Published September 1990 | Version v1
Report

Mechanistic understanding of Zircaloy corrosion in PWRs through a corrosion model

  • 1. CEA Centre d'Etudes Nucleaires de Cadarache, 13 - Saint-Paul-lez-Durance (France)
  • 2. Fragema, 69 - Lyon (France)

Description

Based on theoretical calculations and the comparison of corrosion data yielded by out-of-pile loop, PWR and autoclave tests, a semi-empirical corrosion model makes the following calculations possible: The fine thermal/hydraulic conditions in the environment of the fuel rods in the core of a PWR. The localized pH coolant and over-concentration of soluble species in the coolant under boiling regime. The axial and azimuthal corrosion data (oxide thicknesses and hydriding), associated with the physico-chemical determination of the coolant/cladding system. At present the model is developed to replace the semi-empirical correlations by fundamental equations which describe the mechanisms involved in the corrosion process. This paper emphasizes the heat flux effect which acts as a diffusional driving force in the oxidation process. An approximated solution of the diffusion problem accounts for gradients in concentration, stress and temperature. Theory is in good agreement with the corrosion data collected from autoclave (isothermal) and from out-of-pile loop (heat flux). (author). 5 refs, 9 figs

Part of:
Fundamental aspects of corrosion on zirconium base alloys in water reactor environments

Additional details

Publishing Information

Imprint Title
Fundamental aspects of corrosion on zirconium base alloys in water reactor environments
Imprint Pagination
275 p.
Journal Page Range
p. 173-179.
Report number
IWGFPT--34

Conference

Title
Technical committee meeting on fundamental aspects of corrosion on zirconium base alloys in water reactor environments.
Dates
11-15 Sep 1989.
Place
Portland, OR (USA).

INIS

Country of Publication
International Atomic Energy Agency (IAEA)
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
22038331
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S36: MATERIALS SCIENCE;
Resource subtype / Literary indicator
Conference
Descriptors DEI
COMPARATIVE EVALUATIONS; COOLANTS; CORROSION RESISTANCE; DIFFUSION; MATERIALS TESTING; PH VALUE; PWR TYPE REACTORS; STRUCTURAL MODELS; ZIRCALOY
Descriptors DEC
ALLOYS; ENRICHED URANIUM REACTORS; EVALUATION; POWER REACTORS; REACTORS; TESTING; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS; ZIRCONIUM ALLOYS; ZIRCONIUM BASE ALLOYS

Optional Information