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HAL Id: cea-02339108

https://hal-cea.archives-ouvertes.fr/cea-02339108

Submitted on 13 Dec 2019

HAL is a multi-disciplinary open access archive for the deposit and dissemination of sci-entific research documents, whether they are pub-lished or not. The documents may come from teaching and research institutions in France or abroad, or from public or private research centers.

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Corrosion and decommissioning

D. Feron, F Legendre, Marion Le Flem, Stéphane Gossé, Pierre Laghoutaris

To cite this version:

D. Feron, F Legendre, Marion Le Flem, Stéphane Gossé, Pierre Laghoutaris. Corrosion and decom-missioning. NUPP 2018 / ”2nd International conference on nuclear power plants structures, risk and decommissioning”, Jun 2018, Croydon, United Kingdom. �cea-02339108�

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www.cea.fr

CORROSION

&

DECOMMISSIONING

NUPP 2018 - 2ndInternational Conference on Nuclear Power

Plants: Structures, Risk & Decommissioning Croydon, London, UK / 11-12 June 2018

Damien Féron, Fabrice Legendre, Marion Le Flem, Stéphane Gossé, Pierre

Laghoutaris

Den-Service de la corrosion et du comportement des matériaux dans leur environnement (SCCME), CEA, Université de Paris-Saclay, Gif-sur-Yvette, France | PAGE 1

CONTENT

Introduction / background

Thermodynamics (corium)

ATTILHA setup

Database

Material behavior & irradiation

Experimentation

Carbon & Stainless steels

Long term issues

Atmospheric corrosion

Fukushima

Unit 3

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INTRODUCTION

Nuclear facility life cycle

Siting of nuclear facility

Design of nuclear facility

Construction & commissioning

Operation, management & maintenance

Severe accident management

Decommissioning of nuclear installations

Nuclear waste management

6 FÉVRIER 2019

Bold type: corrosion issues

| PAGE 3 CEA – Damien Féron | 2018

INTRODUCTION

Decommissioning of nuclear reactors

110 commercial power reactors, 48 prototypes and over 250 research

reactors have been retired from operation.

About 17 of these had full decommissioning.

12 reactors closed following an accident/incident, including 8 (partial)

core melts:

TMI (USA-1979)

Chernobyl (Ukraine – 1986) Fukushima Daiichi (Japan, 2011)

Corrosion issues

During the dismantling when it is not immediate Specific issues after core melt

Nuclear waste interim & geological storages

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INTRODUCTION

Importance of corrosion management during

decommissioning

Structural materials have been chosen for reactor standard operation,

investigated for their behavior during accidents, but not for

decommissioning conditions while they still have functions

(mechanical, tightness,…)

Long term issues (deferred dismantling)

After core melt:

knowledge of the corium interactions, fuel debris and fission products (physico-chemical status) & behaviour

corrosion & radiations

behavior of key components after accident conditions

| PAGE 5 CEA – Damien Féron | 2018

Development of fundamental knowledge

INTRODUCTION

Subjects related to decommissioning investigated at

the CEA “Corrosion Service”

Thermodynamics (corium)

Experimental facilities

Database

Material behavior & irradiation

Experimentations and radiolysis calculations

Carbon steels & Stainless steels

Long term issues

Atmospheric corrosion / Microbial Influenced corrosion

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HIGH TEMPERATURE

THERMODYNAMIC TOOLS FOR THE

INVESTIGATION OF CORIUM BEHAVIOR

Experimental setup

Thermodynamic modeling

6 FÉVRIER 2019 | PAGE 7

CEA | 10 AVRIL 2012

In-vessel & Ex-vessel Core Melts

In-vessel corium Interactions:

MOx + Zircaloy + stainless steel + Inconel + B4C + Fission Products “Prototypic” in-vessel corium system:U-Zr-Fe-O

TheMolten Corium Concrete Interactionstarts:

 The components of the concrete (CaO, SiO2, Al2O3, MgO, H2O, CO2) are added

to the already complex in-vessel system (U-Zr-O-Fe)

As a first approximation the Fe-U-Zr-Al-Ca-Si-O system is representative of an ex-vessel corium

Issue

: core melt configurations

A better thermodynamic description of the in & ex-vessel corium sub-systems is needed to improve the thermal and thermo-hydraulics codes accuracy

Need of exp. data at very high temperatures

1500°C ≤ T ≤ 3200°C

Development of a specific exp. setup

Fukushima

| PAGE 8 CEA – Damien Féron | 2018

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Experimental development

Advanced Temperature and Thermodynamics Investigation by a Laser Heating Approach

ATTILHA: Development of a setup for high solid/liquid transitions

Contactless  Aerodynamic levitation

Containerless

Acquisition of data on corium systems

Phase diagram data (liquidus, solidus)

Thermo-radiative properties (IR emissivity)

2 different ATTILHA configurations:

All the instruments are synchronized

Validation on transitions in oxide systems

Al

2

O

3

Al

2

O

3

-ZrO

2

| PAGE 9 CEA – Damien Féron | 2018

Miscibility gap in the Fe-Zr-O system

T=3073 K

Starting composition: Fe0.85Zr0.15

Composition moved into the ternary Fe-Zr- system tie-line: Fe0.97O0.03– Fe0.05Zr0.32O0.63

