蝗ｹ轤唄・ｼ・ｭ・暦ｽｳ・・ｾ枩HPup逕ｨ蝗ｹ・・ｷｨW.pdf
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1 JANTI-VIP-05- 第 4 版 BWR 炉内構造物点検評価ガイドライン [ 炉心シュラウド ] ( 第 4 版 ) 平成 20 年 6 月 有限責任中間法人日本原子力技術協会
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7 A SCC B C D 182 E F G H I K
8 L M N O P
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10 BWR ,5 2-6
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16 VTUT ET VT MVT-1 1 mil0.025mm VT-3 UT JEAG ET 3-
17 ( 3-3)
18 (1) (2) (3)(4)(5) H1H7 MVT-1 (1) UT ET (2) ( 3-4) (3) MVT-1 () UT ET MVT-1 (4) 3.2 ( 3-5) (5)
19 3-5 SCC ( 3-6) (1) 10
20 3.3.2 (1)(2) (1)(2)
21 ) No 1) 1 Yes No Yes Yes No No Yes 3)
22 3.3-2 Yes No Yes No
23
24 H3H7 50( 25mm) S2 H7 50S2 LOCA 2-2
25
26 VT-3
27 X-750 SCC SCC MVT SUS304SUS304L SUS316L SUS316LSUSF316L XM-19 X %SUS304 Cr 0.03% SUS304LSUS316LBWR BWR 0.02% XM-19 BWR % Cr Cr Nb 82 Nb 182 X-750 X-750 SCC X-750
28 304L 316L IASCC 3-1 ET JEAC
29
30
31 3-3
32 () CSS H7 H7 H3 H6 H7 H4
33 H H
34
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38 50 mm
39 3-6SCC SCC 3-7
40 3-8 X-750 SCC 1 SCC MWe 1mm 10mm % 40mm 20 80% 20 10
41 80% HWC NWC 80% NWC HWC
42
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44 SCC SUS304 SUS SUS304 SCC C 0.03%SUS304L SUS316L C N 0.1% A-1 10 SUS304 SUS304L SUS316L A-1 SUS304 SCC Cr A-2 SUS304 SCC 285 8ppm 1.35y (=159 ) 304 (100A) (SUS304L 316L) 3000 A-3 (SUS304L316L) SUS304 SCC SUS304 SUS316L SCC A-4SUS316L HAZ SCC A-5 SCC A-6 SUS304 SCC A-7NWC 0.2S/cm150mVSHE
45 HWC 0.2S/cm200mVSHE SUS304L SUS316L SUS304 A-8 SUS304 SUS316 IASCC n/m 2 E1MeV A-9 A-1 BWR Vol.34No.10pp (1983).
46 (a) SUS304 ( 0.06%) 50m (b) SUS304L 0.017% ) 50m (c) SUS316L ( 0.010%) 50m A-1 10%620 24h BWR IGSCC 12 9.
47 PPrecipitate Cr23C6 A-2 SUS h TEM N.Saito, Y.Tsuchiya, F.Kano, N.Tanaka,Variation of Slow Strain Rate Test Fracture Mode of Type 304L Stainless Steel in 288 Water,Corrosion, Vol.56. No.1, pp (2000).
48 % %kgf/mm 2 A-3 SCC 1.35y= ppm ( 100A) ()() ( 59 )
49 A-4 CBB SCC 12888ppm M. Tsubota, Y.Kanazawa, H.Inoue, Effect of Cold Work on the SCC Susceptibility of Austenitic Stainless Steels Proceedings of 7 th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors,Vol.1(1995)
50 A-5 SUS316L SCC S.Ooki, Y.Tanaka, K.Takamori, S.Suzuki, S.Tanaka, Y.Saito, T.Nakamura, T.Kato, K.Chatani, M.Kodama, Study on SCC Growth Behavior of BWR Core Shroud Proceedings of the 12 th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors-, 2005,
51 A-6 CBB SCC
52 A-7(1) SSRT SUS h IGSCC O 2 440ppbH 2 O 2 =0~570ppbH 2 =0150ppb 0.1S/cm 0.3S/cm N.Saito, E.Kikuchi, H.Sakamoto, J.Kuniya, S.Suzuki,Susceptibility of Sensitized Type 304 Stainless Steel to Intergranular Stress Corrosion Craking in Simulated Boiling-Water Reactor Environments,Corrosion, Vol.53, No.7, pp (1997).
