제출문 : ~ ː ː ː - 1 -

Transcription

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2 제출문 : ~ ː ː ː - 1 -

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4 기술개발사업최종보고서초록 - 3 -

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12 목 차

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16 표목차 ӧ

17 γ

18 그림목차 ӧ ӧ

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20 T w T sat T w T sat

21 T w T sat T w T sat T w T sat

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23 μ μ μ μ μ μ μ μ μ μ

24 μ μ μ μ μ μ

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36 l l l l l l l l

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44 ž ž ž ž ž

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47 ӧ ӧ Δ ӧ

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51 Mass loss (%) 100 f2 f3 f4 f Temperature ( o C)

52 Heat flow (mw/mg) f2 f3 f4 f Temperature ( o C) Absorption (%) NiFe 2 O 4 + Ni 2 FeBO Velocity (mm/s) ӧ

53 ӧ

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70 Φ ρ

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73 μ μ μ

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77 Ω

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87 1mm specimen 3mm copper rod 300 o C 96 bar Temperature [ o C] 308 Boiling point 0 Current [A]

88 Boiling point Temperature [ o C] mm specimen 3mm copper rod 300 o C 96 bar Current [A] voltage Linear fit Voltage [V] mm specimen 3mm copper rod 300 o C 96 bar Current [A]

89 bar Boiling point Temperature [ o C] bar Boiling point 1mm specimen 3mm copper rod 300 o C 96 bar Heat flux [W/cm 2 ]

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105 Chemicals Li-B P-103 DI-Water Purifier Sampling BPR Test Autoclave LIC Column 1 Column 2 DO/DH ph/cond. HX CW Purge HX Preheater H 2/O 2 Chemicals P-101 TIC Ni-Fe P-102 DWG. No. AOA-NANA Input Signal Action Always Heater Off Level Low Pump Charging Off Temp. Inlet Low High Warning Pump Recirc. Off Temp Outlet High Pump Recirc. Off Press. Low High Warning Pump Charging Off Cooling Pump Low Pump Recirc. Off

106 9.5mm MgO 160mm Heated Nichrome wire 240mm Zircaloy 4 Thermocouple SUS

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110 Li, ppm Metal, ppm Ni Fe B, ppm Hours Metal, ppm Ni Fe Li, ppm B, ppm Hours

111 Metal, ppm Li, ppm Ni Fe B, ppm Hours Metal, ppm Li, ppm Ni Fe B, ppm Hours

112 Metal, ppm Li, ppm Ni Fe B, ppm Hours

113 n r ( a r ) + Ñ ( a r vq ) = å( m& - m& ) + S t q q q q pq qp q p= 1 aq V q = ò a dv V q

114 m& pq m& lv ( - ) " hlv Tl Ts A i qe Aw = + L L C T T ( + pl max ( s - l,0)) hlv h pq = 6k q a p a q p d 2 p Nu 1/ 2 1/3 Nu p = Re p Pr Ai A i (( - ) - ) 6a sv 1 av /(1 a sv = d v a sv = min( av,0.25) " qe Aw r uur A = d x - x w ( w ) Aw dv

115 -4 ì , Tsub > 13.5K ï -3-4 dv = í Tsub, 0 < Tsub < 13.5K ï -3 î1.5 10, Tsub < 0 r r r ur ur r r å t n ( a qr ) ( ) ( pq ) q v q + Ñ a qr q v q v q = -a qñ p + Ñ t q + a qr q g + R + m& pq v pq - m& qp v qp ur ur ur ( F,, ) q F lift q F vm q p= 1 ur R pq n ur n r r å R pq = å K pq v p - vq p= 1 p= 1 ( ) K pq K pq aqa pr p f = t p t p t p r pd = 18m 2 p q f C D

116 C Re f = D 24 C D ( ) ì ï Re / Re, Re 1000 = í ïî 0.44, Re > 1000 C D a a = a + + Re Re ur R pq r r 0.75CD r pa q vr vr = d q dis vis ( ) Cd = min Cd, Cd dis vis Cd Cd ur F lift ur r r r F = -C r a v - v Ñ v ( ) ( ) lift l q p q p q

117 Cl ì , f 6000 ï f Cl = í-( e ) e, 6000 < f < ï 5 ïî f ³ /36000 f /310 5 f = Reb Rev Re b Re v Re Re b v r dv v = n d = 2 v l r r Ñ v n l l ur F vm ur F dq vq d p v p 0.5r a æ r r = - ö ç dt dt è ø vm q p ε ε ε

118 r æ m, ö ( r k ) + Ñ ( r vmk ) = Ñ Ñ k + G - r e + S t è ø t m m m ç k, m m k s k r æ mt, m ö e ( rme ) + Ñ ( rmvme ) = Ñ ç Ñ e + ( C1 Gk, m - C2 rme ) + S t è s e ø k e e e rm r N = åa r m i i i= 1 m t, m = r mc m 2 k e ε S k r r 0.75CD rlav vr vr = d v 3Cd vr Se = Ce 3 S d v r k C e 3 = 0.45 r p r r ur å t t n q ( a qr qhq ) + Ñ ( a qr quqhq ) = - a q + t q : Ñuq - Ñ qq + Sq + ( Q pq + m& pqhpq -m& qphqp ) p=

119 Q ur pq ( ) Qpq = hpq Tp -Tq h pq = 6k q a p a q p d 2 p Nu 1/ 2 1/3 Nu p = Re p Pr N ph " w = åaq, cell q q - w q= l ( ) q h T T " " " " qw, liq = qw, E + qw, C + qw, Q q " w, E " p 3 qw, E = dbw fnrvl 6 dbw ( ) dbw p a bq - = a = ( T -T ) w 2r v s r C k s ps s p

