Memorias de investigación
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Corrosion and activation analysis of the LIPAC beam dump cooling circuit
Año:2013

Áreas de investigación
  • Centrales térmicas nucleares y de fusión

Datos
Descripción
The LIPAC beam dump cooling circuit has been modelled by means of TRACT (TRansport and ACTivation) code. TRACT simulates the flow and isotope transport inside a network of 1-D channels. The cooling circuit consists of the beam dump (inner cone and shroud made of EDP Cu (electrodeposited copper) and the cylinder made of SS304L), the piping from the cooling skid to the beam dump cell and the cooling skid itself composed of the heat exchanger, the purifying loop and the pump. Corrosion is an issue that deserves attention because of radioprotection reasons and because it could affect the cartridge thermomechanical performance. A simulation with TRACT for a water pH of 7 at the beam dump entrance has been performed, showing corrosion rates (< 1 g/(m2 year)) which do not compromise the beam dump performance.
Internacional
Si
JCR del ISI
Si
Título de la revista
Fusion Engineering And Design
ISSN
0920-3796
Factor de impacto JCR
1,49
Información de impacto
Datos JCR del año 2011
Volumen
88
DOI
http://dx.doi.org/10.1016/j.fusengdes.2013.04.010
Número de revista
Desde la página
827
Hasta la página
830
Mes
OCTUBRE
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Grupos de investigación, Departamentos, Centros e Institutos de I+D+i relacionados
  • Creador: Centro o Instituto I+D+i: Instituto de Fusión Nuclear
  • Departamento: Ingeniería Energética y Fluidomecánica