Published 1987 | Version v1
Book

Laboratory simulation of rod-to-rod mechanical interactions during postulated loss-of-coolant accidents in a PWR involving cladding oxidation

  • 1. UKAEA Northern Research Labs., Springfields (UK)

Description

Creep deformation of Zircaloy cladding in postulated PWR loss-of-coolant accidents may lead to rod-to-rod mechanical interactions. Tests have been performed in the electrically heated FOURSQUARE rig at 7500C and 8500C in steam to investigate this effect. Conservatisms inherent in a simple 'square with rounded corners' coolant channel blockage model have been quantified; about 5-10% flow area may remain even at strains which in ideal circumstances would give total blockage. Reduction of average burst strains produced by an oxide layer (up to 13 μm) has been demonstrated, resulting from strain concentration at oxide cracks. (author)

Additional details

Publishing Information

Publisher
British Nuclear Energy Society.
Imprint Place
London (UK)
ISBN
0 7277 1306 X
Imprint Title
Materials for nuclear reactor core applications. 2 v.
Imprint Pagination
454 p.
Journal Page Range
v. 1 p. 79-85.

Conference

Title
International conference on materials for nuclear reactor core applications.
Dates
27-29 Oct 1987.
Place
Bristol (UK).