Published July 2005
| Version v1
Book
Cladding liner surface effects and PCI
- 1. Studsvik Nuclear AB (Sweden)
- 2. Westinghouse Electric Sweden AB (Sweden)
Description
A soft, metallurgically bonded inner layer of zirconium with small quantities of alloying elements is used in BWR zircaloy fuel cladding as a remedy against pellet-cladding interaction (PCI) fuel failures. The inner surface of the liner becomes significantly hardened during irradiation. Local micro-hardness and elemental composition profiles close to the inner surface of the cladding liner have been measured in a fuel rod subjected to power ramp testing. In addition, small incipient cracks in the hardened zone have been detected and characterised after the ramp test. The extent of the hardening, its cause and its impact on the initiation of PCI cracks are discussed in the paper. (authors)
Additional details
Publishing Information
- Publisher
- Organisation for Economic Co-Operation and Development - Nuclear Energy Agency
- Imprint Place
- Paris (France)
- ISBN
- 92-64-01157-9
- Imprint Title
- Pellet-clad Interaction in Water Reactor Fuels
- Imprint Pagination
- 548 p.
- Journal Page Range
- p. 273-278
Conference
- Title
- Pellet-clad Interaction in Water Reactor Fuels
- Acronym
- Seminar
- Dates
- 9-11 Mar 2004
- Place
- Aix-en-Provence (France)
INIS
- Country of Publication
- France
- Country of Input or Organization
- Nuclear Energy Agency of the OECD (NEA)
- INIS RN
- 37021746
- Subject category
- S36: MATERIALS SCIENCE;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CLADDING; FUEL-CLADDING INTERACTIONS; HARDENING; PHYSICAL RADIATION EFFECTS; ZIRCALOY
- Descriptors DEC
- ALLOYS; DEPOSITION; RADIATION EFFECTS; SURFACE COATING; TRANSITION ELEMENT ALLOYS; ZIRCONIUM ALLOYS; ZIRCONIUM BASE ALLOYS