53 A-7(2) SUS h 288O 2 440ppbH 2 O 2 =0~570ppbH 2 =14150ppb =0.1S/cm 0.3S/cm E.Kikuchi, M.Itow, J.Kuniya, H.Sakamoto, M.Yamamoto, A.Sudo, S.Suzuki, M.Kitamura,Intergranular Stress Corrosion Crack Growth of Type 304 Stainless Steel in a Simulated Boiling-Water Reactor Environment,Corrosion, Vol.53, No.4, pp (1997).
54 A-8(1) SUS304 SCC 0.2S/cm150mVSHE 18) M.Itow et al., SCC Crack Growth Rates of Type 304 Stainless Steel at High K Region in Simulated BWR Environment,CORROSION 2000, Paper ) BWR IGSCC 12 9
55 A-8(2) SCC 0.2S/cm150mVSHE 19) BWR IGSCC 12 9
56 A-8(3) SUS304 SCC 0.2S/cm200mVSHE 10) E.Kikuchi et al, Intergranular Stress Corrosion Crack Growth of Sensitized Type 304 Stainless Steel in a Simulated Boiling-Water Reactor Environment, Corrosion Vol.53, No.4, pp (1997). 11) L.Lungberg, BWR Water Chemistry Impurity Studies, Volume 3: Fracture Mechanics Studies, EPRI NP-6773-SD (March, 1990). 12) A.Sudo and M.Itow, SCC Propagation of Sensitized Materials in BWR Environment, Proc. of the International Symposium on Plant Aging and Life Predictions of Corrodible Structures, pp , May 15-18, 1995, Sapporo, Japan. 13) BWR ) BWR 7 3
57 A-8(4) SCC 0.2S/cm200mVSHE 22) 12 3
58 A-9 SSRT SUS304 SUS316 IGSCC 288O ppm0.1S/cm M.Kodama, R.Katsura, J.Morisawa, S.Nishimura, S.Suzuki, K.Asano, K.Fukuya, K.Nakata,IASCC Susceptibility of Austenitic Stainless Steels Irradiated to High Neutron Fluence, Proc. of 6th Int. Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, TMS, 1993, pp A-9 Ref.1:W.L.Clarke, A,J.Jacobs, Proc. of 1 st Int. Symposium. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, NACE, 1983, pp Ref.3:A.J.Jacobs, G.P.Wozaldo, K.Nakata, T.Yoshida, I.Masaoka, Proc. of 3rd Int. Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, TMS, 1987, pp Ref.8:M.Kodama, S.Nishimura, J.Morisawa, S.Suzuki, S.Shima, M.Yamamoto, Proc. of 5th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, ANS, 1991, pp
59 XM-19 XM-19ASME Type XM-19 SUS304 Cr Ni MoMnNbV CRD A-2 A-3 A-2 XM-19 ASME SA-479 / SA-479M Type XM-19 wt.% C Mn P S Si Cr Ni N Mo Cb V A-3 XM-19 JSME SNC MPa MPa MPa 300 XM-19GXM SUS SUS SUS316L A-10 XM-19 SUS304 M-19 2 A-11 XM SCC SUS IGSCC XM-19 10,000 SCC
60 A-10 XM-19 ASTM A262E J.N. Kass et al., Stress Corrosion Resistance of XM-19, CORROSION NACEVol.35, No., June, % A-11 XM-19 SCC J.N. Kass et al., Stress Corrosion Resistance of XM-19, CORROSION NACEVol.35, No., June, 1979.
