Postirradiation examination of the HT9 clad fuel test X425 at 2.9% burnup

Postirradiation examination of the HT9 clad fuel test X425 at 2.9% burnup [electronic resource]

The X425 experiment was the first EBR-II subassembly to be irradiated with U-Pu-Zr metallic fuel clad in the HT9 alloy. This report summarizes our initial postirradiation examination of selected elements from X425 at 2.9% peak burnup. Fuel microstructure, swelling behavior, fission gas release, and...

Full description

Saved in:
Bibliographic Details
Online Access: Online Access (via OSTI)
Corporate Author: Argonne National Laboratory (Researcher)
Format: Government Document Electronic eBook
Language:English
Published: Washington, D.C. : Oak Ridge, Tenn. : United States. Department of Energy. ; distributed by the Office of Scientific and Technical Information, U.S. Department of Energy, 1987.
Subjects:
Alloy-Ht-9.
Physical Radiation Effects.
Fuel Cans.
Post-Irradiation Examination.
Burnup.
Microstructure.
Nuclear Fuels.
Swelling.
Uranium.
Plutonium.
Zirconium.
Materials Testing.
Reactor Materials.
General Studies Of Nuclear Reactors.
Engineering.
Materials Science.

Internet

Online Access (via OSTI)

Online

Holdings details from Online
Call Number: E 1.99:anl-ifr--81
E 1.99:anl-ifr--81 Available

Similar Items