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Authors

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Disclaimer

qÜÉ=áåÑçêã~íáçå=éêÉëÉåíÉÇ=áå=íÜáë=êÉéçêí=Ü~ë=ÄÉÉå=ÅçãéáäÉÇ=~åÇ=~å~äóëÉÇ=Äó=

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Acronyms and explanations

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Unit conversion

TEMPERATURE DISTANCE °C + 273.15 = K °C*1.8 +32 = °F x (µm) x (mils) 0.6 0.02

T(K) T(°C) T(°F) 1 0.04 273 0 32 5 0.20 289 16 61 10 0.39 298 25 77 20 0.79 373 100 212 25 0.98 473 200 392 25.4 1.00 573 300 572 100 3.94 633 360 680 673 400 752 773 500 932 783 510 950 793 520 968 823 550 1022 PRESSURE 833 560 1040 bar MPa psi 873 600 1112 1 0.1 14 878 605 1121 10 1 142 893 620 1148 70 7 995 923 650 1202 70.4 7.04 1000 973 700 1292 100 10 1421

1023 750 1382 130 13 1847 1053 780 1436 155 15.5 2203 1073 800 1472 704 70.4 10000 1136 863 1585 1000 100 14211 1143 870 1598 1173 900 1652 1273 1000 1832 1343 1070 1958 1478 1204 2200 STRESS INTENSITY FACTOR

MASS MPa√m ksi√inch kg lbs 0.91 1

0.454 1 1 1.10 1 2.20

Radioactivity 1 Sv 1 Ci 1 Bq

= 100 Rem = 3.7 x 1010 Bq = 37 GBq = 1 s-1

=




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Contents Acronyms and explanations III Unit conversion VI 1 Introduction (Peter Rudling) 1-1 2 Secondary side steam generator tube problems (Rolf Riess) 2-1 OKN fåíêçÇìÅíáçå= OJN OKNKN _~ÅâÖêçìåÇ= OJN OKNKO pd=ÇÉëáÖå=ÑÉ~íìêÉë= OJP OKNKP píÉ~ã=ÖÉåÉê~íçê=íìÄáåÖ=ã~íÉêá~äë= OJV OKO qÉãéÉê~íìêÉë=~åÇ=ÅçåÅÉåíê~íáçåë= OJNS OKP PWR=ëÉÅçåÇ~êó=ëáÇÉ=ÅÜÉãáëíêó= OJNT OKPKN mä~åí=ÅçåÅÉéíë= OJNT OKPKO léíáãáò~íáçåë= OJNV OKPKOKN ée=çéíáãáò~íáçå= OJOM OKPKOKO lñóÖÉå=Åçåíêçä= OJON OKPKOKP `çêêçëáçå=éêçÇìÅí=Åçåíêçä= OJOO OKPKOKQ fãéìêáíó=Åçåíêçä= OJOR OKPKOKR `ÜÉãáëíêó=ëìéÉêîáëáåÖ=çÑ=íÜÉ=ÅçåÅÉéí= OJOS OKPKP péÉÅáÑáÅ=Åçåíêçä=ãçÇÉë= OJOU OKPKPKN jçä~ê=ê~íáç=Åçåíêçä=(MRC)= OJOU OKPKPKO eáÇÉçìí=êÉíìêå=éêçÅÉëë= OJOU OKPKPKP eóÇê~òáåÉ=ÅÜÉãáëíêó= OJOU OKPKQ `çêêçëáçå=áåÜáÄáíçêë= OJOU OKPKQKN mÜçëéÜ~íÉ=íêÉ~íãÉåí= OJOU OKPKQKO _çêáÅ=~ÅáÇ=íêÉ~íãÉåí= OJPM OKPKQKP líÜÉê=áåÜáÄáíçêë= OJPN OKPKR píÉ~ã=ÖÉåÉê~íçê=ÅäÉ~åäáåÉëë= OJPN OKPKRKN iÉ~Ç= OJPO OKPKRKO `çééÉê= OJPO OKPKRKP päìÇÖÉ=ä~åÅáåÖ= OJPO OKPKRKQ `ÜÉãáÅ~ä=ÅäÉ~åáåÖ= OJPO OKPKRKR ^ééäáÅ~íáçå=çÑ=ÇáëéÉêë~åíë= OJPP OKPKS pìãã~êó= OJPQ OKQ aÉÖê~Ç~íáçå=çÑ=ëíÉ~ã=ÖÉåÉê~íçê=íìÄáåÖ=EmÉíÉê=cçêÇF= OJPQ OKQKN fåíêçÇìÅíáçå= OJPQ OKQKO mêÉÇáÅíáåÖ=Ç~ã~ÖÉ=áå=káJÄ~ëÉ=ëíÉ~ã=ÖÉåÉê~íçê=íìÄáåÖ=çå=íÜÉ=PWR=

ëÉÅçåÇ~êó=ëóëíÉã= OJPT OKQKP mêÉÇáÅí~Äáäáíó=Ä~ëÉÇ=çå=íÜÉ=ãÉÅÜ~åáëã=çÑ=Åê~ÅâáåÖ= OJQN OKQKQ mêÉÇáÅí~Äáäáíó=Ä~ëÉÇ=çå=ìåÇÉêëí~åÇáåÖ=çÑ=ÉÑÑÉÅí=çÑ=ëóëíÉã=áåíÉêÇÉéÉåÇÉåÅáÉë= OJQQ OKQKR `çåÅäìëáçåë= OJRQ 3 Material degradation management (Peter Ford) 3-1 PKN páíì~íáçå=~í=íÜÉ=ÅçåÅäìëáçå=çÑ=íÜÉ=LCCO=êÉéçêí= PJN PKO réÇ~íÉë=çå=ã~íÉêá~äë=ÇÉÖê~Ç~íáçå=fáëëìÉë= PJP PKOKN qÜÉ=ÉÑÑÉÅí=çÑ=ÅçäÇ=ïçêâ=çå=ëíêÉëë=Åçêêçëáçå=Åê~ÅâáåÖ=çÑ=ëíêìÅíìê~ä=ã~íÉêá~äë=

áå=BWRë=~åÇ=PWRë= PJP PKOKNKN dÉåÉêáÅ=~ëéÉÅíë= PJQ PKOKNKO pÉêîáÅÉ=~åÇ=ä~Äçê~íçêó=ÉñéÉêáÉåÅÉ= PJS PKOKNKP jÉÅÜ~åáëíáÅ=råÇÉêëí~åÇáåÖ= PJNT PKOKNKQ pìãã~êó=~åÇ=ÑìíìêÉ=ïçêâ= PJOO PKOKO qÜÉ=êçäÉ=çÑ=íÜÉ=ÉåîáêçåãÉåí=çå=Ñê~ÅíìêÉ=êÉëáëí~åÅÉ= PJOP PKOKP qÜÉ=ÉÑÑÉÅí=çÑ=ÇáëëçäîÉÇ=ÜóÇêçÖÉå=ÅçåÅÉåíê~íáçå=çå SCC=çÑ=åáÅâÉäJÄ~ëÉ=

~ääçóë=áå=PWR=éêáã~êó=ëóëíÉãëK= PJOV




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PKOKPKN _~ÅâÖêçìåÇ= PJOV PKOKPKO bÑÑÉÅí=çÑ=ÇáëëçäîÉÇ=ÜóÇêçÖÉå=ÅçåíÉåí=çå=PWSCC=áåáíá~íáçå=~åÇ=

éêçé~Ö~íáçå=áå=åáÅâÉäJÄ~ëÉ=~ääçóë= PJPN PKOKPKP jÉÅÜ~åáëíáÅ=Ä~ëáë=Ñçê=ÇÉéÉåÇÉåÅó=çÑ=íÜÉ=Åê~Åâ=éêçé~Ö~íáçå=ê~íÉ=áå=åáÅâÉäJ

Ä~ëÉ=~ääçóë=çå=íÜÉ=ÇáëëçäîÉÇ=ÜóÇêçÖÉå=ÅçåÅÉåíê~íáçå=áå=PWR=éêáã~êó=

ÉåîáêçåãÉåíë= PJPS PKOKPKQ _ÉåÉÑáíëI=îáë=~=îáë=ëíêÉëë=Åçêêçëáçå=Åê~ÅâáåÖ=êÉëáëí~åÅÉI=çÑ=ÉáíÜÉê=áåÅêÉ~ëáåÖ=

çê=ÇÉÅêÉ~ëáåÖ=íÜÉ=ÇáëëçäîÉÇ=ÜóÇêçÖÉå=ÅçåíÉåí= PJPV PKOKPKR pìãã~êó=~åÇ=ÑìíìêÉ=ïçêâ= PJQO 4 Electrochemical membrane methods in LWR cleanup systems

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~=PWR= QJOS QKQ t~íÉê=íêÉ~íãÉåí=ïáíÜ=Äçêçå=ÇçéÉÇ=Çá~ãçåÇ=ÉäÉÅíêçÇÉë= QJPM QKQKN qÜÉçêÉíáÅ~ä=Ä~ÅâÖêçìåÇ= QJPM QKQKO bñéÉêáãÉåíë=áå=íÜÉ=éä~åí=ïáíÜ=~ããçåá~=ÇÉëíêìÅíáçå= QJPN QKQKOKN oÉ~Åíáçåë=~í=íÜÉ=Çá~ãçåÇ=ÉäÉÅíêçÇÉë= QJPO QKQKOKO oÉëìäíë= QJPP QKQKOKP lìíäççâ= QJPR QKR `~íáçå=ÅçåÇìÅíáîáíó=ïáíÜ=ãÉãÄê~åÉ=ÉäÉÅíêçäóëáë= QJPR QKRKN oÉëìäíë= QJPU QKRKO lìíäççâ= QJPV QKS pìãã~êó=~åÇ=çìíäççâ=~Äçìí=ìëÉ=çÑ=ãÉãÄê~åÉ=íÉÅÜåçäçÖáÉë=áå=NPPë= QJPV