120 in ( Ts -T s ) b = / ( r r ) v l in ( U l ) q = max / 0.61,1.0 ( 200( )) 1.8 w sat n = T -T f æ 4gDr ö = ç è 3d bw r l ø q " w, C cell ( )( ) q = h T -T - W " w, C lw w 1 l q " w, Q 0.5 cell ( k r ) ( ) " -0.5 qw, Q = 2p W f l lc pl Tw -Tl W

121 ε

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123 Quenching heat flux ratio q q " " = w, Q / w, liq Evaporative heat flux ratio q q " " = w, E / w, liq

124 Vapor Volume Fraction W Heat Flux 6W Heat Flux 7W Heat Flux 8W Heat Flux 9W Heat Flux Axial Position(m)

125 Bubble Departure Diameter(m) W Heat Flux 6W Heat Flux 7W Heat Flux 8W Heat Flux 9W Heat Flux Axial Position(m) Wall Super Heat( o C) W Heat Flux 6W Heat Flux 7W Heat Flux 8W Heat Flux 9W Heat Flux Axial Position(m) T w T sat

126 0.4 Quenching Heat Ratio W Heat Flux 6W Heat Flux 7W Heat Flux 8W Heat Flux 9W Heat Flux Axial Position(m) 0.5 Evaporative Heat Ratio W Heat Flux 6W Heat Flux 7W Heat Flux 8W Heat Flux 9W Heat Flux Axial Position(m)

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128 Vapor Volume Fraction m/sec-314 o C 2m/sec-316 o C 2m/sec-317 o C 5m/sec-317 o C 5m/sec-318 o C 5m/sec o C 8m/sec o C 8m/sec-318 o C 8m/sec o C Axial Position(m)

129 Vapor Volume Fraction m/sec-306 o C 2m/sec-308 o C 2m/sec-310 o C 5m/sec-313 o C 5m/sec-315 o C 5m/sec-317 o C 8m/sec-315 o C 8m/sec-317 o C 8m/sec-318 o C Axial Position(m) Vapor Volume Fraction m/sec-300 o C 2m/sec-302 o C 2m/sec-303 o C 5m/sec-310 o C 5m/sec-312 o C 5m/sec-314 o C 8m/sec-313 o C 8m/sec-315 o C 8m/sec-317 o C Axial Position(m)

130 Bubble Departure Diameter(m) m/sec-314 o C 2m/sec-316 o C 2m/sec-317 o C 5m/sec-317 o C 5m/sec-318 o C 5m/sec o C 8m/sec o C 8m/sec-318 o C 8m/sec o C Axial Position(m) Bubble Departure Diameter(m) m/sec-306 o C 2m/sec-308 o C 2m/sec-310 o C 5m/sec-313 o C 5m/sec-315 o C 5m/sec-317 o C 8m/sec-315 o C 8m/sec-317 o C 8m/sec-318 o C Axial Position(m)

131 Bubble Departure Diameter(m) m/sec-300 o C 2m/sec-302 o C 2m/sec-303 o C 5m/sec-310 o C 5m/sec-312 o C 5m/sec-314 o C 8m/sec-313 o C 8m/sec-315 o C 8m/sec-317 o C Axial Position(m) Wall Super Heat( o C) m/sec-314 o C 2m/sec-316 o C 2m/sec-317 o C 5m/sec-317 o C 5m/sec-318 o C 5m/sec o C 8m/sec o C 8m/sec-318 o C 8m/sec o C Axial Position(m) T w T sat

132 Wall Super Heat( o C) m/sec-314 o C 2m/sec-316 o C 2m/sec-317 o C 5m/sec-317 o C 5m/sec-318 o C 5m/sec o C 8m/sec o C 8m/sec-318 o C 8m/sec o C Axial Position(m) T w T sat Wall Super Heat( o C) m/sec-300 o C 2m/sec-302 o C 2m/sec-303 o C 5m/sec-310 o C 5m/sec-312 o C 5m/sec-314 o C 8m/sec-313 o C 8m/sec-315 o C 8m/sec-317 o C Axial Position(m) T w T sat

133 Evaporative Heat Ratio m/sec-314 o C 2m/sec-316 o C 2m/sec-317 o C 5m/sec-317 o C 5m/sec-318 o C 5m/sec o C 8m/sec o C 8m/sec-318 o C 8m/sec o C Axial Position(m) Quenching Heat Ratio m/sec-314 o C 2m/sec-316 o C 2m/sec-317 o C 5m/sec-317 o C 5m/sec-318 o C 5m/sec o C 8m/sec o C 8m/sec-318 o C 8m/sec o C Axial Position(m)

134 Evaporative Heat Ratio m/sec-306 o C 2m/sec-308 o C 2m/sec-310 o C 5m/sec-313 o C 5m/sec-315 o C 5m/sec-317 o C 8m/sec-315 o C 8m/sec-317 o C 8m/sec-318 o C Axial Position(m) Quenching Heat Ratio m/sec-306 o C 2m/sec-308 o C 2m/sec-310 o C 5m/sec-313 o C 5m/sec-315 o C 5m/sec-317 o C 8m/sec-315 o C 8m/sec-317 o C 8m/sec-318 o C Axial Position(m)

135 Evaporative Heat Ratio m/sec-300 o C 2m/sec-302 o C 2m/sec-303 o C 5m/sec-310 o C 5m/sec-312 o C 5m/sec-314 o C 8m/sec-313 o C 8m/sec-315 o C 8m/sec-317 o C Axial Position(m) Quenching Heat Ratio m/sec-300 o C 2m/sec-302 o C 2m/sec-303 o C 5m/sec-310 o C 5m/sec-312 o C 5m/sec-314 o C 8m/sec-313 o C 8m/sec-315 o C 8m/sec-317 o C Axial Position(m)

