Tritium release from highly neutron irradiated constrained and unconstrained beryllium pebbles

Chakin, V.; Rolli, R.; Vladimirov, P.; Moeslang, A.

doi:10.1016/j.fusengdes.2015.04.027

Cited by 13 publications

(2 citation statements)

References 20 publications

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“…Then, assuming that it is a sphere with the same weight as the polyhedron, an approximate diameter of the spheres was calculated (see Table 1). The temperature-programmed desorption (TPD) tests were carried out using a flowthrough setup with an ionization chamber (IC) situated in the Fusion Materials Laboratory (FML) [20]. A helium purge gas containing 0.1 vol.…”

Section: Methodsmentioning

confidence: 99%

Tritium Desorption Behavior and Microstructure Evolution of Beryllium Irradiated at Low Temperature Up to High Neutron Dose in BR2 Reactor

Chakin

Rolli

Gaisin

et al. 2023

JNE

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The present study investigated the release of tritium from beryllium irradiated at 323 K to a neutron fluence of 4.67 × 1026 m−2 (E > 1 MeV), corresponding up to 22,000 appm helium and 2000 appm tritium productions. The TPD tests revealed a single tritium release peak during thermal desorption tests, irrespective of the heating mode employed. The tritium release peaks occurred at temperatures ranging from 1031–1136 K, depending on the heating mode, with a desorption energy of 1.6 eV. Additionally, the effective tritium diffusion coefficient was found to vary from 1.2 × 10−12 m2/s at 873 K to 1.8 × 10−10 m2/s at 1073 K. The evolution of beryllium microstructure was found to be dependent on the annealing temperature. No discernible differences were observed between the as-received state and after annealing at 473–773 K for 5 h, with a corresponding porosity range of 1–2%. The annealing at temperatures of 873–1373 K for 5 h resulted in the formation of large bubbles, with porosity increasing sharply above 873 K and reaching 30–60%.

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Section: Methodsmentioning

confidence: 99%

Tritium Desorption Behavior and Microstructure Evolution of Beryllium Irradiated at Low Temperature Up to High Neutron Dose in BR2 Reactor

Chakin

Rolli

Gaisin

et al. 2023

JNE

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“…In principle, all of these methods for swelling measurements of irradiated berylliumbased specimens result in close swelling values. However, for dimension and immersion methods in cases when an oxidation of the specimen surface or presence of numerous open channels [23] is observed, the swelling can have the slightly different values. Moreover, a comparison of the results after swelling measurements by immersion and helium pycnometry methods allows us to reach conclusions about availability of open and closed porosity in the irradiated specimen.…”

Section: Methodsmentioning

confidence: 99%

Swelling of Highly Neutron Irradiated Beryllium and Titanium Beryllide

Chakin

Fedorov

Gaisin

et al. 2022

JNE

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The swelling of beryllium and titanium beryllide after irradiation at 70–750 °C to neutron fluences of (0.25–8) · 1022 cm−2 (E > 1 MeV) was measured using methods of immersion, dimension, and helium pycnometry. Dependences of the swelling on the irradiation temperature and neutron dose were plotted and analyzed. The dose dependences show linear dependences of the swelling for all irradiation temperatures except 70 °C, where the swelling rate varies, depending on increasing neutron dose. Be-7Ti shows much less swelling than pure Be. Irradiation at 430–750 °C to neutron fluence of 1.82 · 1022 cm−2 (E > 1 MeV) leads to swelling of Be at about 50%; for Be-7Ti, it is 2.7%. The microstructure study shows that the formation of bubbles and pores in beryllium occurs much more intense than in titanium beryllide.

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Effects of Heat Treatment and Aging on Microstructural and Mechanical Properties of RAFM Steel

Qiu,

Zhang,

et al. 2024

JOM

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Tritium release from highly neutron irradiated constrained and unconstrained beryllium pebbles

Cited by 13 publications

References 20 publications

Tritium Desorption Behavior and Microstructure Evolution of Beryllium Irradiated at Low Temperature Up to High Neutron Dose in BR2 Reactor

Tritium Desorption Behavior and Microstructure Evolution of Beryllium Irradiated at Low Temperature Up to High Neutron Dose in BR2 Reactor

Swelling of Highly Neutron Irradiated Beryllium and Titanium Beryllide

Effects of Heat Treatment and Aging on Microstructural and Mechanical Properties of RAFM Steel

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