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5 Effect of water chemistry on fuel cladding 5-1 RKN PWR=ï~íÉê=ÅÜÉãáëíêó=EoçäÑ=oáÉëëF= RJN RKNKN fåíêçÇìÅíáçå= RJN RKNKNKN `çåÅÉêåë=êÉÖ~êÇáåÖ=ÑìÉä=ÉäÉãÉåíë= RJN RKNKNKO eáÖÜÉê=ée=éêáã~êó=ï~íÉê=ÅÜÉãáëíêóX=äáíÜáìãL_Jëíê~íÉÖó= RJO RKNKNKP PWR=òáåÅ=áåàÉÅíáçå= RJP RKNKNKQ PWR=ÑìÉä=CRUD=~åÇ=AOA=Eçê=CIPSF= RJQ RKNKO kÉï=êÉëìäíë=áå=OMMSLOMMT= RJR RKNKOKN `ìêêÉåí=ÅçåÅÉêåë=êÉÖ~êÇáåÖ=ÑìÉä=ÉäÉãÉåíë= RJR RKNKOKO ^Çî~åÅÉë=áå=ÜáÖÜ=ée=éêáã~êó=ï~íÉê=ÅÜÉãáëíêó= RJS RKNKOKP ^å=ìéÇ~íÉ=çå=PWR=òáåÅ=áåàÉÅíáçå= RJNM RKNKOKQ ^Åíì~ä=PWR=ÑìÉä=CRUD=Ç~í~=~åÇ=AOA= RJNQ RKNKOKR eóÇêçÖÉå=Åçåíêçä=áå=PWR=éêáã~êó=Åççä~åí= RJNT RKNKP hÉó=êÉëìäíë=áå=OMMSLOMMT=Ñçê=PWRë= RJPQ RKNKQ `çåÅäìëáçåë=~åÇ=êÉÅçããÉåÇ~íáçåë= RJPQ RKO BWR=ï~íÉê=ÅÜÉãáëíêó=EoçäÑ=oáÉëëF= RJPR RKOKN fåíêçÇìÅíáçå= RJPR RKOKNKN eóÇêçÖÉå=ï~íÉê=ÅÜÉãáëíêó=~åÇ=åçÄäÉ=ãÉí~ä=ÅÜÉãáëíêó=E^äÑêÉÇ=píê~ëëÉêF= RJPS RKOKNKO wáåÅ=áåàÉÅíáçå=EoçäÑ=oáÉëëF= RJPT RKOKO kÉï=êÉëìäíë= RJPT RKOKOKN kçêã~ä=ï~íÉê=ÅÜÉãáëíêó=ENWCF= RJPT RKOKOKO eóÇêçÖÉå=ï~íÉê=ÅÜÉãáëíêó=~åÇ=~äíÉêå~íáîÉë= RJQM RKOKOKP wáåÅJáåàÉÅíáçå=ìéÇ~íÉ=Ñçê=BWRë= RJQQ RKOKP hÉó=êÉëìäíë=áå=OMMSLOMMT=Ñçê=BWRë= RJQQ 6 References 6-1

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1 Introduction (Peter Rudling)

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2 Secondary side steam generator tube problems (Rolf Riess)

2.1 Introduction

2.1.1 Background

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çíÜÉê=ã~åìÑ~ÅíìêÉêë=äáâÉ=páÉãÉåëI=_~ÄÅçÅâ=C=táäÅçñ=EB&WF=~åÇ=`çãÄìëíáçå=båÖáåÉÉêáåÖ=ECEF=~êÉ=ëáãáä~ê=áå=ëçãÉ=ï~óë=~åÇ=ÇáÑÑÉêÉåí=áå=çíÜÉêëK=qÜÉ=páÉãÉåë=ÇÉëáÖå=Ñçê=Éñ~ãéäÉI=ëÜçïå=áå=

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ëìééçêí=ÇÉëáÖåë=~åÇ=~ääçóë=Ñêçã=íÜÉ=ÄÉÖáååáåÖK=qÜÉëÉ=ÇáÑÑÉêÉåÅÉë=ïáää=ÄÉ=ÇÉëÅêáÄÉÇ=ä~íÉêK=eçïÉîÉêI=

áí=áë=áãéçêí~åí=íç=êÉÅçÖåáëÉ=íÜ~í=íÜÉ=éêÉëÉåí=ÇÉëáÖåë=çÑ=ëíÉ~ã=ÖÉåÉê~íçêë=~êÉ=îìäåÉê~ÄäÉ=íç=

Åçêêçëáçå=Ç~ã~ÖÉK=cçê=Éñ~ãéäÉ=^ääçó=SVM=Å~å=ëìëí~áå=ÉñíÉåëáîÉ=Åçêêçëáçå=ìåÇÉê=ÅÉêí~áå=

ÅçåÇáíáçåëK=kÉîÉêíÜÉäÉëëI=áí=Å~å=ÄÉ=~ëëìãÉÇI=íÜ~í=Ä~ëÉÇ=çå=ä~Äçê~íçêó=ÉñéÉêáãÉåíë=~åÇ=íÜÉ=ÉñáëíáåÖ=

ÑáÉäÇ=ÉñéÉêáÉåÅÉI=^ääçóë=SVM=ã~ó=åçí=ìåÇÉêÖç=íÜÉ=ë~ãÉ=ÉñéÉêáÉåÅÉ=äáâÉ=^ääçó=SMMK==

qÜÉ=êÉäá~Äáäáíó=çÑ=ëíÉ~ã=ÖÉåÉê~íçêë=~ë=áí=ÇÉéÉåÇë=çå=íÜÉ=PWR=ëÉÅçåÇ~êó=ëáÇÉ=áë=áåÑäìÉåÅÉÇ=ã~áåäó=Äó=íÜÉ=ÅÜ~ê~ÅíÉêáëíáÅë=çÑ=“ÜÉ~í=íê~åëÑÉê=ÅêÉîáÅÉëÒI=áå=ïÜáÅÜ=ÇáäìíÉ=ëéÉÅáÉë=Ñêçã=íÜÉ=

ëÉÅçåÇ~êó=ÉåîáêçåãÉåí=Å~å=ÄÉ=ÅçåÅÉåíê~íÉÇ=íç=éêçÇìÅÉ=ÜáÖÜäó=ÅçêêçëáîÉ=ÉåîáêçåãÉåíë=çéÉê~íáåÖ=

ÅäçëÉ=íç=íÜÉ=Üçí=äÉÖ=íÉãéÉê~íìêÉK==




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Figure 2-1(a): Schematic view of (a) RSG (Westinghouse Model D3) and (b) OTSG showing typical features. The RSG design is typical of that of Westinghouse, its licensees, CE, and Siemens. The OTSG design is typical of the B&W SGs, Staehle & Gorman, 2002.

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ÖÉåÉê~íçêë=çÑ=çíÜÉê=ã~åìÑ~ÅíìêÉêëK=qÜáë=áåÑçêã~íáçå=áë=ÇÉëÅêáÄÉÇ=áå=ëÉîÉê~ä=ÇçÅìãÉåíë=êÉäÉ~ëÉÇ=Äó=

páÉãÉåëI=ÉKÖK=pÅÜΩÅâí~åò=Éí=~äKI=NVTRX=oáÉëëI=NVTSX=oáÉëë=Éí=~äKI=NVTTX=pÅÜΩÅâí~åò=Éí=~äKI=NVUMX=

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~êÉ=ÑÉï=áå=Åçãé~êáëçå=íç=íÜçëÉ=ÖÉåÉê~íÉÇ=ã~áåäó=áå=íÜÉ=råáíÉÇ=pí~íÉëI~åÇ=êÉéçêíÉÇ=áå=éêçÅÉÉÇáåÖë=

çÑ=ÅçåÑÉêÉåÅÉë=ëìÅÜ=~ë=íÜÉ=fåíÉêå~íáçå~ä=póãéçëá~=çå=båîáêçåãÉåí~ä=aÉÖê~Ç~íáçå=çÑ=j~íÉêá~äë=áå=

kìÅäÉ~ê=mçïÉê=póëíÉãë=Ó=t~íÉê=oÉ~Åíçêë=çê=íÜÉ=cçåíÉîê~ìÇ=`çåÑÉêÉåÅÉëK=j~åó=bäÉÅíêáÅ=mçïÉê=

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Ü~ë=ëéçåëçêÉÇ=íÜÉ=ÇÉîÉäçéãÉåí=~åÇ=~ééäáÅ~íáçå=çÑ=íÜÉ=jriqbnJÅçÇÉ=Ñçê=èì~åíáÑóáåÖ=íÜÉ=

éêçÄäÉãë=áå=~èìÉçìë=íÜÉêãçÇóå~ãáÅë=áãéçêí~åí=Ñçê=íÜÉ=êÉëçäìíáçå=çÑ=áëëìÉë=áå=PWR=ëÉÅçåÇ~êó=ëáÇÉ=ÅçãéçåÉåíëK=^=ÅçãéêÉÜÉåëáîÉ=äáëí=çÑ=oÉÑÉêÉåÅÉë=áë=ÖáîÉå=Äó=pí~ÉÜäÉ=C=dçêã~åI=OMMOI=~åÇ=áå=

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Figure 2-1(c): Siemens designed Steam Generator with Economizer showing typical regions of corrosion attack.

2.1.2 SG design features

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cáÖìêÉ=OJO=ëÜçïë=íÜÉ=íÜêÉÉ=íóéÉë=íÜ~í=~êÉ=äçÅ~íÉÇ=~í=íÜÉ=ëíÉ~ã=ÖÉåÉê~íçê=íìÄÉ=ëÜÉÉíI=áå=íÜÉ=ëäìÇÖÉ=

éáäÉI=~åÇ=~í=íÜÉ=íìÄÉ=ëìééçêí=éä~íÉK=oÉÖ~êÇáåÖ=íÜÉ=íìÄÉ=ëìééçêí=ÅêÉîáÅÉ=íÜÉêÉ=~êÉ=íÜêÉÉ=íóéÉëW=

aêáääÉÇ=ÜçäÉI=Äêç~ÅÜÉÇ=ÜçäÉI=~åÇ=ÉÖÖ=Åê~íÉI=~ë=áääìëíê~íÉÇ=áå=cáÖìêÉ=OJPK=qÜÉ=íìÄÉ=ëÜÉÉí=ÅêÉîáÅÉë=

áíëÉäÑ=Å~å=Ü~îÉ=íÜêÉÉ=ÇÉëáÖåë=~ë=ëÜçïå=áå=cáÖìêÉ=OJQK=låÉ=çÑ=íÜÉ=É~êäó=ÇÉëáÖåë=ï~ë=~=é~êíJÇÉéíÜ=

êçääK=qÜáë=ï~ë=êÉéä~ÅÉÇ=Äó=Ñìää=ÇÉéíÜ=êçää=çê=ÉñéäçëáîÉ=çê=ÜóÇê~ìäáÅ=Éñé~åëáçå=áå=çêÇÉê=íç=~îçáÇ=

éçëëáÄäÉ=Åçêêçëáçå=áå=~=äçåÖ=ÜÉ~í=íê~åëÑÉê=ÅêÉîáÅÉK=^äíÜçìÖÜ=~=Ñìää=ÇÉéíÜ=Éñé~åëáçå=áë=åçï=

ëí~åÇ~êÇI=íÜÉêÉ=áë=~äï~óë=íÜÉ=P=íç=S=ãã=ÅêÉîáÅÉ=åÉ~ê=íÜÉ=íçé=çÑ=íÜÉ=íìÄÉ=ëÜÉÉí=áå=çêÇÉê=íç=~îçáÇ=

“çîÉêJÉñé~åëáçåÒK=få=cáÖìêÉ=OJR=íÜÉ=Éîçäìíáçå=çÑ=íÜÉ=íóéÉë=çÑ=íìÄÉ=ëìééçêí=ÇÉëáÖå=çÑ=íÜÉ=Ñçìê=

ã~åìÑ~ÅíìêÉêë=çÑ=ëíÉ~ã=ÖÉåÉê~íçêë=~êÉ=ëÜçïåK==




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Figure 2-2: Geometries that produce heat transfer crevices involving tubing in steam generators: (a) top of the tube sheet; (b) sludge; (c) tube support, Staehle & Gorman, 2002.