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137 Vapor Volume Fraction o C 315 o C 317 o C 319 o C Axial Position(m) Bubble Departure Diameter(m) o C 315 o C 317 o C 319 o C Axial Position(m)

138 10 5 Wall Super Heat( o C) o C 315 o C 317 o C 319 o C Axial Position(m) T w T sat 0.06 Evaporative Heat Ratio o C 315 o C 317 o C 319 o C Axial Position(m)

139 0.05 Quenching Heat Ratio o C 315 o C 317 o C 319 o C Axial Position(m) ε

140 Wcm Wcm Wcm

141 (a) 8 W/cm 2 (b) 9 W/cm 2 (c) 10 W/cm 2 (a) 8 W/cm 2 (b) 9 W/cm 2 (c) 10 W/cm

142 (a) 8 W/cm 2 (b) 9 W/cm 2 (c) 10 W/cm 2 (a) 8 W/cm 2 (b) 9 W/cm 2 (c) 10 W/cm

143 Twall('C) q=8w/m2 q=9w/m2 q=10w/m2 Sat. Temp. at 150bar = 342'C Bubble departure diameter (mm) q=8w/m2 q=9w/m2 q=10w/m z(m) z(m)

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145 Onset of Nucleate Boiling (z=3.37m) 340 Temperature('C) Liquid average temp. Wall temp. Saturation temp Axial length(m) Average phase change rate (kg/m 3 s) Boiling + Condensation Wall boiling Vapor generation (z=3.53m) Onset of Nucleate Boiling (z=3.37m) Axial length(m)

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169 (9-5) 몰 (9-6) (9-7)

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172 DWG. NO. AOA atm H 2 concentration(cc/kg-h 2 O) atm 3 atm 2 atm 1 atm Temperature ( o C)

173 CW BPR Heat Exchanger 5 Test Section Column 2 Condenser 7 Reservoir High Pressure Pump PreHeater Flow meter Recirculation pump Chemicals Li / B P-103 Purifier Condenser CW Condenser CW DI-Water BPR Sampling ECP Column 2 LIC Column 1 Column 2 DO/DH/Cond. Test Section Purge P-101 Heat Exchanger PreHeater Reservoir Heater H 2/O 2 Chemicals Ni / Fe P-102 P-104 DWG. No. AOA -NANA

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190 log log log

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202 log log log ln

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222 μ μ 고체 용해된화학종,,,,,,,,,,,,,,,,

223 번호화학종번호화학종

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225 exp exp exp exp exp exp exp exp exp exp exp exp exp exp exp

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227 No 반응식 E E E E E E E E E E E E E E E E E E E E E E E E E E E E E E E+06 NA 1.500E E+09 NA 5.500E E E E E E E E E E E E E E E E E E E E E E E E E E E E E E E E E E E E E E E E E E E E E E E E E E+05 NA 3.900E E E E E E E E+04 NA 1.200E E E E E E E E-05 NA 1.400E E E E E E E

228 전기화학반응 Standard Electrode Potential: Standard Gibbs free energy

229 구 역 표면재료 평균온도 ( ) 부피 (m 3 ) 표면적 (m 2 ) 유속 (m/s) 유량 (m 3 /s) Zircaloy Zircaloy Zircaloy Zircaloy Stainless Steel Inconel Inconel Stainless Steel μ μ μ

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291 1.00E+06 (ppm) 9.00E+05 Fe Co Cr Ni Mn Li B 8.00E E+05 Grab 6.00E E E E E E E (hr)

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314 국가연도원전상황원인 / 조치 9 주기 AOA 심각 조치 : 75~80% 감발운전 (7 개월 ) 10주기 노심상부크러드 / 붕소침적 조치 : 출력밀도감소 ; 첨두계수, RCS 붕소농도저감 ; 1회연소된연료초음파세정및조기방출 Callaway 원인 : 5% AOA가주기초 -8% 편차설계와결합하여원자로보호계통의과온 / 온도-차긴급정지설정 80% 로급격출력감소시긴급 치저감초래정지 조치 : 없음 Palo Verde 2 9/10 주기 160 EFPD 까지유사현상확인 원인 : 추이분석결과연료집합체표면크러드축적 ; 과냉핵비등에의한고 - 기포발생률유발 ; 주기초고 - 붕소농도및주기초원자로불시정지등으로발생 조치 : 3.5% AOA 안전성평가, 과냉핵비등시기포발생률및크러드성분평가 Palo Verde 2 9 주기중초음파시험 : 10 개연료봉피복파손확인 원인 : 피복손상이고온과농축리튬에기인한침전물과다퇴적및극히국부적인관통벽부식 ; 연료손상원인은연료집합체과부하 [ 피복표면의아냉각 ( 미포화 ) 비등 ; 계통내철, 니켈등부식생성물 ; 주기초원자로비상정지 ; 주기중간원자로비상정지에기인 미국 Diablo Canyon 1, 2 계획예방정비후 AOA 보임 원인 : 연료봉표면침적물내붕소에의해기대밖의 Flux 형태와관련 조치 : AOA 정확한원인조사중 2 호기는최근 O/H 시징후경험 ; 양호기각각운전주기시점에서 AOA 변화정도경험 Seabrook 화학점검시냉각재고 - 방사능검출후, 5 주기말까지핵분열생성물증가 원인 : 연료인출중검사에서집합체 4 개의핀파손확인 ; 추가초음파검사에서총 5 개핀파손확인 Perry 냥각재계통재순환펌프정비후시험중집합체표면에서크러드이탈시재장전수조선량 10 배증가 원인 : 재장전수조표면선량이 60 m rem/hr 까지상승 ; 재순환펌프고 - 유량에의한핵연료표면으로부터의부식생성물이탈 원인 : 재순환펌프출구밸브완전개방으로재순환펌프수행 ; 운전원은재순환펌프가동으로인한방사선증가인지못함 ; 동시기동가능재순환펌프운전대수제한없었음 전원전 다수원전경험노심변경관련고장사례구분소개및재발방지권고사항제시 원인 : 미경험한기존연료관련설계변경시잠재적위험에대한충분한고려미흡 ; 노심과연료성능에예상치못한약영향을초래하는수질관리변경, 노심설계에대한공급자의분석오류, 예측능력한계성의인식 / 적용미흡등 권고사항 : 원자력정보망이나기타수단으로노심과연료성능불만족사고를산업계에즉시보고 ; 수질관리변경의노심성능영향과노심설계변경에의한냉각재화학적영향일체평가 ; 연료공급자와의긴밀한관계 ; 노심성능예측수단한계성검토 ; 노심운영체계나연료설계상중대변경시위험평가를수행하며, 평가는비정상적노심거동가능성을취급하고, 비상계획과감시요건을입증해야하며, 중요변경수행전에고위경영층과함께위헌평가결과와감시계획검토 헝가리 Paks 연료집합체세정작업중세정용기잔열제거기능상실로연료에심각한손상경험 원인 : Paks 2 호기 (VVER-440, 468 MWe) 집합체상침적 magnetite 제거위한연료 pit 내설치된세정용기에서집합체세정작업중발견 원인 : 연료온도 1,200~1,300 까지도달로판단 ; 임계분석결과용기내에임계에도달하기에충분한연료가있었던것으로판단 ; 해당연료집합체에대한구조적건전성손상여부확인감사계획됨

