0000000000352124

AUTHOR

Elīna Pajuste

0000-0003-1036-4679

showing 6 related works from this author

Tritium release behavior of beryllium pebbles after neutron irradiation between 523 and 823K

2013

Abstract Post-irradiation tritium release from the Pebble Bed Assembly (PBA) neutron-irradiated beryllium (Be) pebbles (∅ ≈ 1 mm; the total tritium inventory 2–4 GBq/g) was investigated on annealing in He + 0.1% H 2 . Temperature ramps of 2.3 K/min followed by annealing for 1 h at 1310–1320 K resulted in complete detritiation of the PBA Be pebbles. The tritium burst release occurred after a time lag of 1–6.5 h during constant temperature anneals at 1089–1180 K, with the release time measured after reaching the annealing temperature. Tritium burst release was also observed to occur during cool down. Anneals at 1089 K for 8 h and at 1045 K for 23 h caused detritiation of the PBA Be pebbles by…

Nuclear and High Energy PhysicsAnnealing (metallurgy)Radiochemistrychemistry.chemical_elementThermal diffusivityRelease timeTritium releaseNuclear Energy and EngineeringchemistryGeneral Materials ScienceTritiumBerylliumPebbleNeutron irradiationJournal of Nuclear Materials
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Novel method for determination of tritium depth profiles in metallic samples

2019

Tritium accumulation in fusion reactor materials is considered a serious radiological issue, therefore a lot of effort has been concentrated on the development of radiometric techniques. A novel method, based on gradual dissolution, for the determination of the total tritium content and its depth profiles in metallic samples is demonstrated. This method allows for the measurement of tritium in metallic samples after their exposure to a hydrogen and tritium mixture, tritium containing plasma or after irradiation with neutrons resulting in tritium formation. In this method, successive layers of metal are removed using an appropriate etching agent in the controlled regime and the amount of evo…

inorganic chemicalsfusionNuclear and High Energy PhysicsMaterials scienceNuclear engineeringchemistry.chemical_elementheliumBlanket114 Physical sciences01 natural sciences010305 fluids & plasmasblanketMetalirradiated berylliumjet0103 physical sciencespolycyclic compounds010306 general physicsHeliumbreeding blanketJet (fluid)Fusiontritiumbehaviororganic chemicalshydrogen diffusiontemperatureiter-like-wallFusion powerfirst wallberylliumCondensed Matter Physicschemistryvisual_arttransportcardiovascular systemvisual_art.visual_art_mediumdepth profileTritiumBerylliumNuclear Fusion
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Tritija uzvedība kodolsintēzes reaktora materiālos

2012

ANOTĀCIJA Darbs veltīts nākotnes enerģijas avota kodolsintēzes attīstībai. Pētījuma mērķis ir novērtēt kodolsintēzes reaktora materiālu piemērotību saistībā ar to izmaiņām iekārtas apstākļos un radioaktīvā ūdeņraža izotopa tritija uzkrāšanos. Darbā izmantotas LU Ķīmiskās Fizikas Institūta Cietvielu Radiācijas Ķīmijas Laboratorijā izstrādātas metodes un iekārtas. Novērots sinerģētisks jonizējošā starojuma un magnētiskā lauka efekts tritija izdalīšanās veicināšanā un novērtēts tā kopējais ieguldījums. Balstoties uz iegūtajiem rezultātiem izstrādātas rekomendācijas attiecībā uz radioaktīvo atkritumu daudzuma mazināšanu kodolsintēzes reaktoros Atslēgas vārdi: kodolsintēze, tritijs, difūzija, ma…

Ķīmija ķīmijas tehnoloģijas un biotehnoloģijaĶīmija
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TRITIUM RELEASE CHARACTERISTICS OF NEUTRON-IRRADIATED REFERENCE BERYLLIUM PEBBLES FOR THE HELIUM COOLED PEBBLE BED (HCPB) BLANKET

2011

In this paper, we present results on tritium release from the beryllium pebbles irradiated for 294 full power days from 17 April 2003 to November 2004 to the neutron fluence of 1.5-2 × 1025 m-2 (E>...

Nuclear and High Energy PhysicsMaterials science020209 energyMechanical EngineeringNuclear engineeringchemistry.chemical_element02 engineering and technologyBlanket01 natural sciences010305 fluids & plasmasTritium releaseNuclear Energy and EngineeringchemistryNeutron flux0103 physical sciences0202 electrical engineering electronic engineering information engineeringGeneral Materials ScienceNeutronIrradiationBerylliumPebbleHeliumCivil and Structural Engineering
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Structure, tritium depth profile and desorption from 'plasma-facing' beryllium materials of ITER-Like-Wall at JET

2017

This work has been carried out within the framework of the EUROfusion Consortium and has received funding from the Euratom research and training programme 2014–2018 under grant agreement No 633053 . The views and opinions expressed herein do not necessarily reflect those of the European Commission.

Nuclear and High Energy PhysicsThermal desorption spectroscopyMaterials Science (miscellaneous)Nuclear engineeringJoint European TorusAnalytical chemistryThermal desorptionchemistry.chemical_elementFuel accumulationTritiumThermal desorption7. Clean energy01 natural sciences010305 fluids & plasmasFusion plasma och rymdfysikDesorption0103 physical sciences:NATURAL SCIENCES:Physics [Research Subject Categories]010306 general physicsJet (fluid)ChemistryITER-like wallPlasmaITER-Like-Walllcsh:TK9001-9401Fusion Plasma and Space Physicsrespiratory tract diseasesNuclear Energy and Engineeringcardiovascular systemlcsh:Nuclear engineering. Atomic powerTritiumBerylliumDepth profileBeryllium
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Tritium Behaviour in the Fusion Reactor Materials

2012

Elektroniskā versija nesatur pielikumus

Chemistry technologyĶīmijas tehnoloģijasĶīmija
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