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Figure 2-3: Geometries of tube supports: (a) Drilled hole typical of early Westinghouse designs; (b) egg crate typical of Siemens and CE; (c) broached trefoil typical of Babcock and Wilcox; (d) broached quatrefoil typical of later Westinghouse designs, Staehle & Gorman, 2002.




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Figure 2-4: Tube sheet geometries. (a) Partially expanded. (b) Fully expanded. (c) Fully expanded with top “Kiss” roll, Staehle & Gorman, 2002.

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Figure 2-5: Evolution of tube support geometries and materials used by four Nuclear Steam Supply System (NSSS) vendors for steam generators. The geometries of tube supports are shown above the lines, and the materials of the tube supports are shown below. The arrows indicate approximately when manufacturing of the respective designs of tube supports started, Staehle & Gorman, 2002.

eÉ~í=íê~åëÑÉê=ÅêÉîáÅÉë=~êÉ=áãéçêí~åí=Ñçê=íÜÉ=Ñ~Åí=íÜ~í=íÜÉó=ÅçåÅÉåíê~íÉ=áãéìêáíáÉë=íç=ÜáÖÜ=ê~íáçë=çÑ=

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Figure 2-6: Three crevice geometries for producing corrosion: (a) Heat transfer crevice typical of those at tube supports, sludge piles, and top of tube sheet. (b) Heated surface where concentration occurs. (c) Non heat transfer crevice, Staehle & Gorman, 2002.

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• lïáåÖ=íç=íÜÉ=é~ÅâáåÖ=çÑ=íÜÉ=ÅêÉîáÅÉI=íÜÉ=êÉÖáçå=ïáíÜáå=íÜÉ=ÅêÉîáÅÉ=íÉåÇë=íç=ÄÉ=ëíÉ~ã=ïáíÜ=

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Figure 2-7: Schematic view of heat transfer crevice at a tube support. (a) Geometry. (b) Chemicals that accumulate and transform. (c) Types of gradients inside the heat transfer crevice, Staehle & Gorman, 2002.

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~ÖÖêÉëëáîÉ=ÉåîáêçåãÉåí=áå=ÜÉ~í=íê~åëÑÉê=ÅêÉîáÅÉë=áë=ÇÉÑáåáíÉäó=ÜáÖÜÉê=áå=ÇêáääÉÇ=ëìééçêí=ëíêìÅíìêÉë=

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bñ~ãéäÉë=Ñçê=äáåÉ=Åçåí~Åí=ÖÉçãÉíêáÉë=~êÉ=ëÜçïå=áå=cáÖìêÉ=OJU=~åÇ=cáÖìêÉ=OJVK=




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Figure 2-8: Schematic view of accumulation of deposits at line contact crevices associated with (a) broached holes and (b) egg crates. Example (c) of different temperatures (d) at open area and at deposit filled contact area, Staehle & Gorman, 2002.

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Figure 2-9: Design Features to avoid Tube Denting, Intergranular Attack (IGA), Intergranular Stress Corrosion Cracking (IGSCC) and Fretting, Riess & Odar, 1991.




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2.1.3 Steam generator tubing materials

oÉÖ~êÇáåÖ=íÜÉ=ëíÉ~ã=ÖÉåÉê~íçê=íìÄÉ=ÇÉÖê~Ç~íáçå=éêçÄäÉãëI=íÜÉ=ÑçääçïáåÖ=ÅÜêçåçäçÖó=Å~å=ÄÉ=ÖáîÉåK=

^ìëíÉåáíáÅ=ëí~áåäÉëë=ëíÉÉä=ï~ë=ìëÉÇ=áåáíá~ääó=Ñçê=íìÄáåÖ=áå=ëÉîÉê~ä=É~êäó=PWRë=ÄìíI=~ë=~=êÉëìäí=çÑ=Åçêêçëáçå=éêçÄäÉãë=ïáíÜ=íÜáë=ã~íÉêá~ä=EëìÅÜ=~ë=Å~ìëíáÅ=~åÇ=ÅÜäçêáÇÉ=áåÇìÅÉÇ=ëíêÉëë=Åçêêçëáçå=

Åê~ÅâáåÖF=^ääçó=SMM=ï~ë=ÅÜçëÉåK=qÜáë=ï~ë=~äëç=ëíáãìä~íÉÇ=Äó=~=ÇÉÅáëáçå=çÑ=íÜÉ=k~î~ä=oÉ~Åíçêë=áå=

íÜÉ=rp=íç=ìëÉ=^ääçó=SMM=áå=íÜÉ=MA=Ñçêã=áåëíÉ~Ç=çÑ=~ìëíÉåáíáÅ=ëí~áåäÉëë=ëíÉÉäK==

q~ÄäÉ=OJNI=éêÉé~êÉÇ=Äó=pí~ÉÜäÉ=C=dçêã~åI=OMMOI=ëìãã~êáòÉë=íÜáë=ÇÉîÉäçéãÉåí=~åÇ=êÉÑäÉÅíë=

~äëç=íÜÉ=ÅÜêçåçäçÖó=ïÜáÅÜ=äÉÇ=íç=íÜÉ=ÇÉîÉäçéãÉåí=çÑ=^ääçó=UMM=~åÇ=^ääçó=SVM=TT=EqÜÉêã~ääó=

qêÉ~íÉÇFK=qÜÉ=ë~ãÉ==áåÇáÅ~íÉë=íÜ~í=íÜÉ=dÉêã~å=lêáÖáå~ä=bèìáéãÉåí=j~åìÑ~ÅíìêÉê=EOEMF=ÇÉÅáÇÉÇ=

~äêÉ~Çó=áå=íÜÉ=NVSMë=íç=ëïáíÅÜ=íç=~=ãçÇáÑáÉÇ=^ääçó=UMM=NGI=ÑçääçïÉÇ=Äó=áíë=Ñáêëí=~ééäáÅ~íáçå=áå=

NVTOK=qÜÉ=Ä~ëáë=Ñçê=íÜáë=ÇÉÅáëáçå=ï~ë=çå=çåÉ=Ü~åÇ=íÜÉ=SCC=ÑáåÇáåÖë=çÑ=`çêáçì=ïáíÜ=^ääçó=SMM=~åÇ=íÜÉ=É~êäó=ÉñéÉêáÉåÅÉ=áå=ä~êÖÉ=PWRë=ïÜÉêÉ=åìãÉêçìë=Åçêêçëáçå=éêçÄäÉãë=çÅÅìêêÉÇK=qÜÉ=ãçëí=

áãéçêí~åí=Çá~Öê~ã=çÑ=íÜçëÉ=Ç~óë=áë=ëÜçïå=áå=cáÖìêÉ=OJNMK=qÜÉ=OEMë=áå=cê~åÅÉ=~åÇ=g~é~å=ïÉêÉ=

iáÅÉåëÉÉë=çÑ=tÉëíáåÖÜçìëÉ=~åÇ=íÜÉó=ëíêáÅíäó=ÑçääçïÉÇ=íÜÉ=rp=ÇÉÅáëáçå=êÉÖ~êÇáåÖ=íÜÉ SGJqìÄáåÖ=

pÉäÉÅíáçåK==

=

Figure 2-10: Stress Corrosion Cracking of austenitic alloys in 660 °F (350 °C) Water with 1000 ppm Chloride, (Debray & Stieding, 1972.) as a function of the alloys nickel content.


Copyright © Advanced Nuclear Technology International Europe AB, ANT International, 2007. This information is the property of Advanced Nuclear Technology International Europe AB or is licensed for use by Advanced Nuclear Technology International Europe AB by its customers or partners. The information may not be given to, shared with, or cited to third party, used for unauthorised purpose, or be copied or reproduced in any form

without the written permission of Advanced Nuclear Technology International Europe AB.

OJNMEOJRQF

Table 2-1: PWR Steam Generator Design Evolution

Mode/lead plant (first commercial

operation)

Typical design TH

(°C)

Hot leg heat flux Btu/hr/ft2

Recirculating or

once through

Tube orientation

Tube material*

Support type

Support material

Tube sheet expansion**

Flow distribution baffle (Y/N)

Preheater (Y/N)

Government laboratory designs

Shippingport (1957) 283 29.000 Recirculating Horizontal SS then 600 MA Hour-glass drilled holes

Carbon steel PDR Not applicable N

N reactor (1965) 279 67.000 Recirculating Horizontal SS then 600 MA Drilled holes Carbon steel PDR Not applicable N

Westinghouse and licensees designs

Early SS designs (1961) 288-302 39.000 Recirculating Vertical 304 SS Drilled holes Carbon steel PDR N N

Early 600 MA designs (1968)

310-318 43.000 Recirculating Vertical 600 MA Drilled holes Carbon steel PDR N N

Intermediate 600 MA designs (1977)

317-322 44.000 Recirculating Vertical 600 MA Drilled holes Carbon steel FDE, FDR or FDR-KR

N N

Later 600 MA designs (1981)

323-324 48.000 Recirculating Vertical 600 MA Drilled holes Carbon steel FDE, FDR or FDR-KR1

Y N

Preheater 600 MA designs (1983)

326-330 49.000 Recirculating Vertical 600 MA Drilled holes Carbon steel FDE, FDR or FDR-KR

Y Y

Model F type (1983) 326 53.000 Recirculating Vertical 600 TT Broached holes 405 SS FDH or FDR-KR1 Y N

Preheater 600 TT designs (1986)

326 49.000 Recirculating Vertical 600 TT Broached holes 405 SS FDH or FDR-KR Y N

Latest replacement designs (1988)

See note 44.000 Recirculating Vertical 690 TT Broached holes 405 SS FDH or FDR-KR1 Y Y




OJNNEOJRQF

Table 2-1: PWR Steam Generator Design Evolution, cont’d


operation)