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322 Region BOC MOC EOC Operation Temp( ) Press(atm) ph t H 3BO 3(ppm) LiOH(ppm) LiBO 2( mol /l) DH 2( cc / kg ) CP ion Fe 2+ ( mol /l) Ni 2+ ( mol /l) Crud Ni(g/ cm2 ) NiO(g/ cm2 ) Ni xfe 3-xO 4(g/ cm2 ) Ni 2FeBO 5(g/ cm2 ) ZrO 2(g/ cm2 ) Li 2B 4O 7( mol /l)

323 축방향출력분포 장주기노심 냉각재 SG 전열관 산화물화학 비정상분포 (AOA) SNB Ni x Fe 3-x O 4 NiO Ni 기포 Ni / Fe ions 출력감발정지여유도감소비상정지조기연료방출피폭증대 붕소 크러드침적 LiBO 2 피복관 Ni 2 FeBO 5 AOA 완화 ï ph 최적화? SG 부식생성물 (CP) 방출감소? 원인물질감소 아연주입농축붕산 (EBA)? SG 전열관표면 CP 안정도증대? 붕소감소 ï? SG 크러드안정화? LiBO 2 감소 초음파세정? 노내크러드감소? 침적생성물제거

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334 1-1. J. A. Sawicki, J. Nuclear Materials, 374, (2008) W. A. Byers, W. T. Linsay, and R. H. Kunig, J. Solution Chemistry, Vol. 29, No. 6, (2000). 4-1., 5, "Halden In-Reactor Test to Exhibit PWR Axial Offset Anaomaly", EPRI , H. Kawamura, Effect of ph and Ni/Fe ratio on Crud Deposition Behavior on Heated Zircaloy-4 Surface in Simulated PWR Primary Water, Proceedings of Int. Conf. on Water Chemistry of Nuclear Reactor Systems, Berlin, P. Srisukvatananan and D. H. Lister, Nickel Ferrite Deposition onto Heated Zircaloy-4 Surfaces in High-Temperature Water with Sub-cooled Boiling; Preliminary Study of the Effects of ph and Zinc Addition, Proceedings of Int. Conf. on Water Chemistry of Nuclear Reactor Systems, Jeju, J. M. Hawkes, "The Simulation and Study of Conditions Leading to Axial Offset Anomaly in Pressurized Water Reactors", Thesis, Georgia Institute of Technology, J. Chen, "AOA-risk assessment, Experimental approaches", private communication, J. Yeon, Deposition behaviour of corrosion products on the Zircaloy heat transfer surface, J. Nuclear Materials, 354, pp J.G. Collier, "Convective boiling and condensation", ,,,, M.Z. Podowski, "Two-Phase flow Dynamics", in Boiling Heat Transfer, (Ed.: R.T. Lahey), Elsevier Publishing Corp., A. A. Troshko,, "Implementation and Testing of Subcooled Boling Model", Fluent Inc. December, W.E. Ranz et al., "Evaporation from Drops, Part I", Chem. eng. Prog., 48(3) : , March W.E. Ranz et al., "Evaporation from Drops, Part II", Chem. eng. Prog., 48(4) : , March N. Kurul and M. Z. Podowski et al., "Multidimensional effects in forced convection subcooled boiling", Proceeding of Ninth International Heat Transfer conference, Jerusalem, Israel, Vol. 1-BO-04, pp M. Z. Podowski, "Multidimensional Modeling of Two-Phase Flow and Heat Transfer", International Journal for Numerical Methods in Heat Transfer and Fluid Flow, V.18, Issue

