Tritium permeation in EUROFER97 steel in EXOTIC-9/1 irradiation experiment

被引:0
|
作者
Fedorov, A. V. [1 ]
Magielsen, A. J. [1 ]
Stijkel, M. P. [1 ]
机构
[1] NRG, NL-1755 ZG Petten, Netherlands
关键词
HYDROGEN TRANSPORT; DEUTERIUM; PERFORMANCE; ISOTOPES; REACTOR;
D O I
10.1016/j.jnucmat.2014.01.022
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
This paper presents the results of the tritium permeation study in EUROFER97 carried out within the EXOTIC (EXtraction Of Tritium In Ceramics) irradiation experiment. In the EXOTIC 9/1 experiment, a pebble bed assembly containing Lithium Titanate (Li2TiO3) pebbles is irradiated for 300 days in the High Flux Reactor (HFR), in the temperature range between 340 and 580 C, reaching a lithium burn up of 3.5% and 1.2 dpa of damage in steel. The primary objective of this experiment was to measure the in-pile tritium release characteristics of Li2TiO3 pebbles. Additionally tritium permeation through the EUROFER97 pebble bed wall was measured on line. The permeation of tritium was studied at steady state conditions, during temperature transients, and at different hydrogen concentrations in the helium purge gas flow. The model used in the analysis of the experimental data which account for co-permeation of tritium and hydrogen is presented. It has been demonstrated that the permeation of tritium under experiment conditions proceeds in the diffusion limited regime. From the analysis of the experimental data the permeability and diffusivity of tritium in EUROFER97 is determined. (C) 2014 Elsevier BA/. All rights reserved.
引用
收藏
页码:139 / 143
页数:5
相关论文
共 50 条
  • [41] A structure-property correlation study of neutron irradiation induced damage in EU batch of ODS Eurofer97 steel
    Kolluri, M.
    Edmondson, P. D.
    Luzginova, N. V.
    van der Berg, F. A.
    MATERIALS SCIENCE AND ENGINEERING A-STRUCTURAL MATERIALS PROPERTIES MICROSTRUCTURE AND PROCESSING, 2014, 597 : 111 - 116
  • [42] SANS and neutron diffraction study of ausformed EUROFER97/2 ferritic/martensitic steel
    Coppola, R.
    Feoktystov, A.
    Mueller, T.
    Pilloni, L.
    Radulescu, A.
    NUCLEAR MATERIALS AND ENERGY, 2020, 24
  • [43] Hydrogen permeation through TiAlN-coated Eurofer '97 steel
    McGuiness, Paul J.
    Cekada, Miha
    Nemanic, Vincenc
    Zajec, Bojan
    Recnik, Aleksander
    SURFACE & COATINGS TECHNOLOGY, 2011, 205 (8-9): : 2709 - 2713
  • [44] Mechanical tests on two batches of oxide dispersion strengthened RAFM steel (EUROFER97)
    Lucon, E
    FUSION ENGINEERING AND DESIGN, 2002, 61-62 : 683 - 689
  • [45] Sputtering of polished EUROFER97 steel: Surface structure modification and enrichment with tungsten and tantalum
    Strom, Petter
    Petersson, Per
    Parra, Rodrigo Arredondo
    Oberkofler, Martin
    Schwarz-Selinger, Thomas
    Primetzhofer, Daniel
    JOURNAL OF NUCLEAR MATERIALS, 2018, 508 : 139 - 146
  • [46] Behavior of Eurofer97 reduced activation martensitic steel upon heating and continuous cooling
    Danón, A
    Alamo, A
    JOURNAL OF NUCLEAR MATERIALS, 2002, 307 (1 SUPPL.) : 479 - 483
  • [47] Fracture toughness master-curve analysis of the tempered martensitic steel Eurofer97
    Mueller, Pablo
    Spaetig, P.
    Bonade, R.
    Odette, G. R.
    Gragg, D.
    JOURNAL OF NUCLEAR MATERIALS, 2009, 386-88 : 323 - 327
  • [48] Use of the failure assessment diagram to deduce ductile fracture toughness of the RAFM steel EUROFER97
    Gaganidze, E.
    Aktaa, J.
    INTERNATIONAL JOURNAL OF PRESSURE VESSELS AND PIPING, 2009, 86 (06) : 345 - 350
  • [49] Interaction of Pb-16Li melt with EUROFER97 under higher temperature and neutron irradiation
    Splichal, Karel
    Berka, Jan
    Zmitko, Milan
    Viererbl, Ladislav
    Lahodova, Zdena
    FUSION ENGINEERING AND DESIGN, 2018, 126 : 73 - 78
  • [50] Experimental study of efficiency of natural oxide layers for reduction of tritium permeation through Eurofer 97
    Aiello, A.
    Utili, M.
    Scalia, S.
    Coccoluto, G.
    FUSION ENGINEERING AND DESIGN, 2009, 84 (2-6) : 385 - 389