61 () SCC ( A-12 A-13 A-14) 182 SCC Cr ( A-15) Cr Nb 82 Nb SCC ( A-4 A-5 A-16) 600 HAZ SCC ( A-5 A-12 A-17) 182 SCC ( A-18) 182 SCC (K ) ( A-19A-20) 182 SCC 10 1 ( A-21) SCC (SUS304L,SUS316L) SCC
62 75m 75m a) Alloy182 b) Alloy600 HAZ A-12 Alloy182/600 SCC SEM A-13 Alloy182/600
63 A-14 Alloy182 AW+62124Hours Concentration (Wt.%) Distance (nm) Grain boundary with Compositional profile M 23 C 6, Nb-rich MC Cr and Nb depletion A-15 Alloy182
64 A-4 A-5 SCC
65 2888 ppmo 2 UCL2.5Sm Alloy182/600 W+PWHT+LTA Alloy182/600 W+LTA k = Hr -1 t 0 = Hr Alloy825 Alloy182/600W+LTA Alloy18230 Alloy182/600W+PWHT+LTA LTA 50024Hr k = Hr -1 PWHT60024Hr t 0 = Hr Alloy82 W+LTA Alloy182 W+PWHT+LTA A-16 Alloy SCC 2888 ppmo 2 2.5Sm Alloy600HAZ* k = Hr -1 t = +2 Hr * : W+PWHT+LTA **: W+PWHT Alloy600HAZ* Alloy600HAZ** Alloy600HAZW+PWHT+LTA SCC Alloy600HAZW+PWHT+LTA 4 Alloy600HAZW+PWHT 5 LTA 50024Hr PWHT60024Hr A-17 Alloy600HAZ SCC
66 mV SHE 0mV SHE -100mV SHE 600 u (MPa) y UCL 182(SR+LTS) (GFW) 0.1S/cm(NaNO 3 ) (Hr) A-18 Alloy182 SCC 182 SCC 45 (1998.8)pp
67 , 182, PWHT, ppmO 2, 0.2S/cm( A182, PWHT, ppbO 2, 0.1S/cm B182, AW, ppbO 2, 0.1S/cm 182, PWHT+LTA, 288NWC,ECP mV, 0.1S/cm 182, AW&PWHT, 288> 250ppbO 2 >50mV, <0.3S/cm 82, AW, ppbO 2, S/cm 82, PWHT+LTA, 288NWC, A-19 BWR SCC
68 A-20 Alloy182 SCC M.Itow, Y.Abe, H.Sakamoto, S.Hida, K.Takamori, S.Suzuki, The Effect of Corrosion Potential on Alloy 182 Crack Growth Rate in High Temperature Water, Proc. of 8th Int. Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, Amelia Island, USA, pp (1997).
69 A-21 Alloy182 SCC L.G.Ljungberg M.Stigenberg, K.Gott, U.Morin, J.L.Nelson, B.Bengtsson and C.Jansson, Propagation of Stress Corrosion Cracking in Weld Structures of the Nickel-Base Alloy182,Proceedings of the International Symposium on Plant Aging and Life Predictions of Corrodible Structures, Japan, pp (1995).
70 X-750 X-750 JIS NCF750 Ni A-6 X-750 SCC A-22 X-750 SCC SCC A A-24 SCC A-25 SCC A-26 A-6 X-750 wt.% C Si Mn P S Ni Cr Fe Mo Cu Al Ti Nb+Ta
71 A-22 X-750 SCC 1994 CBB 2888ppm O2500h A-23 X-750 SCC K. Hattori et al., Effect of Chloride on the Stress Corrosion Cracking Susceptibility of Inconel X-750 in High-Temperature Water, CORROSION NACE, Vol.42(1986)531. Ref.(1) : S.Hattori, Stress Corrosion Cracking of Age-Hardenable Nickel Base Alloy in High Temperature Water American Nuclear Society Annual Meeting, Miami, Florida, P.7, 1981.
72 A-24 X-750 M. Tsubota et al., Study on SCC Susceptibility of Inconel X-750 in Hihi-Temperature Pure Water: Effects of Aging Temperature and Time., CORROSION NACE, Vol.44(1988)73. A-25 X-750 SCC 33 86(1984).
73 UCL 28880kgf/cm 2 8ppm O2 A-26 X-750 SCC 288 M. Tsubota et al., PREDICTION OF THE CRACK INITIATION TIME OF THE ALLOYS USED IN HIGH TEMPERATURE, CORROSION NACE, Vol.35, No., June, 1994.
