Published October 2011 | Version v1
Journal article

LIBRETTO-4: Understanding and modeling tritium transport under irradiation

  • 1. EURATOM-CIEMAT Fusion Association, Av. Complutense 22, 28040 Madrid (Spain)
  • 2. Nuclear Fusion Institute, ETSII, UPM, c/Jose Gutierrez Abascal 2, 28006 Madrid (Spain)
  • 3. NRG, NRG P.O. Box 25 1755 ZG Petten (Netherlands)

Description

LIBRETTO-4 irradiation experiment with in situ T production in eutectic alloy LiPb inside EUROFER97 capsules was performed at the High Flux Reactor (HFR), Petten. Two identical capsules at two temperature ranges (500-550 deg. C and 300-350 deg. C) tested the tritium permeation rate through pre-oxidized ferritic-martensitic EUROFER97 into a He + 1000 H2 vppm cooling channel. A second channel with similar flowing gas composition obtained the tritium released from the LiPb and permeation through the internal wall of austenitic steel AISI316L. A 2-dimensional mathematical model has been developed. The model simulates tritium fluxes in capsule materials for variable experimental conditions (generation rates, gas pressures and flow rates) for a 27 days cycle. Modeling provides a consistent physical picture of release-rate mechanisms within the capsule. Tritium transport data under irradiation in capsule's material have been derived.

Availability note (English)

Available from http://dx.doi.org/10.1016/j.fusengdes.2011.02.055

Additional details

Identifiers

DOI
10.1016/j.fusengdes.2011.02.055;
PII
S0920-3796(11)00225-0;

Publishing Information

Journal Title
Fusion Engineering and Design
Journal Volume
86
Journal Issue
9-11
Journal Page Range
p. 2374-2377
ISSN
0920-3796
CODEN
FEDEEE

Conference

Title
26. symposium on fusion technology
Acronym
SOFT-26
Dates
27 Sep - 1 Oct 2010
Place
Porto (Portugal)

Optional Information

Copyright
Copyright (c) 2011 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.