The hydrogen emission of zirconium hydride at high temperature is a challenging issue for many researchers. The hydrogen emission content of zirconium hydride pins should be evaluated to confirm the application feasibility. The comparison of theory analysis and experiment data indicated Richardson’s Law could offer a conservative result for calculating the hydrogen emission content of zirconium hydride pins at high temperature. Furthermore, the methods of preventing hydrogen loss should be developed for the purpose of extending the work temperature or time. The results showed a ZrO2 layer prepared for zirconium hydride could not prevent hydrogen loss after exposure at 923K in an inert environment and ZrO2 transformed into Zr3O gradually due to the opposite movement of hydrogen and oxygen. Finally, a further improvement to prevent hydrogen loss was developed. The zirconium hydride with a ZrO2 layer in the cladding of He+CO2 exhibited no significant reduction of hydrogen content. It is helpful to prevent the hydrogen loss by increasing the oxygen potential on the outside of ZrO2 layer.
Skip Nav Destination
2017 25th International Conference on Nuclear Engineering
July 2–6, 2017
Shanghai, China
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-5780-9
PROCEEDINGS PAPER
A Study on Hydrogen Emission of Zirconium Hydride Available to Purchase
Fu Xiaogang,
Fu Xiaogang
China Institute of Atomic Energy, Beijing, China
Search for other works by this author on:
Qin Bo,
Qin Bo
China Institute of Atomic Energy, Beijing, China
Search for other works by this author on:
Ma Haoran,
Ma Haoran
China Institute of Atomic Energy, Beijing, China
Search for other works by this author on:
Zhang Jinquan,
Zhang Jinquan
China Institute of Atomic Energy, Beijing, China
Search for other works by this author on:
Long Bin
Long Bin
China Institute of Atomic Energy, Beijing, China
Search for other works by this author on:
Fu Xiaogang
China Institute of Atomic Energy, Beijing, China
Qin Bo
China Institute of Atomic Energy, Beijing, China
Ma Haoran
China Institute of Atomic Energy, Beijing, China
Zhang Jinquan
China Institute of Atomic Energy, Beijing, China
Long Bin
China Institute of Atomic Energy, Beijing, China
Paper No:
ICONE25-67271, V002T03A092; 3 pages
Published Online:
October 17, 2017
Citation
Xiaogang, F, Bo, Q, Haoran, M, Jinquan, Z, & Bin, L. "A Study on Hydrogen Emission of Zirconium Hydride." Proceedings of the 2017 25th International Conference on Nuclear Engineering. Volume 2: Plant Systems, Structures, Components and Materials. Shanghai, China. July 2–6, 2017. V002T03A092. ASME. https://doi.org/10.1115/ICONE25-67271
Download citation file:
17
Views
Related Proceedings Papers
Related Articles
Microstructure and Nanoindentation Studies of Hydridated Zircaloy-4 Claddings After High Temperature Oxidation
ASME J of Nuclear Rad Sci (April,2021)
From Micro to Nano: Material Characterization Methods for Testing of Nuclear Core and Structural Materials
ASME J of Nuclear Rad Sci (July,2019)
Relationship Between Oxide-Ion Conductivity and Ordering of Oxygen Vacancy in the Ln 2 Zr 2 O 7 ( Ln = La, Nd, Eu) System Using High Temperature XRD
J. Fuel Cell Sci. Technol (October,2011)
Related Chapters
Mechanical Behavior of Zircaloy-4 in the Presence of Hydrogen in Solid Solution at Elevated Temperatures
Zirconium in the Nuclear Industry: 20th International Symposium
Advanced PWR Cladding Development through Extensive In-Reactor Testing
Zirconium in the Nuclear Industry: 20th International Symposium
Effect of Chromium Content on the On-Cooling Phase Transformations and Induced Prior-β Zr Mechanical Hardening and Failure Mode (in Relation to Enhanced Accident-Tolerant Fuel Chromium-Coated Zirconium-Based Cladding Behavior upon and after High-Temperature Transients)
Zirconium in the Nuclear Industry: 20th International Symposium