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)

Part of:
Pellet-clad Interaction in Water Reactor Fuels

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

Optional Information