Search Results - "Bonal, J.P."
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Determination of the lithium diffusion coefficient in irradiated boron carbide pellets
Published in Journal of nuclear materials (01-03-1999)“…During neutron irradiation, 10B atoms in B 4C are destroyed, producing lithium and helium atoms according to the well-known 10B(n,α) 7Li reaction. The aim of…”
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2
Carbon fiber composites application in ITER plasma facing components
Published in Journal of nuclear materials (01-10-1998)“…Carbon Fiber Composites (CFCs) are one of the candidate armour materials for the plasma facing components of the International Thermonuclear Experimental…”
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3
Progress of the European R&D on plasma–wall interactions, neutron effects and tritium removal in ITER plasma facing materials
Published in Fusion engineering and design (01-10-2001)“…In a next step D/T fusion device like ITER, an intense neutron flux will be produced as a consequence of the nuclear fusion reactions. The effects of the…”
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4
Design requirements for SiC/SiC composites structural material in fusion power reactor blankets
Published in Fusion engineering and design (01-09-1998)“…This paper recalls the main features of the TAURO blanket, a self-cooled Pb-17Li concept using SiC/SiC composites as structural material, developed for FPR…”
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5
Simulation experimental investigation of plasma off-normal events on advanced silicon doped CFC-NS31
Published in Journal of nuclear materials (01-12-2002)“…Fusion devices high heat loading due to off-normal events (e.g., plasma disruption, slow transients and ELMs, which can occur during a transition from detached…”
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6
Nuclear microprobe analysis of 7Li profile induced in HfB 2 by a neutron irradiation
Published in Journal of nuclear materials (2001)“…HfB 2, a solid poor in boron, was irradiated by thermal neutrons in an experimental reactor. Using a nuclear microprobe, we have tracked lithium atoms produced…”
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7
Conceptual design of a high temperature water-cooled divertor for a fusion power reactor
Published in Fusion engineering and design (01-11-2005)“…This paper presents the conceptual design of a water-cooled divertor target using EUROFER as structural material, water coolant pressure and outlet…”
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8
Neutron irradiation effects on carbon based materials at 350°C and 800°C
Published in Journal of nuclear materials (2000)“…An experimental study on the neutron irradiation induced thermal properties and dimensional changes of various carbon based materials has been carried using…”
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Neutron induced thermal properties changes in carbon fiber composites irradiated from 600 to 1000°C
Published in Journal of nuclear materials (02-06-1996)“…An experimental study on the neutron irradiation induced thermal properties changes of various carbon fiber composites has been carried out using the High Flux…”
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10
Nuclear microprobe analysis of 7Li profile induced in HfB2 by a neutron irradiation
Published in Journal of nuclear materials (01-09-2001)Get full text
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Neutron irradiation effects on the thermal conductivity and dimensional stability of carbon fiber composites at divertor conditions
Published in Journal of nuclear materials (01-03-1996)“…In continuation of our study on neutron induced property changes of carbon fiber composites at low irradiation temperatures and low neutron doses, an…”
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12
Neutron effects on properties and annealing of low-Z materials
Published in Fusion engineering and design (01-11-2000)“…Among the low-Z materials, carbon and beryllium are seriously considered as plasma facing materials (PFC) for the next step fusion experimental reactor,…”
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13
EU results on neutron effects on PFC materials
Published in Fusion engineering and design (01-09-1998)“…Among the low-Z materials, carbon and beryllium are primary candidates for use as plasma facing materials for the International Thermonuclear Experimental…”
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14
European development of the ITER divertor target
Published in Fusion engineering and design (01-11-1999)“…The main European contribution to the ITER divertor project was the development of the divertor target with severe operating requirements such as peak heat…”
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15
European development of prototypes for ITER high heat flux components
Published in Fusion engineering and design (01-11-2000)“…The extensive EU research and development, on international thermonuclear experimental reactor (ITER) high heat flux (HHF) components aims at the demonstration…”
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Journal Article Conference Proceeding