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.
Authors
- D. P. Shornikov
- A. V. Bratsuk (ORCID: https://orcid.org/0000-0002-8285-9905)
- V. V. Mikhalchik (ORCID: https://orcid.org/0000-0003-3515-2074)
- A. A. Urusov (ORCID: https://orcid.org/0009-0002-1014-8765)
- Nikolay Samotaev (ORCID: https://orcid.org/0000-0002-7761-4057)
- M. S. Staltsov (ORCID: https://orcid.org/0000-0002-2454-4817)
- Г. А. Иванов
- K K Polunin (ORCID: https://orcid.org/0009-0000-5902-1242)
- S. Yu. Kovtun
- A. V. Tenishev (ORCID: https://orcid.org/0000-0002-2424-1656)
Institutions
- Research Institute of Scientific Research and Production Association (RU)
- National Research Nuclear University MEPhI (RU)
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
- 0.00