ZrH

Zirconium hydride (ZrH) is an intermetallic compound formed by the absorption of hydrogen into zirconium metal, creating a brittle ceramic-like material with significantly altered mechanical properties compared to pure zirconium. It is encountered in nuclear fuel cladding applications, where it forms as an undesirable corrosion byproduct during zirconium alloy exposure to water and steam, and is also studied as a hydrogen storage medium and as a neutron moderator material in specialized reactor designs. Engineers must manage ZrH formation in nuclear systems because excessive hydride precipitation degrades the ductility of zirconium cladding and increases embrittlement risk; conversely, controlled hydride phases are leveraged in some advanced reactor concepts where hydrogen moderation or tritium handling is relevant.