74 IASCC IASCC BWR 1100MWe IASCC IASCC B-1 BWRSSRT (1) SCCIGSCC SUS n/m 2 SUS n/m MWe (DOT 3.5) (E>1MeV) B-1 80% (n/m 2 s) B (n/m 2 ) 60 (n/m 2 ) IASCC H H H H H6a H6b H
75 H4 IASCC H4 60 IASCC () (1) M.Kodama, R.Katsura, J.Morisawa, S.Nishimura, S.Suzuki, K.Asano, K.Fukuya, K.Nakata,IASCC Susceptibility of Austenitic Stainless Steels Irradiated to High Neutron Fluence, Proc. of 6th Int. Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, TMS, 1993, pp
76 B-1 IGSCC B-1 Ref.1:W.L.Clarke, A,J.Jacobs, Proc. of 1 st Int. Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, NACE, 1983, pp Ref.3:A.J.Jacobs, G.P.Wozaldo, K.Nakata, T.Yoshida, I.Masaoka, Proc. of 3rd Int. Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, TMS, 1987, pp Ref.8:M.Kodama, S.Nishimura, J.Morisawa, S.Suzuki, S.Shima, M.Yamamoto, Proc. of 5th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, ANS, 1991, pp
77 C. C. (1) KW (2) C-3 (3) (4).J m sec
78 (5) a a b C. (1) (2) C-8 C-9 C-9 (3) C-10 C-11 C-12 t1 (t3-t2) t2 20% (4) C-13
79
80 a
81 b
82 a a ()
83 b ()
84 a. b
85 a b H4
86 a N/mm
87 C- C-
88
89 C-13a
90 C-13
91 182 SCC 1. SCC 2. SCC D-1 JSME JSME S NA ASME Code Sec.XI App.C C3220 App.C C-3220 ASME ASMENRC NUREG-0313 Rev.2 SKIFS NRC NUREG-0313 Rev.2 D-1 K 10ksiin 11MPam28.5ksiin31.3MPam SKIFS D-2 BWRVIP SCC SCC SCC SUS304 SUS304LSUS316L316NG JSMESCCSUS304
92 NUREG-0313 Rev.2 JanssonMorin Jones Molander Janssen Molander Kikuchi Lungberg Sudo BWR NRC NUREG-0313 Rev.2 Horn Sec.XI Task Group NRC NUREG-0313 Rev.2 Type S/cm 0.28ppm ksiin 62ksiin BWR0.2S/cm SKIFSMorinJansson JanssonMorin Itow SUS304 SCC (PLEX 60 8 ) D-3 SUS304 SUS304LSUS316L316NGSCC Ford Ford NUREG-0313Rev.2 SCC SCC n/m 2 SCC n/m n/m 2 SCC n/m 2
93 SUS304 SUS304LSUS316L316NG SCC D-4 R (KminKmax) ECP Hz 0.2S/cm 150mVSHE 5ppb 5ppb SUS304 D-4 NUREG-0313 Rev.2 SKIFS D-2 NRC NUREG-0313 Rev.2 SKIFS D-3 PLEDGE Jansson Morin SCC D-3 D-4 NRC NUREG-0313 Rev.2 K mm/s mm/s K mm/s mm/sk=57.9mpamk da/dt mm/sk57.9mpam (1) D-4 PLEDGE
94 SUS304 D-5 PLEDGE D-6 NRC NURE-0313 Rev.2 KSUS mm/s mm/s K SUS304 K SCC da/dt mm/sk57.9 MPam (2) D-5 R (KminKmax) ECP Hz 0.2S/cm 200mVSHE 5ppb 5ppb SUS304 SUS304 D-7 JSMEK mm/sscc KSUS304 SCC K da/dt mm/sk57.9 MPam (3) D-8 SKIFS Jansson Morin PLEDGE
95 SCC D mm/s SCC SUS304 SCC SKIFS 1/10 JSME 1/8 SCC 1/10 K mm/ssccksus304 SCCKSCC da/dt mm/sk57.9 MPam (4) D-10 SUS304 PLEDGE n/m 2 SUS304 SCC (PLEDGE)(PLEX 60 8 )SUS304L SUS316L316NG SCC SUS304 SUS304 SCC da/dt= n 3.6 (CK 4 ) n (5) n
96 C (i) (n/m 2 ) C= (6) (ii) (n/m 2 ) (n/m 2 ) C= ln() (7) (iii) (n/m 2 ) C= (8) da/dtmm/skmpam SCC SUS304 SUS304LSUS316L316NG SCC n/m 2 0.2S/cmECP150mVSHE SUS304 da/dt K K57.9 (9) da/dt K3.4 (10) da/dt K57.9 (11) da/dt K K57.9 (12) da/dt K6.7 (13) da/dt K57.9 (14) da/dtmm/skmpam SCC D S/cmECP200mVSHE SUS304 da/dt K K57.9 (15) da/dt K12.9 (16)
97 da/dt K57.9 (17) da/dt K K57.9 (18) da/dt K19.3 (19) da/dt K57.9 (20) da/dtmm/skmpam SCC D n/m 2 SUS304 da/dt= n 3.6 (CK 4 ) n (21) n C (i) n/m 2 C= (22) (ii) n/m (n/m 2 ) C= ln() (23) (iii) n/m 2 C= (24) da/dtmm/skmpam 5. SCC BWR 182 SCC 23),24),25) NWC 0.1S/cmKMorinNWC 0.3S/cm 26)