Typical design TH

(°C)


Recirculating or

once through

Tube orientation

Tube material*

Support type

Support material



Preheater (Y/N)

CE and licensee designs

First design (1971) 315 50.000 Recirculating Vertical 600 MA Drilled holes Carbon steel FDE N N

Intermediat designs (1973)

313 51.000 Recirculating Vertical 600 MA Eggcrates & drilled holes

Carbon steel FDE N N

Later designs (1983) 321 56.000 Recirculating Vertical 600 MA Eggcrates Carbon steel FDE N N

Ekonomizer model (1986)

327 52.000 Recirculating Vertical 600 MA Eggcrates 409 SS FDE Y Y

Latest Korean model 322 47.000 Recirculating Vertical 690 TT Eggcrates 409 SS FDE Y Y

B&W designs

Prototype plant design (1963)

271 - Recirculating Horizontal 304 SS - - - Not applicable N

One-through design (1973 and later)

317-320 33.000 Once-through Vertical 600 MA + sensitized

Broached holes Carbon steel PDR N N

Replacement RSGs (1992 and later)

See note2 50.000 Recirculating Vertical 690 TT Lattice bar 410 SS FDH Y N




OJNOEOJRQF

Table 2-1: PWR Steam Generator Design Evolution, cont’d


operation)

Typical design TH

(°C)


Recirculating or

once through

Tube orientation

Tube material*

Support type

Support material



Preheater (Y/N)

Siemens

Lead plant design (1969) 312 61.000 Recirculating Vertical 600 MA Lattice bar SS Rolled at top, mid and bottom

N N

Second generation design (1972)

314-319 68.000 Recirculating Vertical 800 NG Lattice bar SS Rolled at top and bottom

N N

Preheater design (~1983)

329 57.000 Recirculating Vertical 800 NG Lattice bar SS Rolled at top and bottom

Y Y

Replacement design (1989)

See note1 51.000 Recirculating Vertical 800 NG or 690 TT

Lattice bar SS FDH with roll at top and bottom

- N

* MA = Mill annealed, TT = Thermal treated, NG = Nuclear grade ** PDR = Part depth roll, FDR = Full depth roll, KR = Kiss roll, FDE = Full depth explosive, FDH = full depth hydraulic

Notes: 1 Variety of full depth tube sheet expansion designs used in Japan 2 TH of replacement SGs is usually lower than that of original SGs




OJNPEOJRQF

qÜÉ=ÇÉîÉäçéãÉåí=çÑ=^ääçó=SVM=TT=ëí~êíÉÇ=áå=íÜÉ=ãáÇ=TMë=~ÑíÉê=íÜÉ=çÅÅìêêÉåÅÉ=çÑ=ëÉîÉê~ä=ëÉîÉêÉ=

éêçÄäÉãë=ïáíÜ=^ääçó=SMM=MAI=ëìÅÜ=~ëW=

• IGALSCC=áå=íÜÉ=ëäìÇÖÉ=éáäÉ=êÉÖáçå=• mÜçëéÜ~íÉ=ï~ëí~ÖÉ=

• SCC=áå=ÇÉÉé=íìÄÉ=ëÜÉÉí=ÅêÉîáÅÉë=• aÉåíáåÖ=

qÜÉ=Ñáêëí=ãçÇáÑáÅ~íáçå=íç=^ääçó=SMM=ï~ë=~=ÜÉ~í=íêÉ~íãÉåí=~í=TMQ=ø`=Ñçê=~Äçìí=NR=Üçìêë=äÉ~ÇáåÖ=íç=

^ääçó=SMM=TTK=eçïÉîÉêI=íÜÉ=áãéêçîÉãÉåíë=ïÉêÉ=åçí=ä~êÖÉ=ÉåçìÖÜ=~åÇ=SCC=êÉã~áåÉÇ=~=ã~íÉêá~ä=

áëëìÉK=^ë=~=ÅçåëÉèìÉåÅÉI=~=åÉï=ã~íÉêá~ä=ï~ë=ÇÉîÉäçéÉÇ=Äó=fåíÉêå~íáçå~ä=káÅâÉäI=áKÉK=^ääçó=SVM=TTK=qÜáë=ã~íÉêá~ä=ï~ë=èì~äáÑáÉÇ=áå=íÜÉ=ä~Ä=~åÇ=íÜÉå=ìëÉÇ=Ñêçã=íÜÉ=ãáÇ=UMë=çåï~êÇë=~åÇ=áí=áë=åçï~Ç~óë=

íÜÉ=Ñ~îçìêáíÉ=ã~íÉêá~ä=Ñçê=~ää=åÉï=tÉëíáåÖÜçìëÉ=éä~åíë=~åÇ=íÜÉ=éä~åíë=çÑ=éêÉîáçìë=tÉëíáåÖÜçìëÉ=

iáÅÉåëÉÉë=EpáÉãÉåë=~åÇ=jáíëìÄáëÜá=eÉ~îó=fåÇìëíêáÉë=EMHIFFK=qÜÉ=ÉñÅÉéíáçå=ïáíÜ=êÉëéÉÅí=íç=íÜáë=Å~ëÉ=áë=páÉãÉåë=~ë=~=ÑçêãÉê=tÉëíáåÖÜçìëÉ=iáÅÉåëÉÉ=Eåçï=ôbs^FK=

qÜÉ=ëí~íìë=êÉÖ~êÇáåÖ=íÜÉ=ìëÉ=çÑ=^ääçó=SVM=TT=Ü~ë=ÄÉÉå=ÇÉëÅêáÄÉÇ=Äó=kçêÇã~ååI=OMMQ=~åÇ=áí=áë=

ëÜçïå=áå=q~ÄäÉ=OJOK=

Table 2-2: Ratio of Units with 690 TT/ 600 MA, Nordmann, 2004.

Units with USA France Japan Belgium Sweden, United Kingdom

China, Korea

690 TT (a) 21 18 15 7 5

600 MA (b) 34 13 0 3 4

R = a/b 0.62 1.4 - 2.3 1.2

qÜÉ=åìãÄÉê=çÑ=ìåáíë=ïáíÜ=SVM=TT=áë=~äêÉ~Çó=ÖêÉ~íÉê=íÜ~å=ïáíÜ=SMM=MAK=^ÅÅçêÇáåÖ=íç=kçêÇã~åå=

íÜÉêÉ=ëÜçìäÇ=ÄÉ=~äãçëí=åç=ëíÉ~ã=ÖÉåÉê~íçê=áå=NM=óÉ~êë=ïáíÜ=SMM=MA=qÜÉ=ëí~íìë=êÉÖ~êÇáåÖ=íÜÉ=ìëÉ=çÑ=^ääçó=UMM=NG=áë=íÜ~í=~ää=dÉêã~å=PWRë=~åÇ=ëçãÉ=PWRë=áå=

çíÜÉê=bìêçéÉ~å=ÅçìåíêáÉë=~åÇ=`~å~Ç~=~êÉ=ìëáåÖ=íÜáë=ã~íÉêá~ä==

^ë=Å~å=ÄÉ=ëÉÉå=Ñêçã=íÜÉ=q~ÄäÉ=OJNI=íÜÉ=ëìÅÅÉëëÑìä=çéÉê~íáåÖ=ÉñéÉêáÉåÅÉ=ïáíÜ=ÄçíÜ=ÅìêêÉåíäó=

ìëÉÇ=ã~íÉêá~äë=áëW=

• PP=óÉ~êë=ïáíÜ=^ääçó=UMM=

• NR=óÉ~êë=ïáíÜ=^ääçó=SVMK=

`çåëáÇÉêáåÖ=íÜ~í=ÄçíÜ=ã~íÉêá~äë=~êÉ=ëìëÅÉéíáÄäÉ=íç=Åçêêçëáçå=ìåÇÉê=ëçãÉ=ÉåîáêçåãÉåí~ä=

ÅçåÇáíáçåëI=íÜÉ=éçëáíáîÉ=éä~åí=çéÉê~íáåÖ=ÉñéÉêáÉåÅÉ=ëÜçìäÇ=ÄÉ=çÑ=ÖêÉ~í=î~äìÉ=Ñçê=íÜÉ=ëÉäÉÅíáçå=çÑ=çåÉ=

çÑ=íÜÉëÉ=ã~íÉêá~äëK=

_çíÜ=ã~íÉêá~äë=Å~å=ÄÉ=ÅÜ~ê~ÅíÉêáòÉÇ=çå=íÜÉ=cÉJ`êJká=íÉêå~êó=Çá~Öê~ã=çÑ=mìÖÜ=C=káëÄÉíI=NVRMI=

Ñçê=QMM=ø`K=få=~ÇÇáíáçåI=íÜÉ=Åçãéçëáíáçå=çÑ=çíÜÉê=ã~íÉêá~äëI=ïÜáÅÜ=~êÉ=áãéçêí~åí=Ñçê=ëíÉ~ã=

ÖÉåÉê~íçê=éÉêÑçêã~åÅÉ=äáâÉ=ëìééçêí=ëíêìÅíìêÉ=ã~íÉêá~äë=çå=íÜÉ SGJëÉÅçåÇ~êó=ëáÇÉ=çê=oÉ~Åíçê=

`ççä~åí=póëíÉã=ERCSF=ã~íÉêá~äëI=Å~å=~äëç=ÄÉ=í~âÉå=Ñêçã=íÜáë=îáÉïÖê~éÜ=EëÉÉ=cáÖìêÉ=OJNNFK=




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=

Figure 2-11: Fe-Cr-Ni-diagram for 400°C, Pugh & Nisbet, 1950.

qÜÉ=ÇÉí~áäÉÇ=ÅÜÉãáÅ~ä=Åçãéçëáíáçå=çÑ=^ääçó=SVM=TT=~åÇ=^ääçó=UMM=NG=Å~å=ÄÉ=í~âÉå=Ñêçã=

píÉääï~Ö=Éí=~äKI=NVUSI=~ë=áí=áë=ëÜçïå=áå=q~ÄäÉ=OJPK=

Table 2-3: Chemical Composition of the Alloys 690 TT, 800 NG and 600, Stellwag et al., 1986.

