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...

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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.
Description
Summary: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 fuel/clad chemical interaction are discussed.
Item Description:Published through SciTech Connect.
11/01/1987.
"anl-ifr--81"
"TI88025660"
Pahl, R G; Beck, W N; Sanecki, J E.
Physical Description:58 p. : digital, PDF file.

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