Protective Coatings on Hafnium Hydride and Their Effect on Its Thermal Decomposition

Hafnium hydride is studied as an absorber for fast neutron reactors. A high value of the neutron absorption cross section is noted that is retained by all hafnium isotopes formed during neutron irradiation in reactor. However, there is a risk of hafnium hydride decomposing in the range of 600–700°C, which corresponds to the operating temperature of absorbers in fast neutron reactors. An approach is proposed to reduce hydrogen evolution from hafnium hydride that consists of applying a protective hafnium oxide coating to it. Hafnium hydride samples are annealed in helium at temperatures of 1200°C in a synchronic thermal analysis setup. Hydrogen desorption starts at a temperature of 640°C. Complete hydrogen evolution is observed at a temperature of 1200°C. A substantial drop in hydrogen evolution at low temperatures is seen when annealing samples with applied coatings. A special setup is developed that allows the thermal testing of hydride materials in a liquid sodium environment. Hafnium hydride is annealed in liquid sodium at 700°C. Synchronic thermal analysis of samples after exposure to sodium reveals a drop in the emission of gas that is associated with an increase in the thickness of the oxide layers on the surfaces of samples.

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Publication Details

Journal
Physics of Atomic Nuclei
Published
2024-12-01
DOI
https://doi.org/10.1134/s1063778824100466
Primary Topic
Nuclear Materials and Properties
Type
article
Field-Weighted Citation Impact
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article

Protective Coatings on Hafnium Hydride and Their Effect on Its Thermal Decomposition

D. P. Shornikov, A. V. Bratsuk, V. V. Mikhalchik, A. A. Urusov et al.
Physics of Atomic Nuclei
Nuclear Materials and Properties
article

Protective Coatings on Hafnium Hydride and Their Effect on Its Thermal Decomposition

D. P. Shornikov, A. V. Bratsuk, V. V. Mikhalchik, A. A. Urusov, Nikolay Samotaev, M. S. Staltsov, Г. А. Иванов, K K Polunin, S. Yu. Kovtun, A. V. Tenishev
article en

Abstract

Hafnium hydride is studied as an absorber for fast neutron reactors. A high value of the neutron absorption cross section is noted that is retained by all hafnium isotopes formed during neutron irradiation in reactor. However, there is a risk of hafnium hydride decomposing in the range of 600–700°C, which corresponds to the operating temperature of absorbers in fast neutron reactors. An approach is proposed to reduce hydrogen evolution from hafnium hydride that consists of applying a protective hafnium oxide coating to it. Hafnium hydride samples are annealed in helium at temperatures of 1200°C in a synchronic thermal analysis setup. Hydrogen desorption starts at a temperature of 640°C. Complete hydrogen evolution is observed at a temperature of 1200°C. A substantial drop in hydrogen evolution at low temperatures is seen when annealing samples with applied coatings. A special setup is developed that allows the thermal testing of hydride materials in a liquid sodium environment. Hafnium hydride is annealed in liquid sodium at 700°C. Synchronic thermal analysis of samples after exposure to sodium reveals a drop in the emission of gas that is associated with an increase in the thickness of the oxide layers on the surfaces of samples.

Physics of Atomic NucleiVol. 87(11)
Research Institute of Scientific Research and Production Association (RU), National Research Nuclear University MEPhI (RU)
Openalex Percentile: Top 83%
Nuclear Materials and Properties
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