Fabricación de carburo de silicio poroso con capa densa para su aplicación en inserciones aislantes en canal para futuros reactores de fusión nuclear.

Within the project TECNO_FUS on CONSOLIDER- INGENIO 2010 program, a dual coolant blanket design is developing (DCLL = Dual Coolant Lithium Lead) for DEMO with Pb-15.7Li and He as coolant. It is a ferritic-martensitic steel with low activation as structural metrial cooled by He. The Pb-15.7Li acts...

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Bibliographic Details
Main Authors: Bereciartu-Andrés, A. (Ainhoa), Ordas-Mur, N. (Nerea), Garcia-Rosales, C. (Carmen)
Format: info:eu-repo/semantics/doctoralThesis
Language:eng
Published: Servicio de Publicaciones. Universidad de Navarra. 2015
Subjects:
Online Access:https://hdl.handle.net/10171/37253
Description
Summary:Within the project TECNO_FUS on CONSOLIDER- INGENIO 2010 program, a dual coolant blanket design is developing (DCLL = Dual Coolant Lithium Lead) for DEMO with Pb-15.7Li and He as coolant. It is a ferritic-martensitic steel with low activation as structural metrial cooled by He. The Pb-15.7Li acts as tritium breeder, neutron multiplier and coolant. The Pb-15.7Li outlet temperature has been as high as possible to achieve the highest possible efficiency, without exceeding the maximum temperature of steel. Due to the high magnetic fields produced in the region of the blanket, the Pb-15.7Li needs to be electrically insulated from the steel to reduce the magnetohydrodynamic pressure drop (MHD). Also, it should be thermially insulated from stell to avoid heat loss. This is one of the main functions of the Flow Channel Iserts (FCI), which also act as thermal insulator to maximize the Pb-15.7Li temperature, and thus, the efficiency. Silicon carbide is the main candidate material for FCI in the DLL blanket, due to its excellent thermal, mechanical and chemical stability at high temperatures, low thermal expansion, good thermal shock resistance, low corrosion by Pb-15.7Li, low activation and good resistance to neutron irradiation, low activation and good resistance to neutron irradiation. Porous SiC is one of the most attractive types of SiC under consideration, since it is expected to achieve the required properties following a simple and inexpensive manufacturing route compared to SiCf/SiC materials. To avoid tritium permeation and corrosion by Pb-15.7Li, a dense coating must be applied on the porous SiC surface. In this work the results obtained in the production of porous SiC powder metallurgical route by pressureless sintering are presented. For the manufacture of porous SiC different particle size starting SiC and carbonaceous powders, with and without additives, have been used. A study on liquid phase sintering by varying sintering temperature and time is performed. Carbonaceus powders are used as poreformers by their burnout during oxidation after sintering. A study on the effect of different processing parameters on final relevant properties of porous SiC has been carried out and the two most promising porous SiC materials were selected on the basis of lowest thermal conductivity (11-13 W/mK a 700 °C) and highest flexural strength (100-140 MPa). The two selected materials are coated with a 30 μm thick CVD SiC layer. Electrical conductivity was measured at CIEMAT before and after irradiation in a Van de Graaff accelerator with 1.8 MeV electrons up to 130 MGy, and values < 20 S/m at 400°C are obtained. Corrosion tests under static Pb-15.7Li are conducted at 700C during 1032 houers under 99% Ar + 1% H2 atmosphere at IQS; even though the used Pb-17.5Li has very high O content, the 30 μm CVD SiC layer provide partial protection against corrosion.