98 D-13 SCC da/dt(m/sec)k(mpam) da/dt K K50.3 (25) K m/sec (25) m/seck=13.3mpamk da/dt K13.3 (26) K m/sec(2) m/seck=50.3mpamk da/dt210-9 K50.3 (27) 182 SCC D-14 SUS304 K K SCC 1)JSME S NA ) ASME Boiler and Pressure Vessel Code Sec. XI, The American Society of Mechanical Engineers, 1995, p397. 3) Hazelton W.S. and Koo W.H, Technical Report on Material Selection and Processing Guidelines for BWR Coolant Pressure Boundary Piping, U.S. Nuclear Regulatory Commission,NUREG-0313 Rev.2,July ) DRAFT SKIFS 1996:1 The Swedish Nuclear Power Inspectoraite s Regulations Concerning Structural Components in Nuclear Installations, SKIFS 1994:1 including changes in accordance with SKIFS 1995:1,Department of Structural
99 Integrity Swedish Nuclear Power Inspectorate,Augst ) BWRVIP BWR Vessel and Internals Project,Evaluation of Crack Growth in Stainless Steel RPV Internals (BWRVIP-14), EPRI TR , March ) C.Jansson and U.Morin, Assessment of Crack Growth Rates in Austenitic Stainless Steels in Operating BWRs,Proc. of the 8 th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems, ANS, La Grange Park, IL, August ) R.L.Jones,Some Critical Corrosion Issues and Mitigation Strategies Affecting Light Water Reactors,Material Performance, July ) A.Molander and C.Janssen,In Situ Corrosion Potential Monitoring in Swedish BWRs,Proc. of the 5 th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems, ANS, La Grange Park, IL, p.118 August ) A.Molander et al,influence of Flow-rate on Critical Potential for IGSCC of Stainless Steel in Simulated BWR Environment A SSRT Study, Proc. of the 8 th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems, ANS, La Grange Park, IL, August ) E.Kikuchi et al,intergranular Stress Corrosion Crack Growth of Sensitized Type 304 Stainless Steel in a Simulated Boiling-Water Reactor Environment,Corrosion Vol.53, No.4, P.307 (1997). 11) L.Lungberg,BWR Water Chemistry Impurity Studies, Volume 3: Fracture Mechanics Studies,EPRI NP-6773-SD (March, 1990). 12) A.Sudo and M.Itow, SCC Propagation of Sensitized Materials in BWR Environment, Proc. of the International Symposium on Plant Aging and Life Predictions of Corrodible Structures, p.903, May 15-18, 1995, Sapporo, Japan. 13) ) ) M.R.Horn et al., The Growth of and Stability of Stress Corrosion Cracks in Large Diameter BWR Piping, Electric Power Research Institute, NP-2472, vol.1, 2, July ) Section XI Task Group for Piping Flaw Evaluation, ASME Code, Evaluation of
100 Flaws in Austenitic Steel Piping, J. Of Pressure Vessel Technology, vol.8, p.366, ASME, ) U.Morin and C.Jansson, Stress Corrosion Growth in BWR Environment MD-01 Rev.2in SwedishSydkraft KonsultMalmo,Sweden, ) M.Itow et al.,scc Crack Growth Rates of Type 304 Stainless Steel at High K Region in Simulated BWR Environment, CORROSION 2000, Paper ) IGSCC ) () 8 3 pp ) F.P.Ford,Quantitative Prediction of Environmentally Assisted Cracking, CORROSION Vol.52, No.5, pp , May (1996). 22) ) 24) M.Itow et al.,crack Growth Rates of Alloy 182 in High Temperature Water, Seventh International Symposium on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, August ) M.Itow et al.,the Effect of Corrosion Potential on Alloy 182 Crack Growth Rate in High Temperature Water,Eighth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, August ) U.Morin et al.,crack Growth Rates for Ni-Base Alloys with the Application to an Operating BWR, Sixth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, August 1993.
