5-9 September 2016
Prague Congress Centre
Europe/Prague timezone

P1.103 Potential irradiation of Cu alloys and tungsten samples in DONES

5 Sep 2016, 14:20
1h 40m
Foyer 2A (2nd floor), 3A (3rd floor) (Prague Congress Centre)

Foyer 2A (2nd floor), 3A (3rd floor)

Prague Congress Centre

5. května 65, Prague, Czech Republic
Board: 103
Poster F. Plasma Facing Components P1 Poster session

Speaker

Fernando Mota (Laboratorio Nacional de Fusion)

Description

Tungsten and Cu-alloys are currently proposed as reference candidate material for ITER first wall and divertor. Tungsten is proposed for its high fusion temperature and Cu-Cr-Zr alloys for their high thermal conductivity together good mechanical properties.  However its behavior under the extreme irradiation conditions as expected in ITER or DEMO is still unknown. Due to the determinant role of H and He played in the material behavior any irradiation experiment must take into account the important amount of these gases produced during the irradiation in Fusion reactors. DONES (DEMO Oriented Neutron Source) has been conceived as a simplified IFMIF-like plant to provide in a reduced time scale and with a reduced budget – both compared to IFMIF- the basic information on materials damage. The objective of DONES-IFMIF in its first stage will be to test structural materials under similar neutron irradiation nuclear fusion conditions as expected in fusion reactors. These tests will be carried out in specimens irradiated in the so-called High Flux Test Module (HFTM). The objective of this paper is to assess on the potential use of DONES to irradiate Cu alloys and tungsten in the HFTM together other stainless steel based materials. The presence of Cu alloys or w specimens may have an effect in the irradiation parameters of the stainless steel samples placed also in the HFTM and in the samples of the Creep Fatigue Test Module (CFTM). Alternatively the Cu alloy specimens could be located in the volume made available in DONES with the absence of other irradiation modules. These different locations are analyzed and compared. McDeLicious code is used for neutron transport calculations. Damage dose rate and H and He production are analyzed in the different locations and compared with the actual irradiation conditions in first wall and divertors in fusion machines.

Co-authors

Angel Ibarra (Laboratorio Nacional de Fusion, CIEMAT, Avda. Complutense 40, CP: 28040, Madrid, Spain) Fernando Mota (Laboratorio Nacional de Fusion, CIEMAT, Avda. Complutense 40, CP: 28040, Madrid, Spain) Iole Palermo (Laboratorio Nacional de Fusion, CIEMAT, Avda. Complutense 40, CP: 28040, Madrid, Spain) Joaquin Molla (Laboratorio Nacional de Fusion, CIEMAT, Avda. Complutense 40, CP: 28040, Madrid, Spain) Selece Laces (Unidad Académica de estudios nucleares, UAZ, Zacatecas CP: 98060, Mexico)

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