Element Alloy 690TT Alloy 800 NG Alloy 600

C 0.01-0.04 0.03 0.01-0.05

Mn 0.50 0.4-1.0 1.00

P 0.025 0.020 0.025

S 0.015 0.015 0.015

Si 0.50 0.3-0.7 0.50

Cr 28-31 20-23 14-17

Ni Bal.(>58) 32-35 Bal.(>72)

Mo - - -

Fe 7-11 Bal. 6-10

Cu 0.50 0.75 0.50

Co 0.10 0.10 0.10

Al 0.50 0.15-0.45 0.50

Ti 0.50 0.60 0.50

Other - Ti/C ≥12 ; Ti/(C+N)≥8 N≥0.03 - =




OJNREOJRQF

`çãáåÖ=Ä~Åâ=íç=íÜÉ=ÅÜêçåçäçÖó=çÑ=píÉ~ã=dÉåÉê~íçê=qìÄÉ=aÉÖê~Ç~íáçå=~åÇ=íÜÉ=NVUMë=~ë=gçåÉëI=

OMMQI=ëìãã~êáòÉÇI=ëÉîÉê~ä=ëäçïÉê=ÇÉîÉäçéáåÖ=ÇÉÖê~Ç~íáçå=Ñçêãë=ÉãÉêÖÉÇI=ëìÅÜ=~ëW=

• máííáåÖ=

• sáÄê~íáçå=áåÇìÅÉÇ=ÑêÉííáåÖ=~åÇ=Ñ~íáÖìÉ=

• mêáã~êó=ëáÇÉ=ëíêÉëë=Åçêêçëáçå=Åê~ÅâáåÖ=~åÇ=ëÉÅçåÇ~êó=ëáÇÉ=SCC=~åÇ=IGA=

qÜÉ=ä~ëí=çÑ=íÜÉëÉ=áíÉãë=Ü~ë=Ü~Ç=íÜÉ=ÖêÉ~íÉëí=áãé~Åí=çå=íÜÉ=ê~íÉ=çÑ=íìÄÉ=éäìÖÖáåÖI=~åÇ=íÜÉ=áå~Äáäáíó=

íç=Åçåíêçä=íÜÉëÉ=Ñçêãë=çÑ=Ç~ã~ÖÉ=Ü~ë=êÉëìäíÉÇ=áå=ã~àçê=êÉéä~ÅÉãÉåí=~ÅíáîáíáÉëK=

^=ïçêäÇïáÇÉ=çîÉêîáÉï=çå=íÜÉ SG=éêçÄäÉãë=áë=ëÜçïå=áå=cáÖìêÉ=OJNOK=

=

Figure 2-12: Worldwide Causes of Steam Generator Tube Repair, Jones, 2004.

cêçã=íÜÉ=Åçêêçëáçå=áëëìÉë=ÉëéÉÅá~ääó=áå=íÜÉ=rp=ëçãÉ=ÅçåÅäìëáçåë=ïÉêÉ=Çê~ïå=Äó=gçåÉëI=OMMQW=

• SCC=éêçîÉÇ=íç=ÄÉ=íÜÉ=ãçëí=ÇáÑÑáÅìäí=áëëìÉ=íç=ÄÉ=ã~å~ÖÉÇ=ÅçëíJÉÑÑÉÅíáîÉäó=

• qÜÉ=ã~å~ÖÉãÉåí=~ééêç~ÅÜ=íç=SCC=áë=íç=áåëéÉÅíI=~ëëÉëë=êÉã~áåáåÖ=äáÑÉI=~åÇ=êÉé~áêLêÉéä~ÅÉK=

eçïÉîÉêI=SCC=áë=Ü~êÇ=íç=ÇÉíÉÅí=~åÇ=íÜÉ=`ê~Åâ=dêçïíÜ=o~íÉ=ECGRF=Å~å=ÄÉ=ê~éáÇK=qÜÉêÉÑçêÉI=ãáíáÖ~íáçå=ãÉíÜçÇë=~êÉ=ÇÉëáê~ÄäÉK=

• få=~=SCC=ãáíáÖ~íáçå=ÅçåíÉñí=íÜÉ=çéíáçåë=~êÉ=äáãáíÉÇ=íç=ëíêÉëë=êÉÇìÅíáçå=~åÇLçê=ï~íÉê=

ÅÜÉãáëíêó=áãéêçîÉãÉåíëK=eçïÉîÉêI=ïáíÜ=êÉëéÉÅí=íç=êÉé~áêLêÉéä~ÅÉãÉåí=åÉï=ãçêÉ=êÉëáëí~åí=

ã~íÉêá~äë=~êÉ=ÇÉëáê~ÄäÉK=

• t~íÉê=ÅÜÉãáëíêó=ãáíáÖ~íáçå=ãÉíÜçÇë=êÉèìáêÉ=ÉñíÉåëáîÉ=íÉëíáåÖ=~åÇ=èì~äáÑóáåÖ=~åÇ=ã~ó=

ÄÉÅçãÉ=îÉêó=ÉñéÉåëáîÉK=




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2.2 Temperatures and concentrations

pçãÉ=Åçêêçëáçå=éÜÉåçãÉå~=çÅÅìêêáåÖ=çå=íÜÉ=ëÉÅçåÇ~êó=ëáÇÉ=~í=íìÄÉ=ëìééçêí=ÉäÉî~íáçåë=~êÉ=

áåÅêÉ~ëáåÖ=ïáíÜ=íÉãéÉê~íìêÉë=çå=íÜÉ=ëìêÑ~ÅÉ=çÑ=íÜÉ=íìÄÉ=~åÇ=íÜÉ=ÅçåÅÉåíê~íáçå=çÑ=áãéìêáíáÉë=áå=íÜÉ=

ÅêÉîáÅÉëK=qÜáë=áë=îÉêáÑáÉÇ=ïáíÜ=íÜÉ=ÇÉÅêÉ~ëáåÖ=çÅÅìêêÉåÅÉ=çÑ=ÉÇÇó=ÅìêêÉåí=áåÇáÅ~íáçå=~í=ëìÅÅÉëëáîÉäó=

ÜáÖÜÉê=íìÄÉ=ëìééçêíëK=táíÜ=áåÅêÉ~ëáåÖ=ÜÉáÖÜí=íÜÉ=éêáã~êó=ëáÇÉ=íÉãéÉê~íìêÉ=áë=êÉÇìÅÉÇ=ïÜáÅÜ=

êÉÇìÅÉë=ÄçíÜ=íÜÉ=ëìéÉêÜÉ~í=~åÇ=íÜÉ=ëìêÑ~ÅÉ=íÉãéÉê~íìêÉK=tÜáÅÜ=çÑ=íÜÉëÉ=ÉÑÑÉÅíë=áë=~ÅíáåÖ=ÜÉêÉ=áë=åçí=

ÅäÉ~êK=qÜÉ=ÉñéÉêáÉåÅÉ=êÉÖ~êÇáåÖ=íÜáë=éÜÉåçãÉåçå=áë=ëÜçïå=áå=cáÖìêÉ=OJNP=Ñçê=íÜêÉÉ=éä~åíëK==

=

Figure 2-13: (a) Number of indications at successive tube support locations for three plants using Alloy 600 MA after about 12 to 15 years service. From Takamatsu et al., 1996. (b) Percentage of tubes with eddy current indications vs. 1000/T at successive tube supports for various Model D and Model 51 SGs. Activation energies shown. From Baum, 1999.

få=~ÇÇáíáçå=íç=íÜÉ=áåÑäìÉåÅÉ=çÑ=ëìêÑ~ÅÉ=íÉãéÉê~íìêÉ=íÜÉ=ÅçåÅÉåíê~íáçå=çÑ=ÅÜÉãáÅ~ä=ëéÉÅáÉë=áå=

ÅêÉîáÅÉë=ÇìÉ=íç=ëìéÉêÜÉ~í=ÅçåíêáÄìíÉë=ëáÖåáÑáÅ~åíäó=íç=Åçêêçëáçå=áå=ÜÉ~í=íê~åëÑÉê=ÅêÉîáÅÉëK=

cáÖìêÉ=OJNQ=ëÜçïë=íÜÉ=ã~ÖåáíìÇÉ=çÑ=ÅçåÅÉåíê~íáçå=íÜ~í=Å~å=çÅÅìê=áå=ÜÉ~í=íê~åëÑÉê=ÅêÉîáÅÉë=Ñçê=

î~êáçìë=ëéÉÅáÉë=~ë=~=ÑìåÅíáçå=çÑ=ÅçåÅÉåíê~íáçå=áå=íÜÉ=ÉåîáêçåãÉåíK=oÉã~êâ~ÄäÉ=~êÉ=íÜÉ=ÇáÑÑÉêÉåí=

ÅçåÅÉåíê~íáçå=Ñ~ÅíçêëK=k~=~åÇ=h=ÅçåÅÉåíê~íÉ=ãçêÉ=íÜ~å=`ä=~åÇ=cK=pìÅÜ=ÇáÑÑÉêÉåÅÉë=~êÉ=ÇìÉ=íç=íÜÉ=

ÇáÑÑÉêÉåí=î~éçìê=éêÉëëìêÉë=çÑ=íÜÉëÉ=ëéÉÅáÉëK==




OJNTEOJRQF

=

Figure 2-14: Estimated concentration of species in simulated SG crevices vs. concentration in the bulk water. Various concentration factors are shown. From Takamatsu et al., 1992.

2.3 PWR secondary side chemistry

2.3.1 Plant concepts

qÜÉ=ëÉÅçåÇ~êó=ëáÇÉ=ÅÜÉãáëíêó=Ü~ë=~äï~óë=ÄÉÉå=ÇáêÉÅíÉÇ=íç=~îçáÇ=çê=ãáåáãáòÉ=Åçêêçëáçå=Ç~ã~ÖÉ=íç=

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Figure 2-15: Secondary Side concept of a typical US PWR.