101 da/dt(mm/s) K(MPam) NUREG Rev.2 () da/dt= K () 11mm/ Type304 SKIFS Draft (NWC) da/dt= K 3 (HWC) da/dt= K 3 SS23 33 (Type304 ) JSME (NWC) da/dt= K (HWC) da/dt= K SUS304 K K K ( )
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120 R(t)(R/t) 50 H4H7H6a 50.8 mm H7 70 mmh6a 75.8 mm E-1 H6a ( E-2) SCC 50m a/=0.1 E m ( E-2) 0 0 H4 ( 2 )H7 H6a H4 H4 2 ( 2) E-3 E-4 SCC 2
121 SCC H7 H7 2 H7a E-5 E-6 H7b E-7 H7 E-8 E-9 E-10 0 SCC SCC H6a H6a E-11 E-12 H6a SCC H6a SCC KWang 4 K ( S S ) a (1) n1 n in Snn((x)=(x/a) n ) S in n
122 n=0 n=1 (1) Raju-Newman API KI[Go og1 1(a/t)G2 2(a/t) 2 +G3 3(a/t) 3 G4 4(a/t) 4 ]a (2) Go G4 a 04 4 X t X t (X) (3) X X t X SCC SCC SUS304 SUS304LSUS316L316NG SCC SCC n/m 2 0.2S/cmECP150mVSHE (i) SUS304 da/dt K K57.9 (4) da/dt K3.4 (5) da/dt K57.9 (6) (ii) da/dt K K57.9 (7) da/dt K6.7 (8) da/dt K57.9 (9) da/dtmm/skmpam
123 SCC E S/cmECP200mVSHE (i) SUS304 da/dt K K57.9 (10) da/dt K12.9 (11) da/dt K57.9 (12) (ii) da/dt K K57.9 (13) da/dt K19.3 (14) da/dt K57.9 (15) da/dtmm/skmpam SCC E n/m 2 SUS304 da/dt= n 3.6 (CK 4 ) n (16) n C (i) n/m 2 C= (17) (ii) n/m n/m 2 C= ln() (18) (iii) n/m 2 C= (19) da/dtmm/skmpam
124 182 SCC da/dt K K50.3 (20) da/dt K13.3 (21) da/dt K50.3 (22) da/dtmm/skmpam 182 SCC E-15 SUS304 K K SCC K K H4 ( 1) K 17mm 31MPam K 0 E-16 H4 ( 2) K 10mm 28 MPam 25 K 0 E-17(1) K 9MPam 18 mm K 0 E-17(2) H7 H7a K 12mm 33MPam K 0 E-18 H7 H7b K 19mm 24MPam K 0 E-19 H7 () 8 18MPa m E-20
125 H7 () 30 30MPa m E-21 H7 () 20 28MPam E-22 H6a K 14mm 41MPam K=21MPa m E-23 H6a K 8mm 27MPam 23mm K 0 ( E-24) K H6a 500m K 9mm K 49MPam 28mm K 0 ( E-25) H7 K 20mm 63MPam K 0 E-26 SCC SCC IASCC H SCCda/dt a/=0.1 H4 ( 1) NWC 38 50% HWC E-27(1) H4 ( 1) NWC 33
126 50%HWC E-27(2) H4 ( 2) NWC % E-28(1) HWC E-28(2) H4 ( 2) NWC % E-28(3) HWC 30 E-28(4) H7 H7a NWC 23 50%HWC E-29 H7 () NWC60 5% E-30 H7 () H7 () 60 8% ( E-31 E-32) H7 () %( E-33) H6 (H6a )25 50%(HWC) E-34 H6 (H6a )
127 NWC (HWC) ( E-35) H6 H6a NWC 5 20 HWC E-36 H7 NWC 7 HWC E-37 1)G.S.WangWeight Function Estimation of SIF for Mode I Part-Elliptical Crack under Arbitrary Load,Engineering Fracture Mechanics Vol.41, No.5, pp ,(1992). 2)I.S.Raju and J.C.Newman Jr., NASA Technical Paper 1578(1979). 3)API Recommended Practice 579 First Edition,AppendixC,Jan ) 60 8.