335 3/4, 208, pp N. Kurul, "On the modeling of multidimensional effects in boiling channels", ANS Proc. 27th National Heat Transfer Conference, Minneapolis, MN, L. Schiller and Z. Naumann, "Z. Ver. Deutsch. Ing.", 77:318, S. A. Mosi and A. J. Alexander, " An Investigation of Particle Trajectories in Two-Phase Flow Systems", J. Fluid Mech., 55(2): , September 26, D. A. Drew and R. T. Lahey, "In Particulate Two-Phase Flow", pp , F. J., Moraga et al.; "Lateral forces on spheres in turbulent uniform shear flow", Int. J. Multiphase Flow, Vol. 25, pp A. A. Troshko and Y. A. Hassan, "A two-equation turbulence model of turbulent bubbly flow", Int. J. Multiphase Flow, Vol. 22 (11), pp Y. Wei and C. Morel, " Prediction of parameters distribution of upward boiling two-phase flow with two-fluid model" Proceedings of ICONE 10, Arlington, VA, USA, M. Z. Podowski, "Towards next generation multiphase models of nuclear thermal-hydraulics", Proceedings of Eighth International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Kyoto, Japan, Vol. I, pp , J. Henshaw, J. McGuire, H. Sims, A. Tuson, S. Dickinson, " The Chemistry of fuel deposits and its effect on AOA in PWR plants", Proc. Int. Conf. on Water Chemistry of Nuclear Reactor Systems, Jeju, Korea (2006) W. Byers, J. Deshon, "Structure and chemistry of PWR crud", Proc. Int. Conf. on Water Chemistry of Nuclear Reactor Systems, San Fransisco, U.S.A., p.1722 (2004) B. Beverskog, " AOA fuel crud: a theoretical approach", Proc. Int. Conf. on Water Chemistry of Nuclear Reactor Systems, Jeju, Korea (2006) W. Byers, J. Deshon, G. Gary, J. Small, J. McInvale, "Crud metamorphosis at the Callaway plant" Proc. Int. Conf. on Water Chemistry of Nuclear Reactor Systems, Jeju, Korea (2006) H. Kawamura, M. Furuya, "Effect of ph and Ni/Fe ratio on crud deposition behavior on heated Zircaloy-4 surface in simulated PWR primary water" Proc. Int. Conf. on Water Chemistry of Nuclear Reactor Systems, Berlin, Germany (2008) J. Blok, S. Chauffiriat, P. Frattini, "Modeling the axial offset anomaly in PWRs", Proc. Int. Conf. on Water Chemistry of Nuclear Reactor Systems, Avignon, France (2002) N. Doncel, J. Chen, P. Gillen, H. Bergvist, "On the role of nickel deposition in a CIPS occurrence in PWR", Proc. Int. Conf. on Water Chemistry of Nuclear Reactor Systems, Berlin, Germany (2008) J. Sawicki, "Nuclear chemistry model of borated fuel crud" Proc. Int. Conf. on Water Chemistry of Nuclear Reactor Systems, Avignon, France (2002) D. Farnsworth, J. Bosma, "Summary of first cycle data and results for elevated-constant

336 ph control at Comanche Peak steam electric station" Proc. Int. Conf. on Water Chemistry of Nuclear Reactor Systems, San Fransisco, U.S.A., p.1661 (2004) J. Deshon, K. Edsinger, P. Frattini, D. Hussey, C. Wood, "Ultrasonic fuel cleaning in PWRs and BWRs", Proc. Int. Conf. on Water Chemistry of Nuclear Reactor Systems, Jeju, Korea (2006) J. Stevens, D. Farnsworth, J. Bosma, J. Deshon, "Elevated RCS ph program at Comanche Peak", Proc. Int. Conf. on Water Chemistry of Nuclear Reactor Systems, Jeju, Korea (2006) A. Tigeras, J-L. Bretelle, E. Decossin, "EDF AOA experience: chemical and thermal-hydraulic analysis", Proc. Int. Conf. on Water Chemistry of Nuclear Reactor Systems, San Fransisco, U.S.A., p.1661 (2004) Y. K. Kim et al., Technology development to resolve axial offset anomaly",, KNFC, D. M. Himmelblau, "Solubilities of Inert Gases in Water", Journal of Chemical and Engineering Data, Vol. 5, No. 1, January (1960) PWR Primary water chemistry guidelines, Vol. 1, Rev. 5, EPRI, Palo Alto, CA, TR V1R5, A.Tigeras, J-L. Bretelle, E. Decossin, "EDF AOA experience: Chemical and thermal-hydraulic analysis", Int. Conf. on Water Chemistry of Nuclear Reactor Systems", San Francisco, US, OCt Root cause investigation of axial offset anomaly, EPRI, Palo Alto, CA USA, TR , P.L. Frattini, P.L. Blok, S. Chauffriat, J. Sawicki, J. Riddle, "Axial offset anomaly: coupling PWR primary chemistry with core design", Nuclear Energy, 2001, 40(2), , (), V.K. Dhir, "Complete Numerical Simulation of Subcooled flow boiling in the presence of thermal and chemical interactions", DOE grant No. DE-FG03-99SF-21930, B.G. Jones, et al., "Modeling and Thermal Performance Evaluation of Porous Layers in Sub-Cooled Boiling Region of PWRs and Effects of Sub-Cooled Nucleate Boiling on Anomalous Porous Crud Deposition on Fuel Pin Surfaces", DOE DEFG07-001D13924, Modeling PWR Fuel Corrosion Product Deposition and Growth Processes, EPRI, Palo Alto, CA: F.D. Nicholson and J.V. Sarbutt, "The effect of boiling on the mass transfer of corrosion products in high temperature, high pressure water circuits", Corrosion, 36(1), 1-9,

