Journal Published Online: 03 June 2010
Volume 7, Issue 5

The Effect of Microstructure on Delayed Hydride Cracking Behavior of Zircaloy-4 Fuel Cladding—An International Atomic Energy Agency Coordinated Research Program

CODEN: JAIOAD

Abstract

The rate of delayed hydride cracking (DHC) has been measured in Zircaloy-4 fuel cladding in several metallurgical conditions using the pin-loading tension technique. In light water reactor (LWR) cladding in the cold-worked and cold-worked and stress-relieved conditions, the cracking rate followed Arrhenius behavior up to about 280 °C, but at higher temperatures the rate declined with no cracking above 300°C. Non-LWR cladding appeared to behave in the same manner. In LWR cladding in the recrystallized condition, the cracking rate was highly variable because it depended on KI within the test range up to 25 MPa√m, whereas in the other LWR claddings, cracking rate was independent of KI, indicating that KIH was below 11 MPa√m. The main role of microstructure was to control the material strength; the cracking rate increased as the strength increased. Although all the claddings had a radial texture, it did not protect the cladding from DHC. The DHC fracture surface consisted of flat broken hydrides, often in arcs, but no striations were observed, except in one specimen subjected to thermal cycles.

Author Information

Coleman, C.
Chalk River Laboratories (CRL), AECL, Chalk River, ON, Canada
Grigoriev, V.
Studsvik Nuclear AB, Nyköping, Sweden
Inozemtsev, V.
International Atomic Energy Agency (IAEA), Vienna, Austria
Markelov, V.
The Joint Stock Company A. A. Bochvar High-Technology Research Institute of Inorganic Materials (JSC VNIINM), Moscow, Russia
Roth, M.
Materials Testing Group, Institute for Nuclear Research (INR), Romanian Authority for Nuclear Activities (RAAN), Piteşti, Romania
Makarevicius, V.
Laboratory of Materials Research and Testing, Lithuanian Energy Institute (LEI), Kaunas, Lithuania
Kim, Y.
Zirconium Team, Korea Atomic Energy Research Institute (KAERI), Daejeon, Korea
Liaqat Ali, Kanwar
Pakistan Institute of Nuclear Science and Technology (PINST), Islamabad, Pakistan
Chakravarrty, J.
Mechanical Metallurgy Section, Materials Group, Bhabha Atomic Research Centre (BARC), Mumbai, India
Mizrahi, R.
Materials Dept., National Atomic Energy Commission (CNEA-CAC), San Martín, Pcia. de Buenos Aires, Argentina
Lalgudi, R.
Materials Science and Technology Centre, Energy and Nuclear Research Institute (ENRI), Sao Paulo, Brazil
Pages: 20
Price: $25.00
Related
Reprints and Permissions
Reprints and copyright permissions can be requested through the
Copyright Clearance Center
Details
Stock #: JAI103008
ISSN: 1546-962X
DOI: 10.1520/JAI103008