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Effect of elevated lithium on the waterside corrosion of zircaloy-4: Experimental and predictive studies

Abstract

Lithium and boron content in the coolant are known to influence the oxidation behaviour of the fuel cladding. Since new PWR operating conditions could consist in an increase of the lithium and the boron concentration in the coolant early in the cycle, a specific study has been conducted to analyze and to predict the effect of such new water chemistry conditions on the oxidation kinetics of the Zircaloy-4 material. Experimental studies have been performed in out-of-pile loop tests, under one and two phase flow heat transfer in various water chemistry conditions (0{<=}Li{<=}350 ppm, 0{<=}B{<=}1000 ppm, 0{<=}K{<=}56 ppm). A simulation of the effect of elevated lithium on the corrosion has been made using the semi-empirical COCHISE corrosion code. Under one phase flow heat transfer conditions, the addition of lithium hydroxide in the coolant increases the oxidation rate, essentially in the post-transition regime for low lithium levels ({<=} 75 ppm) and immediately in the pre-transition phase for very high lithium level (350 ppm). Under two phase flow heat transfer, an enhancement of the corrosion is observed in the area of the rod submitted to boiling. Based on the out-of-pile loop test performed in presence of KOH instead of LiOH, such an enhancement  More>>
Authors:
Pecheur, D; Giordano, A; Picard, E; Billot, P; [1]  Thomazet, J [2] 
  1. CEA Centre d`Etudes de Cadarache, 13 - Saint-Paul-lez-Durance (France)
  2. FRAMATOME, Nuclear Fuel Div., Lyon (France)
Publication Date:
Feb 01, 1997
Product Type:
Technical Report
Report Number:
IAEA-TECDOC-927; CONF-9310467-
Reference Number:
SCA: 210200; PA: AIX-28:034568; EDB-97:060672; SN: 97001775144
Resource Relation:
Conference: Technical committee meeting on influence of water chemistry on fuel cladding behaviour, Rez (Czech Republic), 4-8 Oct 1993; Other Information: PBD: Feb 1997; Related Information: Is Part Of Influence of water chemistry on fuel cladding behaviour. Proceedings of a technical committee meeting; PB: 499 p.
Subject:
21 NUCLEAR POWER REACTORS AND ASSOCIATED PLANTS; LITHIUM; ZIRCALOY 4; CORROSION; BOILING; BORON; C CODES; EXPERIMENTAL DATA; FUEL-COOLANT INTERACTIONS; HEAT TRANSFER; OXIDATION; PWR TYPE REACTORS; THEORETICAL DATA; TWO-PHASE FLOW; WATER CHEMISTRY
OSTI ID:
462438
Research Organizations:
International Atomic Energy Agency, Vienna (Austria)
Country of Origin:
IAEA
Language:
English
Other Identifying Numbers:
Journal ID: ISSN 1011-4289; Other: ON: DE97622401; TRN: XA9743687034568
Availability:
INIS; OSTI as DE97622401
Submitting Site:
INIS
Size:
pp. 111-130
Announcement Date:

Citation Formats

Pecheur, D, Giordano, A, Picard, E, Billot, P, and Thomazet, J. Effect of elevated lithium on the waterside corrosion of zircaloy-4: Experimental and predictive studies. IAEA: N. p., 1997. Web.
Pecheur, D, Giordano, A, Picard, E, Billot, P, & Thomazet, J. Effect of elevated lithium on the waterside corrosion of zircaloy-4: Experimental and predictive studies. IAEA.
Pecheur, D, Giordano, A, Picard, E, Billot, P, and Thomazet, J. 1997. "Effect of elevated lithium on the waterside corrosion of zircaloy-4: Experimental and predictive studies." IAEA.
@misc{etde_462438,
title = {Effect of elevated lithium on the waterside corrosion of zircaloy-4: Experimental and predictive studies}
author = {Pecheur, D, Giordano, A, Picard, E, Billot, P, and Thomazet, J}
abstractNote = {Lithium and boron content in the coolant are known to influence the oxidation behaviour of the fuel cladding. Since new PWR operating conditions could consist in an increase of the lithium and the boron concentration in the coolant early in the cycle, a specific study has been conducted to analyze and to predict the effect of such new water chemistry conditions on the oxidation kinetics of the Zircaloy-4 material. Experimental studies have been performed in out-of-pile loop tests, under one and two phase flow heat transfer in various water chemistry conditions (0{<=}Li{<=}350 ppm, 0{<=}B{<=}1000 ppm, 0{<=}K{<=}56 ppm). A simulation of the effect of elevated lithium on the corrosion has been made using the semi-empirical COCHISE corrosion code. Under one phase flow heat transfer conditions, the addition of lithium hydroxide in the coolant increases the oxidation rate, essentially in the post-transition regime for low lithium levels ({<=} 75 ppm) and immediately in the pre-transition phase for very high lithium level (350 ppm). Under two phase flow heat transfer, an enhancement of the corrosion is observed in the area of the rod submitted to boiling. Based on the out-of-pile loop test performed in presence of KOH instead of LiOH, such an enhancement of the corrosion appears to be due to a lithium enrichment in the oxide layer induced by boiling and not to a pH effect. The simulation of the increase of lithium content in the coolant from 2.2 to 3.5 ppm leads to an enhancement in corrosion rates which becomes only significant at high burn up. This predictive result of elevated lithium effect on corrosion is then compared with oxidation data derived from reactors operating under an elevated lithium regime. (author). 14 refs, 9 figs, 3 tabs.}
place = {IAEA}
year = {1997}
month = {Feb}
}