo-mechanic (4) 4
three dimensional models (4) 4
tokamak devices (4) 4
transport (4) 4
tripoli-4 (4) 4
tritium production rate (4) 4
usage (4) 4
vakuum (4) 4
walls (4) 4
wcll (4) 4
advection (3) 3
advertising campaigns (3) 3
alloys (3) 3
betriebsbedingung (3) 3
building materials (3) 3
buoyancy effect (3) 3
cast3m (3) 3
channels (3) 3
consortia (3) 3
more...
Language Language
Publication Date Publication Date
Click on a bar to filter by decade
Slide to change publication date range


Fusion Engineering and Design, ISSN 0920-3796, 09/2019, Volume 146, pp. 162 - 167
This paper presents the nuclear analysis carried out with the TRIPOLI-4 Monte-Carlo code for the Helium Cooled Lithium Lead (HCLL) “Advanced-Plus” breeding... 
Blanket | Breeder | Neutronic | SMS | HCLL | DEMO | Fusion
Journal Article
Fusion Engineering and Design, ISSN 0920-3796, 11/2018, Volume 136, pp. 1428 - 1432
In the framework of the European “HORIZON 2020” innovation and research programme, the EUROfusion Consortium develops a design of a fusion power demonstrator... 
DEMO | HCLL | Breeding Blanket | NUCLEAR SCIENCE & TECHNOLOGY | Nuclear reactors | Design and construction | Building materials | Analysis | Modeling and Simulation | Computer Science
Journal Article
NUCLEAR FUSION, ISSN 0029-5515, 04/2019, Volume 59, Issue 4, p. 46019
Breeding blankets are designed to ensure tritium self-sufficiency in deuterium-tritium fusion power plants. In addition to this, breeder blankets play a vital... 
fusion | breeder blanket | PHYSICS, FLUIDS & PLASMAS | parametric | CAD | HCLL BLANKET | 3D model | neutronics
Journal Article
Fusion Engineering and Design, ISSN 0920-3796, 09/2019, Volume 146, pp. 2026 - 2030
In the framework of the European “HORIZON 2020” research program, the EUROfusion Consortium develops a design of a fusion demonstrator (DEMO). CEA-Saclay, with... 
Finite elements | HCLL | Breeding Blanket | DEMO | Thermo-mechanic | RCC-MRx code
Journal Article
Fusion Engineering and Design, ISSN 0920-3796, 11/2018, Volume 136, pp. 1370 - 1375
Within the framework of EUROfusion R&D activities a research campaign has been performed at CEA-Saclay, in close collaboration with the University of Palermo,... 
FEM analysis | HCLL | Breeding blanket | DEMO | Thermomechanics | Finite element method | Research & development--R&D | Mechanical properties | Lithium | Thermomechanical properties | Mathematical models | Helium | Fusion | Three dimensional models | Thermomechanical analysis
Journal Article
FUSION ENGINEERING AND DESIGN, ISSN 0920-3796, 11/2018, Volume 136, pp. 1540 - 1544
In the frame of the European R&D effort to develop a fusion demonstrator (DEMO) a new concept of Helium Cooled Lithium Lead breeding blanket, called... 
Blanket | TRIPOLI-4 | NUCLEAR SCIENCE & TECHNOLOGY | European DEMO | Tritium breeding | Neutronics | HCLL
Journal Article
Fusion Engineering and Design, ISSN 0920-3796, 11/2018, Volume 136, pp. 1540 - 1544
In the frame of the European R&D effort to develop a fusion demonstrator (DEMO) a new concept of Helium Cooled Lithium Lead breeding blanket, called... 
European DEMO | Tritium breeding | Blanket | TRIPOLI-4 | Neutronics | HCLL
Journal Article
Fusion Engineering and Design, ISSN 0920-3796, 11/2017, Volume 124, pp. 827 - 831
Within the framework of EUROfusion R&D activities, CEA-Saclay has carried out an investigation of the thermal and mechanical performances of alternative... 
Cast3M | Thermo-mechanics | Finite elements | HCLL | Breeding blanket | DEMO | NUCLEAR SCIENCE & TECHNOLOGY | BLANKET
Journal Article
FUSION ENGINEERING AND DESIGN, ISSN 0920-3796, 11/2018, Volume 136, pp. 1231 - 1236
In the framework of the European "HORIZON 2020" research program, the EUROfusion Consortium develops a design of a fusion demonstrator (DEMO). The Breeding... 
Finite elements | HCLL | Breeding blanket | DEMO | Thermo-mechanic | NUCLEAR SCIENCE & TECHNOLOGY
Journal Article
FUSION ENGINEERING AND DESIGN, ISSN 0920-3796, 11/2018, Volume 136, pp. 1370 - 1375
Within the framework of EUROfusion R&D activities a research campaign has been performed at CEA-Saclay, in close collaboration with the University of Palermo,... 