128 a/=0.1 a 50m H4H7 H6a 50.8mm H7 70mm H6a 75.8mm 500m E-1
129 x a a Ri Ri a t t E-2
130 E-3 H4 E-4 H4
131 E-5 H7a E-6 H7a
132 E-7 H7b
133 E-2-5 E-8 HH7-7 1 E-2-6 H-7 E-9 H7 2
134 E-10 H7
135 E-11 H6a E-12 H6a
136 E-4-4 (a) (H-7 K E-4-4 ) 4-1 H-4 1 (H-7 E-13 SCC
137 E-14 SCC
138 E SCC
139 E-16 H4 1
140 (1) K (2) K E-17 H4 2
141 E-18 (H7 H7a ) E-19 (H7 H7b )
142 E-20 (H7 1) E-21 (H7 2)
143 E-22 (H7 3) (8) H-6aBWR-VIP14
144 E-23 (H6a ) E-24 (H6a )
145 E-25 (H6a ) E-26 (H7 H7a )
146 E-27(1) (H4 1) () E-27(2) (H4 1) ()
147 E-28(1) (H4 2) () E-28(2) (H4 2) ()
148 E-28(3) (H4 2) () E-28(4) (H4 2) ()
149 E-29 (H7 H7a ) () E-30 (H7 H7b ) ()
150 E-31 () (H7 1) E-32 () (H7 2)
151 E-33 () (H7 3)
152 E-34 (H6a ) () E-35 (H6a ) ()
153 E-36 (H6a ) E-37 (H7a H7a )
154 2.1 (1) BWR 1100MWe (2) BWR 1100MWe (3) -1 (a)
155 (b) (c) (4) BWR 1100MWe (5)
156 2.2 (1) a (2) (3) V7 (4)
157 (5) (6) a b (7)
158 (8) a (9) a (7) (10) 3.1
159 (1) (a)h4 (b)(r)(t)(r/t) 50 50mm (2) (1)Brown Slowley (1) K=aFI() = FI() (3) (a) S2 (b) S2 F (c) (c) (4)PLEXKIC n/m 2 (4) PLEX ( )KIC 43.2MPam( n/m 2 ) 3.2. KIC=43.2MPam S %( 23mm) n/m 2 H4 B 20
160 n/m 2 H-4 -B 20 () (1) W.R.Brown,Jr.andJ.E.SlawleyPlane Strain Fracture Toughness Testing of High Strength Metallic Materials, ASTM STP 410,1966,p.12. (2)()
161 a a a a
162 1100MWe (%) (%) / /(%)
163
164 kn kn (knm) Pa (1) (2) MPa SUS316L (1) (2) =2.3Sm (MPa) (MPa) (MPa) E/
165 V1 V2 V3 V4 V5 V6 V7
166 (a) (b)
167 180 4
168
169
170 75% 50% 25% 10%
171 + 75%+ 50%+ 25%+ 10%+
172
173 75%,50%,25%,10%
174
175 50% + 10% + 10%
176 S2
177 50% +H7a 10%,H6b 40% + 10%
178
179
180 F 2.3
181 (N/mm 2 ) /
182 1100MWe mm
183 7.2mm 1.7mm
184
185
186
187
188
189
190
191
192 ROV
193
194 H-3 1,100MWe BWR
195 H-4 1,100MWe BWR
196 H-5 1,100MWe BWR
197 H-6 1,100MWe BWR
198 H-7 1,100MWe BWR
199 mm (a) a a a (a) (a)a
200 (a) (b) () (b)
201 mm No Yes 57.9MPam
202 (a) (b)
203 (a) 0.25m,0.5m (a) 0.25m,0.5m
204
205
206 J Rt J.1-2 kn kn (knm) Pa (1) (2) (1) (2)
207 J.1-3 MPa (MPa) (MPa) =2.3Sm E/1000 (MPa) SUS316L
208 V1 V2 V3 V4 V5 V6 V7 J.1-1 J.1-2
209 J.1-2 J.1-3 (a) (b) J.1-4
210 J.1.-5
211 J.1.-6
212
213
214
215 No Yes No Yes
216 a. b. J.2
217 0 2 3 J.2-3
218 (1) (2) (1) SCC (1) n/m 2 (a)0.2s/cmecp150mvshe (i) SUS304 da/dt K K57.9 (1) da/dt K3.4 (2) da/dt K57.9 (3) (ii) da/dt K K57.9 (4) da/dt K6.7 (5) da/dt K57.9 (6) da/dtmm/skmpam SCC J.3-1 (b)0.2s/cmecp200mvshe (i) SUS304 da/dt K K57.9 (7) da/dt K12.9 (8) da/dt K57.9 (9)
