Published 1984 | Version v1
Book

Fracture predictions in Zircaloy fuel cladding

  • 1. Department of Mechanical Engineering, Auburn University, Auburn, AL

Description

Predictions of the maximum initial allowable temperature required to achieve a 40-year life in dry storage are made for Zircaloy clad spent fuel. Maximum initial temperatures of 360 to 4050C for irradiated spent fuel cladding (wet pool storage) are predicted. The technique utilized in this work is based on the deformation and fracture map methodology. Maps are presented for temperatures between 50 and 8500C and stresses between 5 and 500 MPa. These maps are then combined with both the known temperature history (an exponentially decaying one) of Zircaloy fuel cladding in dry storage and a life fracture rule to predict the rupture life of the cladding in dry storage. Predictions of the deformation and fracture map methodology are shown to be in good agreement with constant stress-constant temperature data

Additional details

Publishing Information

Publisher
American Society for Testing Materials.
Imprint Place
Philadelphia, PA (USA)
Imprint Title
Effects of radiation on material. STP 870 Vol. 2
Journal Page Range
p. 642-655.

Conference

Title
12. international symposium on effects of radiation on materials.
Dates
18-20 Jun 1984.
Place
Williamsburg, VA (USA).