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Investigation of tritium analysis methods for ion microbeam application
KTH, Skolan för elektro- och systemteknik (EES), Fusionsplasmafysik.
KTH, Skolan för elektro- och systemteknik (EES), Fusionsplasmafysik.
KTH, Skolan för elektro- och systemteknik (EES), Fusionsplasmafysik.
Vise andre og tillknytning
2012 (engelsk)Inngår i: Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, ISSN 0168-583X, E-ISSN 1872-9584, Vol. 273, s. 250-253Artikkel i tidsskrift (Fagfellevurdert) Published
Abstract [en]

The trapping and retention of tritium in deposited layers on plasma-facing components is a critical issue for the international tokamak experimental reactor (ITER) and for future power producing tokamak fusion reactors. Cross sections of deposited layers at surfaces in the JET tokamak divertor are being investigated using ion microbeam analysis. To include tritium analysis with high spatial resolution, a number of plausible ion beam techniques have been investigated. Calibration samples with 150 nm tritiated titanium films were used. Absolute concentrations were determined with classical ERD using 2.5-3.5 MeV C-12(+). Cross sections for non-Rutherford ERD and for the T(C-12,p)C-14 and T(C-12,alpha)B-11 nuclear reactions were measured for different angles in the energy range 2.5-15 MeV. Background spectra were collected from pure carbon, beryllium and deuterium enriched samples and the sensitivity for microbeam NRA measurements of the tritium concentration in thick targets with predominantly Be-C-D matrix was estimated.

sted, utgiver, år, opplag, sider
2012. Vol. 273, s. 250-253
Emneord [en]
Tritium, Cross section, Microbeam, Fusion
HSV kategori
Identifikatorer
URN: urn:nbn:se:kth:diva-91250DOI: 10.1016/j.nimb.2011.07.087ISI: 000300471000066Scopus ID: 2-s2.0-84856103475OAI: oai:DiVA.org:kth-91250DiVA, id: diva2:509257
Merknad
QC 20120312Tilgjengelig fra: 2012-03-12 Laget: 2012-03-12 Sist oppdatert: 2017-12-07bibliografisk kontrollert
Inngår i avhandling
1. Experimental studies of materials migration in magnetic confinement fusion devices: Novel methods for measurement of macro particle migration, transport of atomic impurities and characterization of exposed surfaces
Åpne denne publikasjonen i ny fane eller vindu >>Experimental studies of materials migration in magnetic confinement fusion devices: Novel methods for measurement of macro particle migration, transport of atomic impurities and characterization of exposed surfaces
2014 (engelsk)Doktoravhandling, med artikler (Annet vitenskapelig)
Abstract [en]

During several decades of research and development in the field of Magnetically Confined Fusion (MCF) the preferred selection of materials for Plasma Facing Components (PFC) has changed repeatedly. Without doubt, endurance of the first wall will decide research availability and lifespan of the first International Thermonuclear Research Reactor (ITER). Materials erosion, redeposition and mixing in the reactor are the critical processes responsible for modification of materials properties under plasma impact. This thesis presents several diagnostic techniques and their applications for studies of materials transport in fusion devices. The measurements were made at the EXTRAP T2R Reversed Field Pinch operated in Alfvén laboratory at KTH (Sweden), the TEXTOR tokamak, recently shut down at Forschungszentrum Jülich (Germany) and in the JET tokamak at CCFE (UK). The main outcomes of the work are:

  • Development and application of a method for non-destructive capture and characterization of fast dust particles moving in the edge plasma of fusion devices, as well as particles generated upon laser-assisted cleaning of plasma exposed surfaces. 
  • Advancement of conventional broad beam and micro ion beam techniques to include measurement of tritium in the surfaces exposed in future D-T experiments. 
  • Adaption of the micro ion beam method for precision mapping of non uniform elements concentrations on irregular surfaces. 
  • Implementation of an isotopic marker to study the large scale materials migration in a tokamak and development of a method for fast non destructive sampling of the marker on surfaces of PFCs.
sted, utgiver, år, opplag, sider
Stockholm: KTH Royal Institute of Technology, 2014. s. iv, 84
Serie
TRITA-EE, ISSN 1653-5146 ; 2014:024
Emneord
fusion, tokamak, RFP, divertor, limiter, SOL, transport, migration, surface analysis, IBA, ion micro beam, beryllium, tritium
HSV kategori
Forskningsprogram
Fysik
Identifikatorer
urn:nbn:se:kth:diva-145045 (URN)978-91-7595-147-8 (ISBN)
Disputas
2014-05-16, F3, Lindstedsvägen 26, KTH, Stockholm, 14:00 (engelsk)
Opponent
Veileder
Merknad

QC 20140508

Tilgjengelig fra: 2014-05-08 Laget: 2014-05-07 Sist oppdatert: 2014-05-08bibliografisk kontrollert

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