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Figure 2-16: Simplified diagram of a Steam Water Cycle in Siemens designed PWRs-

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2.3.2 Optimizations

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3 Material degradation management (Peter Ford)

3.1 Situation at the conclusion of the LCC2 report

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3.2 Updates on materials degradation Iissues

3.2.1 The effect of cold work on stress corrosion cracking of structural materials in BWRs and PWRs

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êÉÅÉåíäóI=ëáãáä~ê=ÇÉäÉíÉêáçìë=ÉÑÑÉÅíë=Ü~îÉ=ÄÉÉå=åçíÉÇ=Ñçê=qóéÉ=PMQ=ëí~áåäÉëë=ëíÉÉä=BWR=ÅçêÉ=ÅçãéçåÉåíë=íÜ~í=Ü~îÉ=ÄÉÉå=~ÄìëáîÉäó=ÖêçìåÇ=~åÇLçê=ÅçäÇ=ïçêâÉÇ=ÇìêáåÖ=Ñ~ÄêáÅ~íáçå=EjÉÇçÑÑI=

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4 Electrochemical membrane methods in LWR cleanup systems (Wilfried Rühle)

4.1 Introduction

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ãÉÅÜ~åáÅ~ä=Ñáäíê~íáçå=íÉÅÜåáèìÉëK=qÜÉëÉ=íÉÅÜåçäçÖáÉë=~êÉ=ìëÉÇ=íç=Åçåíêçä=íÜÉ=ÅÜÉãáÅ~ä=ëÜáã=áå=

PWRë=~åÇ=íç=ÅäÉ~å=íÜÉ=Åççä~åí=áå=ÄçíÜ=äáÖÜí=ï~íÉê=êÉ~Åíçê=íóéÉë=Ñêçã=ÅÜÉãáÅ~ä=éçääìí~åíë=~åÇ=

ÉëéÉÅá~ääó=Ñêçã=ê~Çáç=åìÅäáÇÉëK=

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áãéêçîÉãÉåíK=qÜÉ=ÉèìáéãÉåí=áë=ëé~Åáçìë=~åÇ=ÅçåëÉèìÉåíäó=åÉÉÇ=ãìÅÜ=ä~êÖÉê=êççãëK=qÜáë=áë=

ÉëéÉÅá~ääó=êÉäÉî~åí=Ñçê=íÜÉ=Åçåíêçä=~êÉ~ë=ïÜáÅÜ=Ü~îÉ=íç=ÄÉ=ÅçåëíêìÅíÉÇ=~í=~=ÜáÖÜ=íÉÅÜåçäçÖáÅ~ä=äÉîÉä=

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ïÜáÅÜ=ÇçÉëåDí=éêçÇìÅÉ=ãìÅÜ=ê~Çáç~ÅíáîÉ=ï~ëíÉ=~åÇ=ÇçÉëåDí=êÉèìáêÉ=ÜáÖÜ=áåîÉëíãÉåí=ÅçëíëK=

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PWRë=~åÇ=BWRë=Ü~îÉ=ÄÉÉå=ëí~êíÉÇI=m~ìäI=NVVRK=få=íÜÉëÉ=ÉñéÉêáãÉåíë=çåäó=ÉäÉÅíêçÅÜÉãáÅ~ä=ãÉãÄê~åÉ=íÉÅÜåáèìÉë=äáâÉ=“ãÉãÄê~åÉ=ÉäÉÅíêçäóëáëÒ=

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êÉîÉêëÉ=çëãçëáëI=ìäíê~=Ñáäíê~íáçåI=å~åç=Ñáäíê~íáçåI=ÇáÑÑìëáçå=Çá~äóëáë=ÉíÅK=ïÉêÉ=åçí=íÉëíÉÇ=~ë=íÜÉó=~êÉ=

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4.2 Membrane techniques under consideration

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4.2.1 Membrane electrolysis

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Figure 4-1: Schematic chart of membrane electrolysis (by courtesy of FuMA-Tech, a member of BWT AG, 2007).

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4.2.2 Electrodialysis (ED)

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Ñêçã=ëÉ~ï~íÉêI=Ñçê=íÜÉ=éêçÇìÅíáçå=çÑ=ÇêáåâáåÖ=ï~íÉê=Ñêçã=Äê~ÅâáëÜ=ï~íÉêI=Ñçê=íÜÉ=íêÉ~íãÉåí=çÑ=

ÄçáäÉêJÑÉÉÇ=ï~íÉê=~åÇ=íÜÉ=ÇÉë~äáå~íáçå=çÑ=ïÜÉó=EëâáããÉÇ=ãáäâFK=

=

Figure 4-2: Schematic chart of electrodialysis (by courtesy of FuMA-Tech, a member of BWT AG, 2007).

eçïÉîÉêI=íÜÉ=âÉó=~Çî~åí~ÖÉë=çÑ=ÉäÉÅíêçÇá~äóëáë=ÅçãÉ=áåíç=ÉÑÑÉÅí=é~êíáÅìä~êäó=áå=~ééäáÅ~íáçåë=Ñçê=

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4.2.3 Technical details of ED and other membrane techniques

QKOKPKN fçå=ÉñÅÜ~åÖÉ=ãÉãÄê~åÉë=

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5 Effect of water chemistry on fuel cladding

5.1 PWR water chemistry (Rolf Riess)

5.1.1 Introduction

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cáÖìêÉ=RJN=Ñçê=íÜÉ=rp=Å~ëÉ=Äó=qìêå~ÖÉI=OMMQK=cìêíÜÉê=ÇÉí~áäë=Å~å=ÄÉ=ÑçìåÇ=áå=~=êÉîáÉï=çÑ=íÜÉ=EPRI=t~íÉê=`ÜÉãáëíêó=dìáÇÉäáåÉë=Äó=cêìòòÉííá=Éí=~äKI=OMMQK=

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kî=OMMT

'05

Constant pH 6.9

Elevated lithium program

Modified lithium program

Zinc injection

Elevated constant pH (7.1/7.2)

Ultrasonic fuel cleaning

Elevated Constant pH 7.3/7.4

'75 '80 '85 '90 '95 '00

Water Chemistry Changes in U.S. PWRs

=

Figure 5-1: Water Chemistry Changes in U.S. PWRs, Turnage, 2004.




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1500 1000 500 0

6.7

6.8

6.9

7.0

7.1

7.2

7.3

7.4

6.6 0

0.5

1

1.5

2

2.5

3

3.5

4

Boron (mg/kg)

Limax = 2.2 mg/kg

=

Figure 5-2: Typical French Primary Water Chemistry, Bretelle et al., 2004.

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få=íÜÉ=ä~íÉ=NVUMë=òáåÅ=áåàÉÅíáçå=áå=BWRë=éêçîáÇÉÇ=ÉîáÇÉåÅÉ=íÜ~í=ê~Çá~íáçå=ÑáÉäÇë=ÅçìäÇ=ÄÉ=êÉÇìÅÉÇ=ïáíÜ=íÜÉ=ÅçåíêçääÉÇ=~ÇÇáíáçå=çÑ=wáåÅ=íç=íÜÉ=Åççä~åíK=pçãÉ=óÉ~êë=ä~íÉê=ÉñéÉêáãÉåí~ä=ëíìÇáÉë=~åÇ=

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_~ëÉÇ=çå=íÜÉëÉ=ÑáåÇáåÖëI=íÜÉ=ÑçääçïáåÖ=ÉñéÉÅí~íáçåë=ïÉêÉ=ÇÉîÉäçéÉÇI=êÉÖ~êÇáåÖ=íÜÉ=~ééäáÅ~íáçå=

áå=ÅçããÉêÅá~ä=éçïÉê=ëí~íáçåëW=

• wáåÅ=~ÑÑÉÅíë=íÜÉ=Åçêêçëáçå=éêçÇìÅí=Ñáäãë=çå=íÜÉ=áååÉê=ëìêÑ~ÅÉ=çÑ=íÜÉ=Åççä~åí=ëóëíÉãX=áí=ã~âÉë=

íÜÉ=çñáÇÉ=Ñáäã=íÜáååÉê=~åÇ=ãçêÉ=éêçíÉÅíáîÉK=qÜáë=ëáíì~íáçå=ëÜçìäÇ=íÜÉêÉÑçêÉ=êÉÇìÅÉ=íÜÉ=áåJÅçêÉ=

ÇÉéçëáíë=Äó=êÉÇìÅáåÖ=íÜÉ=CRUD=éêçÇìÅíáçå=íÉêãK==

• wáåÅ=êÉÇìÅÉë=íÜÉ=ëçäìÄáäáíó=çÑ=Åçêêçëáçå=éêçÇìÅí=Ñáäãë=çå=Åççä~åí=ëóëíÉã=ëìêÑ~ÅÉëK=fí=ëÜçìäÇ=

íÜÉêÉÑçêÉ=~ÑÑÉÅí=íÜÉ=Åçãéçëáíáçå=çÑ=CRUD=ÇÉéçëáíëK=

• wáåÅ=ëÜçìäÇ=êÉéä~ÅÉ=`çJSM=áå=íÜÉ=çñáÇÉ=ÑáäãK=




SJNESJNPF

6 References

^âìí~Ö~ï~=a~áëìâÉ=Éí=~äKI=póãéçëáìã=çå=t~íÉê=`ÜÉãáëíêó=~åÇ=`çêêçëáçå=çÑ=kìÅäÉ~ê=mçïÉê=

mä~åíë=áå=^ëá~I=OMMTK=

^äî~êÉò=mK=Éí=~äK=“Ultrasonic Fuel Cleaning System (UFCS)ÒI=qçécìÉä=jÉÉíáåÖI=p~ä~ã~åÅ~I=

OMMSK=

^åÇêÉëÉå=mKiKI=“Effect of Material and Environmental Variables on Stress Corrosion Crack Initiation in Slow Strain Rate Tests on Type 304 Stainless SteelÒI=póãéK=çå=båîáêçåãÉåí~ä=

pÉåëáíáîÉ=cê~ÅíìêÉX=bî~äì~íáçå=~åÇ=`çãé~êáëçå=çÑ=qÉëí=jÉíÜçÇëÒ=^éêáä=NVUOK=mìÄäáëÜÉÇ=áå=ASTM=

pqmUONI=ééKOTNJOUTI=NVUQK=

^åÇêÉëÉå=mKiKI=“Specific Anion and Corrosion Potential Effects on Environmentally Assisted Cracking in 288 WaterÒI=dbJòa=oÉéçêí=VPòaONRI=aÉÅÉãÄÉêI=NVVPK=

^åÇêÉëÉå=mKiI=bãáÖÜ=mKb=~åÇ=vçìåÖ=iKjKI=“Mechanistic and Kinetic Role of Yield Strength / Cold Work / Martensite, H2, Temperature, and Composition on SCC of Stainless SteelsÒI=mêçÅK=fåíK=póãéK=çå=jÉÅÜ~åáëãë=çÑ=j~íÉêá~ä=aÉÖê~Ç~íáçå=áå=kçåJaÉëíêìÅíáîÉ=bî~äì~íáçå=áå=iáÖÜí=t~íÉê=

oÉ~ÅíçêëI=lë~â~I=g~é~åI=j~ó=éìÄäáëÜÉÇ=Äó=fåëíK=çÑ=kìÅäÉ~ê=p~ÑÉíó=póëíÉãI=g~é~åI=ééK=ONRJOPVI=

OMMOK=

^åÇêÉëÉå=mKiI=bãáÖÜ=mKtI=jçêê~=jKj=~åÇ=eçêå=oKjI=“Effects of Yield Strength, Corrosion Potential, Stress Intensity Factor, Silicon and Grain Boundary Character on the SCC of Stainless SteelsÒI=mêçÅK=çÑ=NNíÜ