219 (ii) da/dt K K57.9 (10) da/dt K19.3 (11) da/dt K57.9 (12) da/dtmm/skmpam SCC J.3-2 (2) n/m 2 SUS304 da/dt= n 3.6 (CK 4 ) n (13) n C (i) n/m 2 C= (ii) n/m (n/m 2 ) C= ln() (iii) n/m 2 C= da/dtmm/skmpam (3) 182 SCC () da/dt K K50.3 (14) da/dt K13.3 (15) da/dt K50.3 (16) da/dtmm/skmpam 182 SCC J (1) (2)
220 (1) 3.6 J.3-4 (1) 3.2 ( a ) 3.3 K 3.5 (2) 3.4 SCC K t a (3) (4)
221 J-3-1 SCC
222 J-3-2 SCC
223 J SCC
224 J-3-4 SCC
225
226
227
228
229
230
231
232
233
234
235
236
237
238
239 SUS304 SUS316L
240
241
242 mm 70mm 60mm 1 80mm 1 110mm 2 120mm 2 SUSF316L GXM1 XM-19 NCF750 X-750 SUSF316L GXM1 XM-19 GXM1 XM-19 GXM1 NCF750 GXM1 XM-19 XM-19 X-750 NCF750 X-750 SUSF316L SUSF316 GXM1 F316 XM-19 GXM1 NCF750 NCF750 XM-19 X-750 X-750
243
244
245 1) 2) 3)
246 VT-3 MVT-1 MVT-1
247 X-750 SCC 1 SCC
248 1100MWe 93.7MPa MPa 120MPa 1190MPa
249 1100MWe 0 7Hz V 0.5msec V 0= 80mm r V r V f d MPa 147 MPa Hz Hz
250 IASCC IASCC 1100MWe DOT 3.5 E>1MeV 60 IASCC (n/m 2 )IASCC H2 H6a IASCC 60 IASCC n/m 2 s (n/m 2 ) (n/m 2 ) %
251 1100MWe V mm 1mm a/=0.1 V2 30MPa 45MPa V2 V2 SCC K E-5 5.3(1) A A G AG A G A G a 1 / 2 K p (1) / Q (1) A0,A1,A2,A3,Ap0x/a1x (2) K A0A3Ap AppAp0
252 A0A1(x/a)A2(x/a) 2 A3(x/a) 3 (2) G0,G1,G2,G3 E-5-1 E-5-2 Q (a/) 1.65 (3) SCC SCC 0.2S/cmECP150mVSHE da/dt K K57.9 (4) da/dt K6.7 (5) da/dt K57.9 (6) da/dtmm/skmpam 0.2S/cmECP200mVSHE da/dt K K57.9 (7) da/dt K19.3 (8) da/dt K57.9 (9) da/dtmm/skmpam K V2 K 7mm 33MPam (1) V2 K 6mm 26MPam 24mm 0 (2)
253 V2 K 11mm 38MPam (1) V2 K 7mm 27MPam 24mm 0 (2) SCC SCC 1.5 V2 NWC 50 80% 40mm HWC (1) NWC 60 40% 20mm HWC(2) 80% 40mm 20 V2 47mm 80% 80% ) 2004 JSME S NA1-2004
254 V2 a/=0.1 10mm a 1mm 50.8mm
255 V2
256 SCC
257 SCC
258 (1) V2 NWC () (2) V2 NWC ()
259 (2) V2 HWC () (2) V2 HWC ()
260 80% HWC NWC (1) (V2 ) () NWC 80% HWC (2) (V2 ) ()
261 V2 V2 (1) 1100MWe V2 V2 V2 (2) (3) (4) 11.6Jm sec
262 (5) V2
263 V2 (a) (b)
264 0 2 3
265 16mm 16mm
266 V2 V7 V2 V7 (1) (2) MPa (3) f 2.7SmSm SF SF3.0 SF1.5 (4) V2 V7
267 (5) t P Y 1 P Y RoRi Ro Ri a Roa P P f t Y 1 Ro a SF 1 Ri P a Ro Ri SFRi f ac a c P Ro Ri SFRi f 80% 40mmV2 V7 80% mm
268 t L a t Di Do L t Do Di a t
269 Q A B C D AC D [][] NM [][] N NM N M N + M100,1000, M M SCC 10 1
270 D M M B 2.2 AD 5 5 PY A C D B D A B YX D B D P Y=0.5 X B P D
271 4. 3
272 Q- AC
273 Q- D
274 Q-3
275 Q
276 0.124 Q Q
277 0.541 Q Q
278 0.924 Q
279 X=0.5 X0.5 X=0.5 Q-6
280
281
282
283 1mil0.025mm JEAG4207 Yes (%) (%) /(%) Yes / // No No Yes No No No No 50m 1mm 1) 2
284 SCC 20 6
285
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