Corrosion of Electron-Irradiated Zr-2.5Nb and Zircaloy-2


Book Description

We used 10-MeV electrons to rapidly produce radiation damage in zirconium alloys, investigated whether electrons produced the same microstructural changes as neutrons, then performed post-irradiation corrosion tests to determine whether electron-irradiated materials displayed similar corrosion behavior to neutron-irradiated materials.




Studies of Zirconium Alloy Corrosion and Hydrogen Uptake During Irradiation


Book Description

The in-reactor corrosion and hydrogen pickup of Zircaloy-2 and Zr-2.5Nb pressure tube materials are being studied in two test loops: a light water loop in the NRU research reactor, and a new heavy water loop in the Halden reactor. The complimentary test programs examine the corrosion behavior of small specimens as a function of fast neutron flux and fluence, temperature, water chemistry, and specimen pre-oxidation.













Zirconium in the Nuclear Industry


Book Description







Zirconium in the Nuclear Industry


Book Description