337 W.A. Byers, J. Deshon, "Structure and Chemistry of PWR Crud", Int. Conf. on Water Chemistry of nuclear Reactor Systems, San Francisco, CA., USA, P. Cohen, "Heat and mass transfer for boiling in porous deposits with chimneys", AIChe Symposium Series, 70(138), pp , C. Pan, et al., Wick Boiling Performance in Porous Deposits with Chimneys", ASME/AIChe/ANS National Heat Transfer Symposium on Multiphase Flow and Heat Transfer, Denver, August W. Woodside an J.H. Messmer, "Thermal conductivity of porous media I. Unconsolidated Sands", J. of Applied Physics, 32(9), , Handbook of Chemistry and Physics, 73th Edition, CRC Press, Boca Raton, B.G. Jones, and C. Pan, "A study of wick boiling phenomena in porous deposits", annual report, EPRI J. Henshaw, et al., "Modeling PWR Fuel Corrosion Product Deposition and Growth Processes", EPRI, EPRI , R.W. Schrage, "A theoretical study of interface mass transfer", Columbia University Press, New York, Keenan, K.L. and Keyes, F.G., "Thermodynamic Properties of Steam", 1st Edition, Wiley, New York, D.D. Mcdonald, M. Urquius-Mcdonald, "A Coupled Environment Model for Stress Corrosion Cracking in Sensitized Type 304 Stainless Steel in LWR Environments", Corrosion Science, Vol. 32, No. 1, pp , A.S. Quist and W.L. Marshall, "Assignment of limiting equivalent conductances for single ions to 400", J. Phys. Chem., 69(9), (1965) J.A. LaVerne and S.M. Pimblott, "Diffusion-kinetic modeling of the electro radiolysis of water at elevated temperatures", J. Phys. Chem., 97, (1993) D.D. Mcdonald, "Viability of hydrogen water chemistry for protecting in-vessel components of boiling water reactor", Corrosion, 48(3), , C.R. Wike and C.Y. Lee, Ind. Eng. Chem., 47, 1253, (1955) Hari Selvi Viswanathan, Modification of the Finite Element Heat and Mass Transfer Code (FEHM) to Model Multicomponent Reactive Transport, LA T, Los Alamos National Laboratory, U.S.A., D. Dickinson, J. Hensaw, A. Tuson, and H.E. Sims, "Radiolysis Effects in Sub-cooled Nucleate Boiling", Int. Conf. on Nuclear Reactor Systems, avignon, France, H. Christensen, "Fundamental Aspects of Water Coolant Radiolysis", SKI Report 2006:16, April Marshall, W.L., and Franck, E.LU., "Ion product of Water Substance, , bars. New International Formulation and its Background", Journal of Physical and Chemical Reference Data 10(2), p ,

338 W.D. Fletcher, "Interaction of stainless steel corrosion products and boric acid solutions", WCAP-3730, Westinghouse Electric Corporation, Atomic Power Division, March M.A. Blesa, A.J.G. Maroto, A.E. Regazzoni, "Boric acid adsorption on magnetite and zirconium dioxide", J. Colloid Interface Sci., 99, 32-40, Gusonas, Adsorption of Boric Acid on Synthetic Fuel Crud Oxides, EPRI, Palo Alto, CA: , D.A. Palmer, P. Benezeth, D.J. Wesolowski, L.M. Anovitz, Y. Zhgenti, N. Kan, Adsorption of Ions on Zirconium Oxide Surfaces from Aqueous Solutions at High Temperatures, EPRI, Palo Alto, CA: , S. Dickinson, J. Henshaw, J.C. McGurk, H.E. Sims, "Modeling PWR fuel corrosion product deposition and growth process: Final Report", EPRI, Palo Alto, CA: W.A. Byers, W.T. Lindsay Jr., R.H. kunig, "Solubility of Lithium Monoborate in High Temperature Water", J. Solution Chem., 28, 541, J. A. Battaglia and J. Roesmer, "Utilization of Enriched Boric Acid in Pressurized Water Reactor Plants", Proceedings of EPRI Seminar on PWR Primary Chemistry and Radiation Field Control, Paper 34, (1988) V. Goehlich and J. Florinski, "Enriched Boric Acid for Pressurized Water Reactors", Proceedings of Conference on Chemistry in Water Reactors, p. 128 (1994) "An Evaluation of Enriched Boric Acid in European PWRs", , Palo Alto, (2001) "Re-Evaluation of the Benefits of Implementing Enriched Boric Acid"' TR , Palo Alto, (1998) C. M. M. Coutinho et al., "Enrichment of Boron 10", INIS-BR-2496, (1990) K. Takeda et al., Kogaku-Kogaku-Robunshu, 15, 567 (1989) V. Goehlich, "Enriched Boron Products", Proceedings of Int. Conference on Water Chemistry of Nuclear Reactor Systems 6, BNES, p. 187 (1992) W. B. Rodill, "Feasibility Study on Enriched Boron, Surry Power Station, Unit 1&2", Proceedings of EPRI Seminar on PWR Primary Water Chemistry and Radiation Field Control, Paper 35, March (1988) Y. L. Sandler and R. H. Kunig, Nucl. Sci. Eng., 64, 866 (1977) Y. L. Sandler and R. H. Kunig, Nucl. Sci. Eng., 77, 211 (1981) "PWR Primary Water Chemistry Guidelines: Revision 6", , Palo Alto, (2007) "PWR Primary Water Chemistry Guidelines: Revision 4", TR V1R4, Palo Alto, (1999) P. O. Aronsson et al., "High ph Operation at Swedish PWRs", EPRI Radiation Field Control Seminar, Palo Alto, (1991) T. A. Beineke et al., "High ph Operation in ABB C-E Plants", EPRI Radiation Field