Levitation gas: He

O

Observation of dynamic phenomena:

Formation of 2 liquids in-situ

Estimation of the emissivity ratio between the two liquids

 εoxide~ 2εmetal

Infrared camera footage

Real speed 200 Hz Video player 12.5 Hz

Digital level

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MATERIAL BEHAVIOR & IRRADIATION

- EXPERIMENTATION

- CARBON & STAINLESS STEELS

6 FÉVRIER 2019 | PAGE 11 CEA | 10 AVRIL 2012

6 FÉVRIER 2019

Experimental facility: CASIMIR

Irradiation gamma

performed in the POSEIODON pond, at CEA-Saclay

CORROSION & IRRADIATION

Water chemistry Gas (air

or other)

S. Perrin & al., LTC2016, Toronto, 2016

| PAGE 12 CEA – Damien Féron | 2018

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Radiolysis & Electrochemistry

Front part 

link to the cyclotron (H+)

Middle part  Tank of the cell

Back part 

Temperature, pressure & hydrogen pressure sensors

Temperature  300 (°C) Pressure  90 (bar)

Hydrogen pressure  400 (mbar) Free potential  E316Lvs. Platinum (V)

High temperature and high pressure electrochemical cell

High temperature and high pressure electrochemical cell

Brevet n° 08 56970

du 15.10.2008, CEA (DEN & DSM)-LSI

| PAGE 13 CEA – Damien Féron 2018

S. Perrin & al., LTC2016, Toronto, 2016

ATMOSPHERIC CORROSION OF CARBON STEEL

Corrosion of carbon steel (A37) in a closed humid atmosphere

Influence of the humidity at temperature 80°C,

and of irradiation gamma

(20 & 80 Gy.h

-1

)

Generalized corrosion, but not uniform

Lower corrosion rate at 70% HR than at 100% HR, with or without irradiation Higher corrosion rate at 100% HR and 80 Gy.h-1

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-50 -45 -40 -35 -30 -25 -20 -15 -10 -5 0 0 1000 2000 3000 4000 5000 6000 Temps (s) E( 3 16 L )-E( Pt ) (m V) 20 22 24 26 28 30 32 34 P( H2 ) (m bar ) tON= 60s tOFF= 600s

PWR water chemistry (300°C) /316L

in situ

measurement of the radiolytic

production of H

2

Importance of the temperature

Radiolysis & Electrochemistry

Effects of radiolysis on the electrochemical behaviour

of stainless steels

Effects of radiolysis on the electrochemical behaviour

of stainless steels

B. Muzeau & al., JNM 419 (2011) 241–247

Potential and hydrogen partial pressure evolution

at 300°C, proton flux = 6.6x1011H+.cm-2.s-1

| PAGE 15 CEA – Damien Féron 2018

LONG TERM ISSUES

- ATMOSPHERIC CORROSION

- MICROBIAL CORROSION

- CORROSION MODELLING &

SIMULATION

6 FÉVRIER 2019 | PAGE 16 CEA | 10 AVRIL 2012

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ATMOSPHERIC CORROSION

Phenomena:

outdoor and indoor atmospheric corrosion, including

closed atmospheres.

Applications:

deferred dismantling, interim storage, first period of

geological disposal.

Observations:

shape of localised corrosions not in accordance with the

well-known “Evans” droplet

6 FÉVRIER 2019

After cleaning

Localised corrosion at the periphery of the droplet when evaporation occurs

Evans droplet scenario

- Pitting in the middle of the droplet

- No corrosion at the periphery (cathodic reaction)

| PAGE 17 CEA – Damien Féron | 2018

Corrosion under Evaporating Salty Sessile Droplets

Evaporating corrosion droplet

Low salt concentration: c0= 10-3M NaCl

Evaporationof pinned salty sessile droplets causes peripheral salt enrichment Local chloride enrichmentpromotes the initiation of corrosion

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Strong correlation between evaporation process and

localization of corrosion phenomena

6 FÉVRIER 2019

Evaporating corrosion droplet

Soulié, Lequien & al., Materials and Corrosion, Sept. 2017, Vol. 68 Issue 9, p927-93

Schematic diagram of the processes Experimental observations on iron | PAGE 19 CEA – Damien Féron | 2018

CONCLUSION

Decommissioning and corrosion

Fundamental knowledge needed in several areas

Thermodynamics

Effects of irradiation (low & high doses)

Corrosion phenomena even at low temperatures

Modeling and simulation

Prediction of phases and compounds in melt core

Long term prediction & coupling of multi-corrosion issues

Protective measures

| PAGE 20 CEA – Damien Féron | 2018

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IWSSTP 11 | 23rd June, 2016

Damien Féron / damien.feron@cea.fr

Commissariat à l’énergie atomique et aux énergies alternatives Centre de Saclay| 91191 Gif-sur-Yvette Cedex

T. +33 (0)1 69 08 20 65 |F. +33 (0)1 69 08 15 86

Etablissement public à caractère industriel et commercial |RCS Paris B 775 685 019

Direction de l’Energie Nucléaire Département de Physico-Chimie Service de la Corrosion et du Comportement des Matériaux dans leur environnement

CEA de Saclay

THANK YOU FOR YOUR ATTENTION

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