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Corrosion of zirconium alloys in nuclear reactors: A model for irradiation induced enhancement by local radiolysis in the porous oxide

Abstract

An analysis has been undertaken of the various cases of local enhancement of corrosion rate of zirconium alloys under irradiation. It is observed that in most cases a strong emission of energetic {beta}{sup -} is present leading to a local energy deposition rate higher than the core average. This suggests that the local transient radiolytic oxidizing species produced in the coolant by the {beta}{sup -} particles could contribute to corrosion enhancement, by increasing the local corrosion potential. This process is applicable to the local enhanced corrosion found in front of stainless steels structural parts, due to the contribution of Mn, and in front of Pt inserts or Cu-rich cruds. It explains also the irradiation corrosion enhancement of Cu-Zr alloys. Enhanced corrosion around neutron absorbing material is explained similarly by pair production from conversion of high energy capture photons in the cladding, leading to energetic electrons. The same process was found to be active with other highly ionizing species like {alpha} from Ni-rich alloys and fission products in homogeneous reactors. Due to the changes induced by the irradiation intensity on the concentration of the radiolytic species, the coolant chemistry, that controls the boundary conditions for oxide growth, has to be analyzed  More>>
Authors:
Lemaignan, C; Salot, R [1] 
  1. CEA/DRN/DTP, CENG-SECC, Grenoble (France)
Publication Date:
Feb 01, 1997
Product Type:
Conference
Report Number:
IAEA-TECDOC-927; CONF-9310467-
Reference Number:
SCA: 210000; PA: AIX-28:034464; EDB-97:060625; SN: 97001775100
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; POROUS MATERIALS; RADIOLYSIS; ZIRCONIUM ALLOYS; CORROSION; IRRADIATION; NUCLEAR POWER PLANTS
OSTI ID:
462425
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: XA9743688034464
Availability:
INIS; OSTI as DE97622401
Submitting Site:
INIS
Size:
pp. 131-142
Announcement Date:
May 08, 1997

Citation Formats

Lemaignan, C, and Salot, R. Corrosion of zirconium alloys in nuclear reactors: A model for irradiation induced enhancement by local radiolysis in the porous oxide. IAEA: N. p., 1997. Web.
Lemaignan, C, & Salot, R. Corrosion of zirconium alloys in nuclear reactors: A model for irradiation induced enhancement by local radiolysis in the porous oxide. IAEA.
Lemaignan, C, and Salot, R. 1997. "Corrosion of zirconium alloys in nuclear reactors: A model for irradiation induced enhancement by local radiolysis in the porous oxide." IAEA.
@misc{etde_462425,
title = {Corrosion of zirconium alloys in nuclear reactors: A model for irradiation induced enhancement by local radiolysis in the porous oxide}
author = {Lemaignan, C, and Salot, R}
abstractNote = {An analysis has been undertaken of the various cases of local enhancement of corrosion rate of zirconium alloys under irradiation. It is observed that in most cases a strong emission of energetic {beta}{sup -} is present leading to a local energy deposition rate higher than the core average. This suggests that the local transient radiolytic oxidizing species produced in the coolant by the {beta}{sup -} particles could contribute to corrosion enhancement, by increasing the local corrosion potential. This process is applicable to the local enhanced corrosion found in front of stainless steels structural parts, due to the contribution of Mn, and in front of Pt inserts or Cu-rich cruds. It explains also the irradiation corrosion enhancement of Cu-Zr alloys. Enhanced corrosion around neutron absorbing material is explained similarly by pair production from conversion of high energy capture photons in the cladding, leading to energetic electrons. The same process was found to be active with other highly ionizing species like {alpha} from Ni-rich alloys and fission products in homogeneous reactors. Due to the changes induced by the irradiation intensity on the concentration of the radiolytic species, the coolant chemistry, that controls the boundary conditions for oxide growth, has to be analyzed with respect to the local value of the energy deposition rate. An analysis has been undertaken which shows that, in a porous media, the water is exposed to a higher intensity than bulk water. This leads to a higher concentration of oxidizing radiolytic species at the root of the cracks of the porous oxide, and increases the corrosion rate under irradiation. This mechanism, deduced from the explanation proposed for localized irradiation enhanced corrosion, can be extended to the whole reactor core, where the general enhancement of Zr alloys corrosion under irradiation could be attributed to the general radiolysis in the porous zirconia. (author). 18 refs, 3 figs, 3 tabs.}
place = {IAEA}
year = {1997}
month = {Feb}
}