POST IRRADIATION TESTING CAPABILITIES OF EXPERIMENTAL REACTOR - - PowerPoint PPT Presentation

▶
post irradiation testing
SMART_READER_LITE
LIVE PREVIEW

POST IRRADIATION TESTING CAPABILITIES OF EXPERIMENTAL REACTOR - - PowerPoint PPT Presentation

Apr 22, 2023 333 likes •495 views

POST IRRADIATION TESTING CAPABILITIES OF EXPERIMENTAL REACTOR COMPONENTS AT THE LECI FACILITY FOR SERVICE LIFE ASSESSMENT P. GAVOILLE, K.COLAS, B. KAPUSTA CEA Saclay, Universit Paris- Saclay, DEN, Service dEtudes des Matriaux Irradis,

slide-1
SLIDE 1

POST IRRADIATION TESTING CAPABILITIES OF EXPERIMENTAL REACTOR COMPONENTS AT THE LECI FACILITY FOR SERVICE LIFE ASSESSMENT

RRFM – IGORR, SYDNEY, AUSTRALIA, DECEMBER 3-7TH 2017

  • P. GAVOILLE, K.COLAS, B. KAPUSTA

CEA Saclay, Université Paris-Saclay, DEN, Service d’Etudes des Matériaux Irradiés, F-91191, Gif-sur-Yvette, France Presented by

  • C. GONNIER

CEA Cadarache, DEN, Département d’Etude des Réacteurs, 13108 Saint Paul lez Durance, France

| PAGE 1 RRFM - IGORR, Sydney, Australia, December 3-7th 2017

slide-2
SLIDE 2

BACKGROUND Assessment of the environmental degradation

  • f experimental core components is crucial for:
  • Safe et efficient operation of

experimental reactors

  • Determination of achievable service

time and replacement schedule Feedback is needed in particular on:

  • Mechanical properties evolution under

irradiation

  • Amount of Al to Si transmuted
  • Corrosion behavior
  • Swelling

| PAGE 2 RRFM - IGORR, Sydney, Australia, December 3-7th 2017

Orphee Reactor

Saclay, France

[Monographies DEN, Research Nuclear Reactors, CEA, 2012]

slide-3
SLIDE 3

THE LECI FACILITY

| PAGE 3 RRFM - IGORR, Sydney, Australia, December 3-7th 2017

M Line (2005) K Line (Active in 1959) I Line (1970)

  • Hotlab located in Saclay, near Paris,

France

  • Three lines of hotcells
  • Mission: characterization of non-fissile

irradiated materials

  • Determination of behavior in normal,

accidental or storage conditions

  • Prediction of in-service lifetime
  • Materials studied:
  • Gen 2&3 reactors (RPV Steel, Zr alloys)
  • MTR (Aluminum alloys)
  • Gen 4 reactors (sodium or gas cooled

FBR)

slide-4
SLIDE 4

CHARACTERIZATION OF MATERIALS AT THE LECI FACILITY

| PAGE 4

Microstructure Chemical Analyses Mechanical Behavior

Metallography Fractography Tensile tests Fracture Toughness Impact Testing LIBS EPMA EDS ICP-AES Orphee 4F cold finger

slide-5
SLIDE 5

MECHANICAL BEHAVIOR UNDER IRRADIATION (1/2)

| PAGE 5 RRFM - IGORR, Sydney, Australia, December 3-7th 2017

100 200 300 400 500 600 700 800 5 10 15 20 25 30 Fluence thermique (1022 n/cm2) Rp 0,2% (MPa)

5754-O ; MELUSINE ; Fth/Fr=0,6 5754-NET-O ; OSIRIS ; Fth/Fr=1,1 5754-NET-O ; RHF ; Fth/Fr=200 à 250 5154-O ; HFR ; Fth/Fr=0,95 6061-T6 ; HFIR ; Fth/Fr=2,5 ; v=3E-5 s-1 6061-T6 ; HFIR ; Fth/Fr=2,5 ; v=3E-3 s-1 6061-T6 ; HFIR ; Fth/Fr=1,66 6061-T6 ; BR2 ; Fth/Fr=2,25

Thermal fluence Yield strength 5754-NET-O 6061-T6 5154-O Example of hardening of aluminum alloys under irradiation as measured by tensile tests

[B.Kapusta, INSTN, Aluminum Behavior Under Irradiation, 2011]

slide-6
SLIDE 6

MECHANICAL BEHAVIOR UNDER IRRADIATION (2/2)

| PAGE 6 RRFM - IGORR, Sydney, Australia, December 3-7th 2017

20 40 60 80 100 120 140 160 180 200
  • 200 -180 -160 -140 -120 -100
  • 80
  • 60
  • 40
  • 20
20 40 60 80 100 120 140 160 180 200 220 240 260 280 300 Température (°C) Energie (Joules) Matériau témoin (non irradié) Points expérimentaux matériau témoin Matériau irradié Points expérimentaux matériau irradié

