Published July 1985 | Version v1
Report

Relationship between fuel element power and the leaching of 137Cs and 129I from irradiated UO2 fuel

  • 1. Whiteshell Nuclear Research Establishment, Pinawa, Manitoba

Description

The release of 137Cs and 129I from UO2 fuel element sections (typical of CANDU type reactors) exposed to water at 250C and at 1500C has been studied as a function of fuel irradiation history. The relationships between the quantities of these nuclides leached at 250C and the stable xenon release at the end of fuel irradiation are discussed. The results indicate that gap inventories of these nuclides are equal to or less than gap inventories of stable xenon. Preliminary evidence for the rapid leaching, at 1500C, of a fraction of the grain boundary inventory of 137Cs and 129I is also presented

Additional details

Publishing Information

Imprint Title
American Nuclear Society meeting on fission-product behavior and source term research: proceedings
Journal Page Range
p. 15.1-15.12.
Report number
EPRI-NP--4113-SR

Conference

Title
Topical meeting on fission product behavior and source term research.
Dates
15-19 Jul 1984.
Place
Snowbird, UT (USA).