=fåíK=póãéK=çå=båîáêçåãÉåí~ä=aÉÖê~Ç~íáçå=çÑ=j~íÉêá~äë=áå=kìÅäÉ~ê=mçïÉê=

póëíÉãë=Ó=t~íÉê=oÉ~ÅíçêëI=^kpI=ééK=UNSJUPNK=OMMPK=

^åÇêÉëÉå=mKiK=~åÇ=jçêê~=jKjKI=“Effects of Positive and Negative dK/da on SCC Growth Rates”,=mêçÅK=NOíÜ=fåíK=póãéK=çå=båîáêçåãÉåí~ä=aÉÖê~Ç~íáçå=çÑ=j~íÉêá~äë=áå=kìÅäÉ~ê=mçïÉê=

póëíÉãë=Ó=t~íÉê=oÉ~ÅíçêëÒI=qjpI=påçïÄáêÇI=^ìÖìëí=OMMRK=

^åÇêÉëÉå=bKiK=Éí=~äKI=“Use of Primary Water Chemistry in PWRs to Mitigate PWSCC of Nickel Based AlloysÒI=fåíÉêå~íáçå~ä=`çåÑÉêÉåÅÉ=çå=t~íÉê=`ÜÉãáëíêó=çÑ=kìÅäÉ~ê=oÉ~Åíçê=póëíÉãëI=

gÉàìJfëä~åÇI=hçêÉ~I=OMMSK=

^åÇêÉëÉå=mKiI=“Emerging Issues and Fundamental Processes in Environmental Cracking in Hot WaterÒI=mêçÅK=oÉëÉ~êÅÜ=qçéáÅ~ä=póãéçëáìã=çå=båîáêçåãÉåí~ä=`ê~ÅâáåÖI=`çêêçëáçåLMTI=

k^`bI=OMMTK=

^åÇêÉëÉå=mKiKI=eáÅâáåÖ=gKI=^Üäìï~äá~=^K=~åÇ=táäëçå=gK=“Effect of H2 on Mitigation of PWSCC in Nickel Alloys”. mêçÅÉÉÇáåÖë=çÑ=fåíÉêå~íáçå~ä=`çåÑÉêÉåÅÉ=çå=léíáãáò~íáçå=çÑ=aáëëçäîÉÇ=

eóÇêçÖÉå=áå=PWR=mêáã~êó=`ççä~åí=qçÜçâì=råáîÉêëáíóI=g~é~å=gìäó=NUJNVI=OMMTK=

^åÇç=jK=~åÇ=k~â~í~=hI=“Crack Growth Rate Behaviour of Low Carbon Stainless steels of Hardened Heat Affected Zone in PLR Piping Weld JointsÒI mêçÅK=NPíÜ

=fåíK=póãéK=çå=

båîáêçåãÉåí~ä=aÉÖê~Ç~íáçå=çÑ=j~íÉêá~äë=áå=kìÅäÉ~ê=mçïÉê=póëíÉãë=Ó=t~íÉê=oÉ~ÅíçêëÒI=tÜáëíäÉê=

_Ì=^ìÖìëíI=OMMTK=

^åÖÉäáì=qKjI=^åÇêÉëÉå=mKiKI=pìíäáÑÑÉ=gK^K=~åÇ=eçêå=oKjKI=“Intergranular Stress Corrosion Cracking of Unsensitized Stainless Steels in BWR EnvironmentsÒI=áå=mêçÅÉÉÇáåÖë=çÑ=káåíÜ=

fåíÉêå~íáçå~ä=póãéçëáìã=çå=båîáêçåãÉåí~ä=aÉÖê~Ç~íáçå=áå=kìÅäÉ~ê=mçïÉê=póëíÉãëÓt~íÉê=

oÉ~ÅíçêëI=kÉïéçêí=_É~ÅÜI=bÇëK=pK=_êìÉããÉêI=cKmK=cçêÇI=qÜÉ=jÉí~ääìêÖáÅ~ä=pçÅáÉíóI=ééKPNNJPNUI=

^ìÖìëí=NJRI=NVVVK=

^êáçâ~=hKI=v~ã~Ç~=qKI=qÉê~ÅÜá=qK=~åÇ=`ÜáÄ~=dKI=“Cold work and Temperature Dependence on Crack Growth Behaviours of Austenitic Stainless Steels in Hydrogenated and Oxygenated High Temperature WaterÒI=mêçÅÉÉÇáåÖë=çÑ=íÜÉ=fåíÉêå~íáçå~ä=póãéçëáìã=cçåíÉîê~ìÇ=sf=I=pcbkI=

ééKRNJRUI=m~êáëI=pÉéíÉãÄÉê=NUJOOI=OMMSK=

^êáçâ~=hKI=v~ã~Ç~=qKI=qÉê~ÅÜá=qKI=“Role of Grain Boundary Creep on IGSCC of Non-Sensitized stainless Steels in High Temperature WaterÒI=mêçÅK=NPíÜ=fåíK=póãéK=çå=båîáêçåãÉåí~ä=

aÉÖê~Ç~íáçå=çÑ=j~íÉêá~äë=áå=kìÅäÉ~ê=mçïÉê=póëíÉãë=Ó=t~íÉê=oÉ~ÅíçêëI=tÜáëíäÉê=_Ì=^ìÖìëíI=

OMMTK=

^ííÉå~ëáç=pK=~åÇ=jçêíçå=aKI=“Measurement of the Ni/NiO Transition in Ni-Fe Alloys and Updated Data and Correlations to Quantify the Effect of Aqueous Hydrogen and Primary Water SCCÒI=mêçÅÉÉÇáåÖë=çÑ=bäÉîÉåíÜ=fåíÉêå~íáçå~ä=`çåÑÉêÉåÅÉ=çå=båîáêçåãÉåí~ä=aÉÖê~Ç~íáçå=áå=

kìÅäÉ~ê=mçïÉê=póëíÉãëÓt~íÉê=oÉ~ÅíçêëI=pâ~ã~åá~=içÇÖÉI=bÇëK=dK=t~ëI=iK=kÉäëçåI=^ãÉêáÅ~å=

kìÅäÉ~ê=pçÅáÉíóI=^ìÖìëí=RJVI=OMMPK=




SJOESJNPF

_~åÇó=oK=~åÇ=î~å=oççóÉåI=aK=“Mechanisms of Intergranular Failures in Alloy 600 in High Temperature EnvironmentsÒI=fåíÉêå~íáçå~ä=`çåÖêÉëë=çå=jÉí~ääáÅ=`çêêçëáçåI=eKmK=dçÇ~êÇI=ÉÇKI=

éK=OMOI=k~íáçå~ä=oÉëÉ~êÅÜ=`çìåÅáä=`~å~Ç~I=líí~ï~I=NVUQK=

_~ìã=^KI=“Relationships between Stress Corrosion Cracking Tests and Utility Operating ExperienceÒI=mêçÅÉÉÇáåÖë=çÑ=íÜÉ=VíÜ

=fåíÉêå~íáçå~ä=póãéçëáìã=çå=båîáêçåãÉåí~ä=aÉÖê~Ç~íáçå=çÑ=

j~íÉêá~äë=áå=kìÅäÉ~ê=mçïÉê=póëíÉãë=t~íÉê=oÉ~ÅíçêëI=t~êêÉåÇ~äÉI=mÉååëóäî~åá~I=NVVVK=

_~ìÉê=_K=Éí=~äKKI=“Anion-Exchange Membranes with Improved Alkaline StabilityÒI=aÉë~äáå~íáåÖI=TVI=NORJNQQI=NVVMK=

_~óÉê=dK=Éí=~äKI=“Framatome High Temperature Steam Generator Chemical Cleaning Process; A Comparison of Reglementation and Result of the Applications at NPP Neckarwestheim-1 (Germany) and NPP Borssele (Netherlands)ÒI=fåíÉêå~íáçå~ä=ÅçåÑÉêÉåÅÉ=çå=t~íÉê=`ÜÉãáëíêó=çÑ=

kìÅäÉ~ê=oÉ~Åíçê=póëíÉãëI=çå=gÉàì=fëä~åÇI=hçêÉ~I=OMMSK=

_ÉÖäÉó=oKqI=häÉáå=^Kt=~åÇ=dçäÇ=oKbI=“Investigation of ID Stress Corrosion Cracking in Field and Laboratory ProgramsÒI=`çåíêáÄìíáçå=çÑ=j~íÉêá~äë=fåîÉëíáÖ~íáçå=íç=íÜÉ=oÉëçäìíáçå=çÑ=

mêçÄäÉãë=båÅçìåíÉêÉÇ=áå=PWR=mä~åíëW=fåíÉêå~íáçå~ä=póãéçëáìãI=cêÉåÅÜ=kìÅäÉ~ê=båÉêÖó=pçÅáÉíóI=

éK=ONTI=m~êáëI=NVURK=

_ÉåÖíëëçå=_KI=“Recommendation concerning an increased Lithium concentration in the Reactor Water for Ringhals PWR Reactors during Operation (Mode 1-2)ÒI=oáåÖÜ~äë=oÉéçêí=NUV=MR=SMLPKMI=OMMSK=

_ÉååÉí=mK=Éí=~äKI=“Demonstration of the PWR Axial Offset Anomaly in IFA-665 AÒI=e~äÇÉå=

oÉéçêí=eto=UMUI=OMMRK=

_ÉååÉí=mK=Éí=~äKI=“Demonstration of the PWR AOA in the Halden ReactorÒI=fåíÉêå~íáçå~ä=`çåÑÉêÉåÅÉ=çå=t~íÉê=`ÜÉãáëíêó=çÑ=kìÅäÉ~ê=oÉ~Åíçê=póëíÉãëI=gÉàìJfëä~åÇI=hçêÉ~I=OMMSK=

_ÉêÖÉ=mÜ=~åÇ=açå~íá=gKoI=“Materials Requirements for Pressurized Water Reactor Steam Generator TubingÒI=Nuclear Technology Vol. 55I=éK=UUI=NVUNK=

Berge Ph, Noel D., Gras J and Prieux, P “Chloride Stress Corrosion Cracking of Alloy 600 in Boric Acid Solutions”,=mêçÅÉÉÇáåÖë=çÑ=báÖÜíÜ=fåíÉêå~íáçå~ä=póãéçëáìã=çå=båîáêçåãÉåí~ä=aÉÖê~Ç~íáçå=áå=

kìÅäÉ~ê=mçïÉê=póëíÉãëÓt~íÉê=oÉ~ÅíçêëI=^ãÉäá~=fëä~åÇI=bÇëK=^K=jÅfäêÉÉI=pK=_êìÉããÉêI=^ãÉêáÅ~å=

kìÅäÉ~ê=pçÅáÉíóI p. 189I=^ìÖìëí=NMJNQI=NVVT.=_ä~åÅÜÉí=gI=`çêáçì=eKI=dê~ää=iKI=j~ÜáÉì=`KI=lííÉê=`K=~åÇ=qìêäìÉê=dKI=“Historical Review of the