339 Control Seminar, Palo Alto, (1991) M. J. B. Hudson and T. F. Burns, "Radiation Field Reduction by Elevated ph Control at Millstone 3", EPRI Radiation Field Control Seminar, Palo Alto, (1991) T. A. Beineke and P. Crinigan, "Evaluation of Elevated RCS Lithium Chemistry at Calvert Cliffs Unit 2", ASME/IEEE Power Generation Conference, Boston, (1990) I. Mark, "Enriched Boric Acid Promises Greater Flexibility for PWR Operators", Nuclear Eng. Int., 34, 47 (1989) L. W. Green et al., Can. J. Chem., 62, 1452 (1984) C. A. Bergmann, " Evaluation of Selected Parameters on Exposure Rates in Westinghouse Designed Nuclear Plants", Proceedings of Int. Conference on Water Chemistry of Nuclear Reactor Systems 5, BNES, p. 9 (1989) Y. K. Kim et al., Technology development to resolve axial offset anomaly",, KNFC, David Perkins, Programmatic Challenges PWR Primary Chemistry Optimization, 2010 KHNP-EPRI Technical Exchange Workshop, May Jiaxin Chen, AOA-risk assessment - Experimental approaches, Studsvik Nuclear AB, a presentation at KAERI, July 24, MULTEQ: Equilibrium of an Electrolytic Solution with Vapor-Liquid Partitioning and Precipitation. The Database, Version 5.0, EPRI, Palo Alto, CA: , CRUD AOA,, 6 Workshop (2007), ~ 6. 1, INTEC, KAERI Joshua Mahlon Hawkes, The Simulation and Study of Conditions Leading to Axial Offset Anomaly in Pressurized Water Reactors, In Partial Fulfillment Of the Requirements for the Degree Master of Science in Nuclear Engineering School of Mechanical Engineering, Georgia Institute of Technology, USA, December,

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345 l Operating Conditions - Flow rate : ~19 GPM (4315 LPH) - Pressure : 5000 psi (345 bar) Max. - Temperature : 650 F (343 C) Max. Pump - Power : 3/4 HP, MagneDrive - Total head : 12 m l 일본 CRIEPI에서사용중인펌프 (From Kawamura 이메일 ) - Flow rate : 20 liter/min (max) - Total head : 100 m - Temp. : 355 (max)

346 RPM 76.5HZ 1.5HP Req'd HEAD(M) RPM 60 HZ RPM 50 HZ FLOW(LPM)

347 6 5 [ :45 "/Graph2" ( )] Linear Regression for Data1_C: Y = A + B * X Flow(Liter/min) inlet 1/4 inch inlet 1 inch test zone Parameter Value Error A B [ :32 "/Graph1" ( )] Linear Regression for Data1_B: Y = A + B * X Parameter Value Error A B [ :16 "/Graph3" ( )] Linear Regression for Data1_D: Y = A + B * X Hz Parameter Value Error A B E

348 1/2" pipe, w/o spacer 압력 (MPa) 유량 (liter/min) 압력강하 (kpa) 유속 (m/sec) 12.0 MPa MPa /4" pipe, w/ spacer 압력 (MPa) 유량 (liter/min) 압력강하 (kpa) 유속 (m/sec) 15.0 MPa 노심핵연료 Halden Studsvik CEA-EDF Lister Kawamura KAERI ID[annulus], mm Gap size, mm 유량, L/min ? 유속, m/sec 0~ 7? 열원길이, mm , 열원직경, mm , ~

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352 350 A1 ( Li : 1.5 ppm, B : ppm, Fe : 20 ppm, Ni : 20 ppm, Fe/Ni nitrate 사용 ) 300 Temperature ( o C) Specimen Surface Outlet Solution Inlet Solution Preheater Pressure(Kgf/cm 2 ) DH (ppm) DO (count) ph 수소주입농도 : 21 cc/kg 운전중고압펌프정지 (Fe/Ni 용액농도가높아서고압펌프전단필터막힘 ) 소음발생으로펌프교체, 가압중단 DH ppm 단위, 수치이상 ( 보정필요 ) Conductivity (ms/cm) Time (hours) Inlet Outlet

353 350 A2 ( Li : 1.5 ppm, B : ppm, Fe : 200 ppb, Ni : 200 ppb, Fe/Ni nitrate 사용 ) 300 Temperature ( o C) 카트리지히터승온시알람경보 power off (2 회 ) - Thermocouple 교체 Specimen Surface Outlet Solution Inlet Solution Preheater 50 Pressure(Kgf/cm 2 ) A1 실험과비교위해 5 일시험 DH (ppm) DO (ppb) ph 수소주입농도 : 21 cc/kg 5 0 DH 검출기 ppm 단위교정 100 Conductivity (ms/cm) Inlet Time (hours)

354 350 A3 ( Li : 1.5 ppm, B : ppm, Fe : 200 ppb, Ni : 200 ppb, Fe/Ni nitrate 사용 ) 300 Temperature ( o C) Specimen Surface Outlet Solution Inlet Solution Preheater Pressure(Kgf/cm 2 ) 주간실험 0 DH (ppm) DO (ppb) ph 수소주입농도 : 21 cc/kg Conductivity (ms/cm) Time (hours) Inlet

355 350 A4 ( Li : 1.5 ppm, B : ppm, Fe : 200 ppb, Ni : 200 ppb, Fe/Ni acetate 사용 ) 300 Temperature ( o C) Pressure(Kgf/cm 2 ) Specimen Surface Outlet Solution Inlet Solution Preheater Fe/Ni nitrate 에서 acetate 로바꿈 계속 2 주간실험 DH (ppm) DO (ppb) ph 수소주입농도 : 21 cc/kg DH 검출기수치이상 Conductivity (ms/cm) Time (hours) Inlet

356 350 A5 ( Li : 3.5 ppm, B : 1500 ppm, Fe : 2 ppm, Ni : 2 ppm, Fe/Ni acetate 사용 ) 300 Temperature ( o C) Specimen Surface Outlet Solution Inlet Solution Preheater Pressure(Kgf/cm 2 ) DH (cc/kg) DO (ppb) ph Conductivity (ms/cm) 수소주입농도 : 21 cc/kg 고압펌프이상정지, 90 분후재작동 Time (hours) DH 검출기단위를 cc/kg 으로변환 Inlet

