Tritium permeation, retention and release properties of beryllium pebbles

Chakin, V.; Moeslang, A.; Kurinskiy, P.; Rolli, R.; Schneider, Holger; Alves, E.; Alves, L.C.

doi:10.1016/j.fusengdes.2011.01.091

Cited by 9 publications

(5 citation statements)

References 11 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…The investigated beryllium pebbles with a diameter of about 1 mm were fabricated by NGK Insulators Ltd., Japan using the rotating electrode method 49 . Their chemical composition is given in Table 2 50 and the parameters of irradiation, performed in the High Flux Reactor (HFR) Petten within the HIDOBE 2 campaign 4 , are shown in Table 1. The irradiation temperatures within the rigs, which were continuously controlled during irradiation with thermocouples, showed large variations.…”

Section: Discussionmentioning

confidence: 99%

New insights into microstructure of irradiated beryllium based on experiments and computer simulations

Klimenkov

Vladimirov

Jäntsch

et al. 2020

Sci Rep

Self Cite

View full text Add to dashboard Cite

The microstructural response of beryllium after neutron irradiation at various temperatures (643-923 K) was systematically studied using analytical transmission electron microscope that together with outcomes from advanced atomistic modelling provides new insights in the mechanisms of microstructural changes in this material. The most prominent feature of microstructural modification is the formation of gas bubbles, which is revealed at all studied irradiation temperatures. except for the lowest irradiation temperature, gas bubbles have the shape of thin hexagonal prisms with average height and diameter increasing with temperature. A high number density of small bubbles is observed within grains, while significantly larger bubbles are formed along high-angle grain boundaries (GB). Denuded zones (DZ) nearly free from bubbles are found along both high-and low-angle grain boundaries. Precipitations of secondary phases (mainly intermetallic Al-Fe-Be) were observed inside grains, along dislocation lines and at GBs. EDX analysis has revealed homogeneous segregation of chromium and iron along GBs. the observed features are discussed with respect to the available atomistic modelling results. in particular, we present a plausible reasoning for the abundant formation of gas bubbles on intermetallic precipitates, observation of various thickness of zones denuded in gas bubbles and precipitates, and their relation to the atomic scale diffusion mechanisms of solute-vacancy clusters.

show abstract

Section: Discussionmentioning

confidence: 99%

New insights into microstructure of irradiated beryllium based on experiments and computer simulations

Klimenkov

Vladimirov

Jäntsch

et al. 2020

Sci Rep

Self Cite

View full text Add to dashboard Cite

show abstract

“…Generally, impurity segregation in beryllium differs between different production heats due to the significant variation of impurities concentration. In several research studies the presence of impurity particles in beryllium is mentioned without further analytical characterization [9,10]. At the same time it is well known that mechanical properties of Be are influenced by impurity content [12,13].…”

Section: Discussionmentioning

confidence: 99%

“…The beryllium pebbles contain the following main impurities in wt.%: 0.36 BeO, 0.094 Fe, 0.048 Al, 0.029 Si, 0.024 Mg [9,10]. The HIDOBE-01 irradiation campaign at HFR, Petten, started in June 2005 and was completed in October 2007 after 25 reactor cycles or 649 days at full reactor power (>40 MW).…”

Section: Methodsmentioning

confidence: 99%

TEM study of impurity segregations in beryllium pebbles

Klimenkov

Chakin

Moeslang

et al. 2014

Journal of Nuclear Materials

Self Cite

View full text Add to dashboard Cite

“…Tritium depth profile in beryllium pebbles after gas loading has been also measured by the method proposed in this manuscript. Beryllium pebbles (produced by NGK and Brush Materion) loaded with hydrogen and tritium gas mixture for 15 hours at 600 and 850 o C temperature and 4 bar pressure of tritium at the Karlsruhe institute of Technology has been analysed [21].…”

Section: Tritium Loaded Beryllium Pebblesmentioning

confidence: 99%

“…Two types of pebbles produced by different methods were compared-one type produced by the rotating electrode method (REM, NGK, Japan) and the second using the fluoride reduction method (FRM, Materion Brush, USA). Samples were loaded at KIT under exposure to the H and T mixture ( 1 H 2 + 500 appm 3 H 2 ) for 15 h at the temperature of 600 °C and 850 °C, at a 4 bar pressure [26,27].…”

Section: Tritium Loaded Beryllium Pebblesmentioning

confidence: 99%

Novel method for determination of tritium depth profiles in metallic samples

et al. 2019

View full text Add to dashboard Cite

Novel method for determining the depth profile of tritium in metallic samples has been demonstrated. Tritium accumulation in the fusion reactor materials is considered as a radiological issue due to its radioactivity. Therefore, tritium behavior prediction and estimation of its overall retention in fusion devices is of high importance. Proposed method in this study allows to measure depth profile of tritium in the metallic samples after exposure to tritium containing plasma, tritium gas or after irradiation with neutrons resulting in the tritium formation. In the method, successive layers of metal are removed using appropriate etching agent in the controlled regime and amount of evolved gases measured by the means of chromatography (gas composition and release rate) and proportional gas flow detector (tritium). Results on tritium profile in neutron irradiated, plasma exposed and tritium gas loaded beryllium have been reported and possible applications of the method for other metallic samples have been tested within this research.

show abstract

Tritium permeation, retention and release properties of beryllium pebbles

Cited by 9 publications

References 11 publications

New insights into microstructure of irradiated beryllium based on experiments and computer simulations

New insights into microstructure of irradiated beryllium based on experiments and computer simulations

TEM study of impurity segregations in beryllium pebbles

Novel method for determination of tritium depth profiles in metallic samples

Contact Info

Product

Resources

About