Hydrogen-enhanced degradation and oxide effects in zirconium alloys for nuclear applications

A Zieliński, S Sobieszczyk - International journal of hydrogen energy, 2011 - Elsevier
The zirconium alloys used in nuclear industry include mainly Zr–Sn and Zr–Nb alloys of
different chemical composition, microstructure and susceptibility to both hydrogen …

Mechanisms of hydride nucleation, growth, reorientation, and embrittlement in zirconium: A review

YJ Jia, WZ Han - Materials, 2023 - mdpi.com
Zirconium (Zr) hydrides threaten the reliability of fuel assembly and have repeatedly induced
failures in cladding tubes and pressure vessels. Thus, they attract a broad range of research …

Hydrogen in Zircaloy: Mechanism and its impacts

S Suman, MK Khan, M Pathak, RN Singh… - International Journal of …, 2015 - Elsevier
Zircaloy is extensively used as a nuclear fuel cladding tube material. The fuel cladding
encapsulates radioactive fuel pellet and it is resorted to an exceptionally harsh environment …

Precipitation characteristics and distributions of subsurface hydrides in zirconium

YJ Jia, IJ Beyerlein, WZ Han - Acta Materialia, 2021 - Elsevier
Hydride precipitates that develop in Zr after absorbing hydrogen can impart significant
material hardening and embrittlement. Here, we use electrolytic hydrogen charging to …

Modeling and tests on the damage and fracture behaviors of non-irradiated zirconium alloys with different hydrogen concentrations at RT and 350° C

G Ding, J Zhang, J Wang, Y Li, X Jian, S Ding… - Journal of Nuclear …, 2023 - Elsevier
Zirconium alloys are widely used as the materials of nuclear cladding tubes or some other
structural components. The chemical reaction of zirconium with coolant water leads to …

Deformation mechanism of embedded hydride within the polycrystalline zirconium matrix

H Ghaffarian, D Jang - Journal of Nuclear Materials, 2022 - Elsevier
It is widely accepted that the characteristics of hydrides in the Zr-based nuclear fuel cladding
are critical factors determining the integrity of the spent fuel. Therefore, to mitigate any harm …

Accelerated optimization of chromium coating microstructures for nuclear fuel applications through electrochemical corrosion testing

B Aronson, P Fourspring, J Reiss, B Ensor… - Journal of Nuclear …, 2023 - Elsevier
Corrosion of zirconium alloy fuel cladding in nuclear reactors is one of the main limiting
factors to component lifespan. Protective coatings may be applied to reduce the corrosion …

Influence of temperature on threshold stress for reorientation of hydrides and residual stress variation across thickness of Zr–2.5 Nb alloy pressure tube

RN Singh, RL Mikin, GK Dey, DN Sah, IS Batra… - Journal of nuclear …, 2006 - Elsevier
Threshold stress, σth, for reorientation of hydrides in cold worked and stress-relieved
(CWSR) Zr–2.5 Nb pressure tube material was determined in the temperature range of 523 …

Microvoids in electrochemically hydrogenated titanium-based alloys

E Brosh, NU Navi, BA Rosen, N Eliaz - international journal of hydrogen …, 2021 - Elsevier
In a recent study, it was observed that electrochemical charging with hydrogen produces
microvoids both in wrought and in additively manufactured, electron beam melted (EBM) Ti …

Influence of hydride orientation on fracture toughness of CWSR Zr-2.5% Nb pressure tube material between RT and 300 C

RK Sharma, S Sunil, BK Kumawat, RN Singh… - Journal of Nuclear …, 2017 - Elsevier
An experimental setup was designed, fabricated and used to form radial hydrides in Zr-2.5%
Nb alloy pressure tube spool. The design of setup was based on ensuring a hoop stress in …