FEM analysis | HCLL | Breeding blanket | DEMO | NUCLEAR SCIENCE & TECHNOLOGY | Thermomechanics
Journal Article
FUSION ENGINEERING AND DESIGN, ISSN 0920-3796, 11/2018, Volume 136, pp. 852 - 858
In Europe the technology to develop DEMO is being supported by HORIZON 2020 research programme under EUROfusion Consortium. One of the key components that DEMO... 
CFD | Manifolds | HCLL | Breeding Blanket | DEMO | NUCLEAR SCIENCE & TECHNOLOGY | Fluid dynamics | Analysis | Force and energy
Journal Article
Fusion Engineering and Design, ISSN 0920-3796, 11/2017, Volume 124, pp. 473 - 477
The EUROfusion Consortium develops a design of a fusion power demonstrator plant (DEMO) in the framework of the European “Horizon 2020” innovation and research... 
RCC-MRx | Thermo-mechanics | Breeding Blanket | Cast3M | HCLL | DEMO | First Wall | NUCLEAR SCIENCE & TECHNOLOGY | BLANKET | Analysis | Nuclear reactors
Journal Article
Fusion Engineering and Design, ISSN 0920-3796, 09/2019, Volume 146, pp. 173 - 177
The experimental facility THALLIUM was designed and installed at ENEA C.R. Brasimone to investigate the consequence of a HCLL-TBS In box LOCA, ensuring the... 
HCLL-TBS | Pressure wave | LLE | In-box LOCA | NUCLEAR SCIENCE & TECHNOLOGY | Thallium | Relief valves | Gas expanders
Journal Article
Fusion Engineering and Design, ISSN 0920-3796, 09/2019, Volume 146, pp. 514 - 517
In the framework of the European “HORIZON 2020” program, EURO fusion develops a fusion power demonstrator (DEMO). According to a recent study about plasma heat... 
HCLL | Breeding Blanket | DEMO | First Wall | NUCLEAR SCIENCE & TECHNOLOGY | Finite element method | Computer simulation | Armor | Tungsten | Lithium | Helium | Channels | Heat transfer | Heat flux | Loads (forces) | Material properties
Journal Article
FUSION ENGINEERING AND DESIGN, ISSN 0920-3796, 09/2019, Volume 146, pp. 162 - 167
This paper presents the nuclear analysis carried out with the TRIPOLI-4 (R) Monte-Carlo code for the Helium Cooled Lithium Lead (HCLL) "Advanced-Plus" breeding... 
Blanket | Breeder | Neutronic | NUCLEAR SCIENCE & TECHNOLOGY | SMS | HCLL | DEMO | Fusion | Neutron flux | Monte Carlo method | Reduction | Modules | Tritium | Lithium | Helium
Journal Article
Fusion Engineering and Design, ISSN 0920-3796, 10/2013, Volume 88, Issue 9-10, pp. 2492 - 2496
Validation of the calculated Tritium Production Rate (TPR) in the Test Blanket Modules (TBMs) needs relatively simple measurement procedure. Measurement system... 
Tritium | ITER | Diffusion | LSC | HCLL TBM | HCLL | TBM | CSC | NUCLEAR SCIENCE & TECHNOLOGY | Design engineering | Liquids | Mathematical analysis | Irradiation | Monitors | Scintillation | Lead (metal)
Journal Article
Fusion Engineering and Design, ISSN 0920-3796, 11/2017, Volume 123, pp. 102 - 106
The experimental facility THALLIUM (Test HAmmer in Lead LithIUM) was designed to reproduce the hydraulic transient in the HCLL TBS (Helium Cooled Lithium Lead... 
RELAP5-3D | Pressure wave | Hydraulic hammer | In-box LOCA | HCLL TBM | NUCLEAR SCIENCE & TECHNOLOGY | Wave propagation
Journal Article
Fusion Engineering and Design, ISSN 0920-3796, 11/2016, Volume 109-111, pp. 991 - 995
The EUROfusion Consortium develops a design of a fusion power demonstrator (DEMO) in the framework of the European “Horizon 2020” innovation and research... 
Design | Cast3M | RCC-MRx | HCLL | Breeding Blanket | DEMO | NUCLEAR SCIENCE & TECHNOLOGY
Journal Article
FUSION ENGINEERING AND DESIGN, ISSN 0920-3796, 09/2019, Volume 146, pp. 2026 - 2030
In the framework of the European "HORIZON 2020" research program, the EUROfusion Consortium develops a design of a fusion demonstrator (DEMO). CEA-Saclay, with... 
Finite elements | Breeding Blanket | NUCLEAR SCIENCE & TECHNOLOGY | RCC-MRx code | HCLL | DEMO | Thermo-mechanic | Finite element method | Consortia | Heat treatment | Design modifications | Heat shielding | Mechanical properties | Performance enhancement | Lithium | Tritium | Plasmas | Helium
Journal Article
No results were found for your search.

Cannot display more than 1000 results, please narrow the terms of your search.