Principal Research Concerning the Phenomena of Cracking of Nickel-base Austenitic AlloysÒI=mêçÅÉÉÇáåÖë=çÑ=k^`bJR=DpíêÉëë=`çêêçëáçå=`ê~ÅâáåÖ=~åÇ=eóÇêçÖÉå=bãÄêáííäÉãÉåí=çÑ=fêçå=_~ëÉ=

^ääçóëDI=k~íáçå~ä=^ëëçÅá~íáçå=çÑ=`çêêçëáçå=båÖáåÉÉêëI=é=NNQVJNNSMI=NVTTK=

_çäò=jK=~åÇ=båâäÉê=dKI=“Bilanzierung und Regelung des 7Li-Haushaltes in DruckwasserreaktorenÒI=g~ÜêÉëí~ÖìåÖ=hÉêåíÉÅÜåáâ=OMMMI=_çåå=RI=OMMMK=

_çäò=jKI=oìÉÜäÉ=tKI=hçÜä=qK=~åÇ=cêóÇ~=mKI=“Electrochemical Treatment of Ammonia Contaminated Waste Water with Diamond ElectrodesÒ=sd_=hçåÑÉêÉåò=“`ÜÉãáÉ=áã=hê~ÑíïÉêâÒI=

OMMRK=

_êÉíÉääÉ=gJiI=dìáå~êÇ=iKI=^åÇêáÉì=`K=~åÇ=a~èì~áí=cKI=“EDF strategy for the PWR primary coolant pHÒI=fåíÉêå~íáçå~ä=`çåÑÉêÉåÅÉ=çå=t~íÉê=`ÜÉãáëíêó=çÑ=kìÅäÉ~ê=oÉ~Åíçê=póëíÉãëI=p~å=

cê~åÅáëÅçI=lÅíçÄÉê=OMMQK=

_êçïå=jK=~åÇ=jáääë=tKgKI “Load Path Effects on the Fracture Toughness of Alloy 82H and 52 Welds in Low Temperature WaterÒI=mêçÅK=NOíÜ

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j~íÉêá~äë=áå=kìÅäÉ~ê=mçïÉê=póëíÉãë=Ó=t~íÉê=oÉ~ÅíçêëÒI=qjpI=påçïÄáêÇI=^ìÖìëí=OMMRK=

_êìÉããÉê=pKj=~åÇ=qÜçã~ë=iKbI=“Insights into Environmental Degradation Mechanisms from High-Resolution Characterization of Crack TipsÒI=`ÜÉãáëíêó=~åÇ=bäÉÅíêçÅÜÉãáëíêó=çÑ=`çêêçëáçå=

~åÇ=píêÉëë=`çêêçëáçå=`ê~ÅâáåÖW=^=póãéçëáìã=eçåçêáåÖ=íÜÉ=`çåíêáÄìíáçåë=çÑ=oKtK=pí~ÉÜäÉI=oKeK=

gçåÉëI=ÉÇKI=qjpI=éKNOPI=t~êêÉåÇ~äÉI=mÉååëóäî~åá~I=OMMNK=

_êìÉããÉê=pK=~åÇ=qÜçã~ë=iKbKI=“Crack Tip Examinations of Primary Water Stress Corrosion Cracking in Alloy 600ÒI=mêçÅÉÉÇáåÖë=çÑ=íÜÉ=fåíÉêå~íáçå~ä=póãéçëáìã=cçåíÉîê~ìÇ=sf, pcbkI=

ééKPQTJPRTI=m~êáëI=pÉéíÉãÄÉê=NUJOOI=OMMSK=

_óÉêë=^K=~åÇ=aÉëÜçåI=“Crud Structure and Chemistry of PWR CrudÒI=mêçÅÉÉÇáåÖë=çÑ=íÜÉ=fåíÉêå~íáçå~ä=`çåÑÉêÉåÅÉ=çå=t~íÉê=`ÜÉãáëíêó=çÑ=kìÅäÉ~ê=oÉ~Åíçê=póëíÉãëI=p~å=cê~åÅáëÅçI=OMMQK=

_óÉêë=tK=^K=Éí=~äKI=“Crud Metamorphosis at the Callaway PlantÒI=fåíÉêå~íáçå~ä=`çåÑÉêÉåÅÉ=çå=t~íÉê=`ÜÉãáëíêó=çÑ=kìÅäÉ~ê=oÉ~Åíçê=póëíÉãëI=gÉàìJfëä~åÇI=hçêÉ~I=OMMSK=




SJPESJNPF

`~íí~åí=cI=“Chemical Analysis of OD Deposits Removed from SG TubesÒI=mêçÅÉÉÇáåÖëW=NVVP=bmof=tçêâëÜçé=çå=pÉÅçåÇ~êó=páÇÉ=IGALSCCX=qo=NMTUUPI=jKgK=m~êíêáÇÖÉ=~åÇ=gKbK=_êçìëë~êÇI=

ÉÇëKI=bmofI=éK=^LOI=m~äç=^äíçI=NVVPK=

`Ü~ãéáÖåó=cKI=`Ü~éÉäáÉê=cK=~åÇ=^ãò~ää~Ö=`KI=“Maintenance strategy of Inconel components in PWR primary systems in FranceÒI=mêçÅÉÉÇáåÖë=çÑ=`çåÑÉêÉåÅÉ=çå=sÉëëÉä=mÉåÉíê~íáçå=fåëéÉÅíáçåI=`ê~ÅâáåÖ=~åÇ=oÉé~áêëI=d~áíÜÉêëÄìêÖI=jaI=pÉéíÉãÄÉê=OVJlÅíçÄÉê=OI=OMMPK=

`Ü~êíáÉê=mKI=bÇãçåÇ=~åÇ=qìêäìÉê=aKdKI=“The French Regulatory Experience and Views on Nickel-base alloy PWSCC PreventionÒI=mêçÅÉÉÇáåÖë=çÑ=`çåÑÉêÉåÅÉ=çå=sÉëëÉä=mÉåÉíê~íáçå=fåëéÉÅíáçåI=`ê~ÅâáåÖ=~åÇ=oÉé~áêëI=d~áíÜÉêëÄìêÖI=jaI=pÉéíÉãÄÉê=OVJlÅíçÄÉê=OI=OMMPK=

`ÜÉå=`KjI=^ê~ä=hI=~åÇ=qÜÉìë=dKgI=“Computer Calculated Potential pH Diagrams to 300°CÒI=sçäìãÉë=NJPX=kmJPNPTI=bmofI=m~äç=^äíçI=NVUPK=

`ÜÉå=gKI=“AOA Root Cause Examination, Experimental ApproachesÒI=fåíÉêå~íáçå~ä=tçêâëÜçé=çå=léíáãáò~íáçå=çÑ=aáëëçäîÉÇ=eóÇêçÖÉå=`çåíÉåí=áå=PWR=mêáã~êó=`ççä~åíI=qçÜçâì=

råáîÉêëáíóI=g~é~åI=gìäó=NUJNVI=OMMTK=

`Üçá=a=~åÇ=t~ë=dKpI=“Pit Growth in Alloy 600/690 Steam Generator Tubes in Simulated Concentrated Environments (Cu2+, Cl- and SO4 2-)ÒI=Corrosion Vol. 46I=éK=NMM, NVVMK=

`Üçá=pKpI=cêìòòÉííá=hK~åÇ=p~ïçÅÜâ~=pIdI=PWR Molar Ratio Control Application Guidelines, Volume 1, SummaryX=qoJNMQUNNI=bmofI=m~äç=^äíçI=NVVRK=

`ÜóåçïÉíÜ=gK=~åÇ=eóêÉë=gKI=“Metallugical Examination of a Leaking Pressurized Tube from Braidwood Unit 1ÒI=mêçÅK=NPíÜ

=fåíK=póãéK=çå=båîáêçåãÉåí~ä=aÉÖê~Ç~íáçå=çÑ=j~íÉêá~äë=áå=kìÅäÉ~ê=

mçïÉê=póëíÉãë=Ó=t~íÉê=oÉ~ÅíçêëÒI=tÜáëíäÉê=_Ì=^ìÖìëíI=OMMTK=

`çãÄê~ÇÉ=mKI=`~óä~=lKI=cçìÅ~ìäí=jKI=s~åÅçå=aKI=dÉäéá=^K=~åÇ=pä~ã~=dKI=“About the Role of Surface Films on Alloy 600 Corrosion in High Temperature Deaerated EnvironmentsÒI=mêçÅÉÉÇáåÖë=çÑ=qÜáêÇ=fåíÉêå~íáçå~ä=póãéçëáìã=çå=båîáêçåãÉåí~ä=aÉÖê~Ç~íáçå=áå=kìÅäÉ~ê=mçïÉê=

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RORI=^ìÖìëí=PMJpÉéí=PI=NVUTK=

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`çéëçå=eKo=~åÇ=aÉ~å=pKtI=“Effect of Contaminants on Resistance to Stress Corrosion Cracking of Ni-Cr Alloy 600 in Pressurized WaterÒI=Corrosion Vol. 21I=éK=N, NVSRK=

`çìî~åí=qKI=jçìä~êí=mKI=_çêÇÉë=mKI=`~éÉääÉ=gKIoçìáääáçå=vK=~åÇ=_~äçå=qKI=“PWSCC of Austenitic Stainless Steels of Heaters of PressurizersÒI=mêçÅÉÉÇáåÖë=çÑ=íÜÉ=fåíÉêå~íáçå~ä=póãéçëáìã=

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`çìî~åí=qKI=`çãÄê~ÇÉ=mKI=s~áää~åí=cK=~åÇ=aÉ=_çìîáÉê=lKI=“Effect of Chlorides and Sulfates on SCC of Austenitic Stainless Steel in PWR EnvironmentÒI=mêçÅK=NPíÜ=fåíK=póãéK=çå=båîáêçåãÉåí~ä=

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ÇÉ=_çìîáÉê=lKI=s~áää~åí=cKI=_çìÅÜ~Åçìêí=jK=~åÇ=iÉã~áêÉ=mKI=“Effect of Copper Species on IGA/IGSCC of Alloy 600 in Neutral Sulfate EnvironmentsÒI=áå=mêçÅÉÉÇáåÖë=çÑ=qÉåíÜ=fåíÉêå~íáçå~ä=`çåÑÉêÉåÅÉ=çå=båîáêçåãÉåí~ä=aÉÖê~Ç~íáçå=áå=kìÅäÉ~ê=mçïÉê=póëíÉãëÓt~íÉê=

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