Report on fundamental modeling of irradiation-induced swelling and creep in FeCrAl alloys

Report on fundamental modeling of irradiation-induced swelling and creep in FeCrAl alloys [electronic resource]

In order to improve the accident tolerance of light water reactor (LWR) fuel, alternative cladding materials have been proposed to replace zirconium (Zr)-based alloys. Of these materials, there is a particular focus on iron-chromium-aluminum (FeCrAl) alloys due to much slower oxidation kinetics in h...

Full description

Saved in:
Bibliographic Details
Online Access: Online Access (via OSTI)
Corporate Author: Oak Ridge National Laboratory (Researcher)
Format: Government Document Electronic eBook
Language:English
Published: Washington, D.C. : Oak Ridge, Tenn. : United States. Office of the Assistant Secretary for Nuclear Energy ; distributed by the Office of Scientific and Technical Information, U.S. Department of Energy, 2016.
Subjects:
Creep.
Swelling.
Iron Base Alloys.
Chromium Alloys.
Aluminium Alloys.
Ternary Alloy Systems.
Temperature Range 0400-1000 K.
Fuel Cans.
Water Moderated Reactors.
Physical Radiation Effects.
Neutrons.
Dislocations.
Radiation Hardening.
Computerized Simulation.
Water Cooled Reactors.
Stability.
Accident-Tolerant Nuclear Fuels.
Materials Science.

Internet

Online Access (via OSTI)

Online

Holdings details from Online
Call Number: E 1.99:ornl/tm--2016/569
E 1.99:ornl/tm--2016/569 Available

Similar Items