357 350 A6 ( Li : 5 ppm, B : 1500 ppm, Fe : 2 ppm, Ni : 2 ppm, Fe/Ni acetate 사용 ) 300 Temperature ( o C) Specimen Surface Outlet Solution Inlet Solution Preheater Pressure(Kgf/cm 2 ) DH (cc/kg) DO (ppb) ph Conductivity (ms/cm) 수소주입농도 : 21 cc/kg Inlet Time (hours)

358 350 A7 ( Li : 2.2 ppm, B : 1500 ppm, Fe : 2 ppm, Ni : 2 ppm, Fe/Ni acetate 사용 ) 300 Temperature ( o C) Specimen Surface Outlet Solution Inlet Solution Preheater 순간정전으로인한전원 off Pressure(Kgf/cm 2 ) DH (cc/kg) DO (ppb) ph Conductivity (ms/cm) 수소주입농도 : 21 cc/kg Inlet Time (hours)

359 350 A8 ( Li : 1.5 ppm, B : 500 ppm, Fe : 2 ppm, Ni : 2 ppm, Fe/Ni acetate 사용 ) 300 Temperature ( o C) Specimen Surface Outlet Solution Inlet Solution Preheater Pressure(Kgf/cm 2 ) DH (cc/kg) DO (ppb) ph 수소주입농도 : 21 cc/kg DH 센서이상 실험종료후 DO, DH 압력센서보정 Conductivity (ms/cm) Time (hours) Inlet

360 350 A9 ( Li : 1.5 ppm, B : 170 ppm, Fe : 2 ppm, Ni : 2 ppm, Fe/Ni acetate 사용 ) 300 Temperature ( o C) Specimen Surface Outlet Solution Inlet Solution Preheater Pressure(Kgf/cm 2 ) DH (cc/kg) DO (ppb) ph Conductivity (ms/cm) 수소주입농도 : 21 cc/kg Inlet Time (hours)

361 350 A10 ( Li : 5 ppm, B : 885 ppm, Fe : 2 ppm, Ni : 2 ppm, Fe/Ni acetate 사용 ) 300 Temperature ( o C) Specimen Surface Outlet Solution Inlet Solution Preheater Pressure(Kgf/cm 2 ) Preheater 에서 heating zone 으로가는배관에서누수발생 ; 배관수정 리본히터불량 ; 교체 DH (cc/kg) DO (ppb) ph Conductivity (ms/cm) 수소주입농도 : 21 cc/kg Inlet Time (hours)

362 350 A11 ( Li : 2.5 ppm, B : 885 ppm, Fe : 2 ppm, Ni : 2 ppm, Fe/Ni acetate 사용 ) 300 Temperature ( o C) Specimen Surface Outlet Solution Inlet Solution Preheater Pressure(Kgf/cm 2 ) 고압펌프전단필터교환시펌핑이상 ; 약 90 분후재가동 7.0 DH (cc/kg) DO (ppb) ph 수소주입농도 : 21 cc/kg 실험중 DO, DH 센서이상 실험후 DO, DH 센서보정 100 Conductivity (ms/cm) Inlet Time (hours)

363 350 A12 ( Li : 3.5 ppm, B : 1500 ppm, Fe : 2 ppm, Ni : 2 ppm, Fe/Ni acetate 사용 ) 300 Temperature ( o C) Specimen Surface Outlet Solution Inlet Solution Preheater Pressure(Kgf/cm 2 ) DH (cc/kg) DO (ppb) ph 수소주입농도 : 5 cc/kg Conductivity (ms/cm) Time (hours) Inlet

364 350 A13 ( Li : 3.5 ppm, B : 1500 ppm, Fe : 2 ppm, Ni : 2 ppm, Fe/Ni acetate 사용 ) 300 Temperature ( o C) Specimen Surface Outlet Solution Inlet Solution Preheater Pressure(Kgf/cm 2 ) DH (cc/kg) DO (ppb) ph Conductivity (ms/cm) 수소주입농도 : 40 cc/kg Inlet Time (hours)

365 350 A14 ( Li : 3.5 ppm, B : 1500 ppm, Fe : 2 ppm, Ni : 2 ppm, Fe/Ni acetate 사용 ) 300 Temperature ( o C) Specimen Surface Outlet Solution Inlet Solution Preheater Pressure(Kgf/cm 2 ) DH (cc/kg) DO (ppb) ph 수소주입농도 : 70 cc/kg DO 센서이상, 실험후센서보정 DH 센서이상, 실험후센서보정 100 Conductivity (ms/cm) Inlet Time (hours)

366 Temperature ( o C) A14 ( Li : 3.5 ppm, B : 1500 ppm, Fe : 2 ppm, Ni : 2 ppm, Fe/Ni acetate사용 ) (A4 재시험 ) Specimen Surface Outlet Solution Inlet Solution Preheater Pressure(Kgf/cm 2 ) DH (cc/kg) DO (ppb) ph Conductivity (ms/cm) 수소주입농도 : 70 cc/kg 배관을수정하여 Inlet/Outlet 에서전도도를동시측정 Inlet Outlet Time (hours)

367 350 A16 ( Li : 3.5 ppm, B : 1500 ppm, Fe : 2 ppm, Ni : 2 ppm, Fe/Ni acetate 사용 ) 300 Temperature ( o C) Specimen Surface Outlet Solution Inlet Solution Preheater Ar gas 교체시기포에의해 level sensor 오작동 ; 40 분정도 heater off 50 Pressure(Kgf/cm 2 ) 실험용액 0.5 cc/min 으로연속주입 (Makeup tank 농도 Li: 3.5 ppm, B: 1,500 ppm, Fe: 240 ppm, Ni: 240 ppm) DH (cc/kg) DO (ppb) ph Conductivity (ms/cm) 수소주입농도 : 50 cc/kg Time (hours) Inlet Outlet

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378 최종보고서요약서

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