Biological hazard issues from potential releases of tritiated dust from ITER

Pace, L. Di; Letellier, E.; Maubert, H.; Patel, B.; Raskob, W.

doi:10.1016/j.fusengdes.2008.06.011

Cited by 10 publications

(7 citation statements)

References 4 publications

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“…In reality, the particles are not spherical and nor smooth and they are generally deposited on rough surfaces [17]. Hence, adhesion forces cannot be directly calculated by the expression in equation (3). To account for the diminution of adhesion force FjKR, due to surface roughness, Biasi et al [15] tried to determine "universal" correlations for calculating the distribution of adhesion forces.…”

Section: Force (N )mentioning

confidence: 99%

“…In ITER's normal operating conditions, several hundred kilogrammes of particles made of beryllium (Be) and tungsten (W) will be produced following the erosion of the vacuum vessel (VV) walls (blanket and divertor) by the plasma [2]. The particles are subject to the conditions found in the VV and may thus be radioactive (tritium and activation products [3], exhibit acute chemical toxicity (beryllium particles) [4] [5], or constitute, with air or water vapour, a potentially explosive mixture [2].…”

Section: Introductionmentioning

confidence: 99%

“…normalized particle mass concentration évolution during the test (damm = 1 gm)The average resuspension coefficient is then calculated for all experimental cases. For particles with an aerodynamic median diameter (AMMD) of 1 gm, average resuspension coefficients of3 3 ± 2.10-and 4.10-are found for the experimental case and the CFX case respectively.…”

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confidence: 99%

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CFD modelling of particle resuspension in a toroidal geometry resulting from airflows during a loss of vacuum accident (LOVA)

Gélain

Gensdarmes

Peillon

et al. 2020

Fusion Engineering and Design

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Section: Force (N )mentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

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CFD modelling of particle resuspension in a toroidal geometry resulting from airflows during a loss of vacuum accident (LOVA)

Gélain

Gensdarmes

Peillon

et al. 2020

Fusion Engineering and Design

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“…Assessments related to WeH system for applications in thermonuclear reactors are in demand with the launch of the ITER international project, the most important international research project on energy. Until now, the walls of the tokamak prototypes consisted mainly of carbon material in which significant trapping of tritium occurred, inducing the release of tritiated carbon particles with activities sometimes higher than 1 GBq/g [1]. Accidental inhalation of such radioactive particles should thus be harmful for people.…”

Section: Introductionmentioning

confidence: 99%

Tritium absorption/desorption in ITER-like tungsten particles

Kharbachi

Chêne

Garcia‐Argote

et al. 2014

International Journal of Hydrogen Energy

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Tritium retention in plasma facing materials such as tungsten is a major concern for future fusion reactors. During ITER operating mode, the reactor could generate tritiated tungsten dust-like particles which need to be characterized in terms of amount of trapped tritium, tritium source and radiotoxicity. This study is focused on the preparation and character-ization of tungsten particles and on a comparative analysis of tritium absorption/desorp-tion kinetics in these particles and in massive samples. An original gas phase thermal charging procedure was used successfully for tritium incorporation in tungsten powders and massive samples. Much larger tritium amounts are incorporated in W particles than in massive samples indicating important surface effects on tritium absorption, desorption and trapping in W. Tritium desorption from particles occurred at different temperatures related with different interactions on the particles surface and in the bulk; the tritium behavior in massive samples was also shown to depend on the metal microstructure. According to these experimental results tritium absorption/desorption in W particles may have important implications on tritium management in ITER reactor.

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“…The fate of tritium, an isotope of hydrogen (half-life 12.3 y), in the human body, as tritiated water (HTO) or organically bound tritium (OBT), is well understood, with inhaled HTO translocated quickly into blood and distributed uniformly (Di Pace et al, 2008;Nie et al, 2021). Furthermore, tritium-induced biological effects have been extensively explored in aquatic biota under a range of radiation dose rates (Jha et al, 2005(Jha et al, , 2006Adam-Guillermin et al, 2012;Jaeschke and Bradshaw, 2013;Dallas et al, 2016a,b;Gagnaire et al, 2017;Festarini et al, 2019;Arcanjo et al, 2020).…”

Section: Introductionmentioning

confidence: 99%