Fracture toughness Testing Servo-Hydraulic Machine (100 kN)

CT 20 specimen after test

350 J Charpy Impact Testing Ductile-Brittle transition (impact tests)

Application to surveillance programs

  • f core components for

MTRs and NPPs

Compact Tension unconventional thickness

slide-7
SLIDE 7

MICROSTRUCTURAL EXAMINATIONS (1/2)

| PAGE 7 RRFM - IGORR, Sydney, Australia, December 3-7th 2017

Microscopic characterization

Nuclearized SEM (Zeiss Supra 55)

[B.Kapusta, INSTN, Aluminum Behavior Under Irradiation, 2011]

Example of foiling corrosion on 5754- NET-O alloy with important hardening Dose: 4x1021 n/cm2 Ductile behavior Dose: 11.7x1022 n/cm2 Brittle behavior

Fractography of broken tensile sample surfaces

slide-8
SLIDE 8

MICROSTRUCTURAL EXAMINATIONS (2/2)

| PAGE 8

TEM (FEI 300 kV) TAP sample TEM sample

Nano-characterization

LEAP 4000X HR

Sample preparation by nuclearized FIB or electropolishing

Nuclearized FIB-SEM (Zeiss Auriga 40)

Nuclearized Atom Probe

[B.Kapusta, INSTN, Aluminum Behavior Under Irradiation, 2011]

Precipitate-free zone in heavily irradiated 6061-T6 (2x1023 nth/cm²) Mg-Si needles in Si-enriched 6061 alloy

[K. Buchanan et al. Acta Materialia, v132, 2017]

Nota :This work profited from a French government grant managed by the National Agency of Research under the program “Investments for the future” (ref. ANR-11-EQPX-0020

slide-9
SLIDE 9

CHEMICAL ANALYSES (1/2)

| PAGE 9 RRFM - IGORR, Sydney, Australia, December 3-7th 2017

Nuclearized Electron Probe Micro-Analyzer

Examples of EPMA analyses on 5754-NET-O Observation of precipitation and radiation-induced migration of chemical elements F th (0,0254 eV) = 8,2 x1022 n/cm2 DSiwt = 2,1%

Al Si Mg Cr Fe Mn

[B.Kapusta, INSTN, Aluminum Behavior Under Irradiation, 2011]

slide-10
SLIDE 10

CHEMICAL ANALYSES (2/2)

| PAGE 10 RRFM - IGORR, Sydney, Australia, December 3-7th 2017

Wavelength (nm) Intensity (A. U.) Quartz window Laser Sample Plasma Focal lens To spectrometer Quartz window Mirror Mirror Fiber

  • ptic

Nuclearized Laser-Induced Breakdown Spectrometer

Courtesy of N. Coulon CEA, DPC/SEARS

  • LIBS technique: measurement of Si

content on centimeter size samples →information on received dose (transmutation Al-Si)

  • Also available ICP-AES technique on

Al shavings from massive components →information on Mg, Fe, Si contents

slide-11
SLIDE 11

CORRELATION SI CONTENT AND MECHANICAL BEHAVIOR (2/2)

| PAGE 11

Generated Si content (from Al transmutation) is directly linked to embrittlement and hardening of the components of MTRs

[B.Kapusta, IGORR, 2005]

slide-12
SLIDE 12

CORRELATION SI CONTENT AND MECHANICAL BEHAVIOR (2/2)

| PAGE 12

[B.Kapusta, IGORR, 2005]

slide-13
SLIDE 13

CONCLUSIONS

| PAGE 13 RRFM - IGORR, Sydney, Australia, December 3-7th 2017

Methods and experimental capacities have been developed over the years at the LECI facility in order to characterize non-fissile materials. These means can be applied to MTRs core components such as pressure vessels, experimental racks, neutron guide tubes for example. Several aspects of the impact of irradiation on aluminum components can be studied: Degradation of mechanical properties (hardening, embrittlement) Microstructure evolution (radiation-induced segregations, precipitation) Enhanced corrosion Swelling Application to Surveillance programs of MTRs Prediction of component lifetime/replacement LECI is open to national and international clients through direct contracts or international scientific collaboration

slide-14
SLIDE 14

Direction de l’Energie Nucléaire Département des Matériaux pour le Nucléaire Service d’Etudes des Matériaux Irradiés Commissariat à l’énergie atomique et aux énergies alternatives Centre de Saclay | 91191 Gif-sur-Yvette Cedex

  • T. +33 (0)1 69 08 46 24 | F. +33 (0)1 69 08 90 73

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

| PAGE 14 RRFM - IGORR, Sydney, Australia, December 3-7th 2017