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1 JANTI-SANE-03

2

3 WG

4 km 16km23km A, As , Ss Ss S 1-4,

5 30km 10km Google ZENRIN 1-1 As 1 A 1 B C *1:

6

7 Ss 1-4 6

8 H21. H21.6/19 Ss 1-5 7

9

10 2.1 AS AS ASME 2-1

11 AS ASME SCC JSME S NA Sy SuKIC

12 WG 6 2-3

13 2-4

14 2-5

15 3.1 WG

16 (JEAC4111) (JEAC4209) JIS JEC JEM JEAC JEAG4803 JEAG

17 (1) a. b. c. 3-3

18 (2) VT-3 JIS Z 3090 NDIS 3414 NDIS 3415 VT-2 JEAC4803 (3) NDIS 3413 JIS Z 2305 NDIS JIS Z (4) 3-4

19 3.2.7 WG (1) VT-1 (2) a. VT-1 b. c. (3) 3-5

20 (4) (5) 3-6

21 3-7

22 A 3-8

23 B C 3.4 WG 3 3-9

24 WG 3 WG WG 3-10

25

26 Ss

27 H21 Sm

28

29

30

31 (JEAG ) (1) (2) (3) (1) (2) (3) JEAC2008Draft, 2007ASME Sec. (,,)(H8H10

32 ) NUPEC (H10H15 ) EPRI/NRC Piping and Fitting Dynamic Reliability Program( ) FBR U92022,U94012,U95017(H4H7 ) i) ii) (P-) NUPEC H15 ii)i) 10 Ds S PFDRPNupec Ph.2 PD0 = B1 2t + B S 2 M Z ( ) ( ) 6Sm Ds Cs Ds 0.7

33

34

35

36 1 39 pp p

37

38

39 (1) (SUS316NG)

40 (2) (SFVQ1A) (3) pre/f0.2 (4) (SUS316NG)(SFVQ1A) (5) SUS316L 10% 20% SUS304TPSTS480STPT410 SFVC2BSS400 UFpre0.2 SUS316NG STS410SFVQ1A(300) LCF a kN L/C ε Taxis

41 d ε = Taxis 2 ln ( ) d 0 d 0 d ε Taxis b (300) (DFC) UFpre 0.2 UF pre = N / N f0 UF post = Nf / Nf0 ( N Nf Nf0 SUS316NGSFVQ1ASTS410 ( 300) UFpre0.2 DFC (UFpre)(UFUFpre UFpost) SUS316NGSFVQ1A STS410 ( 300) UF 1 (300) UF c SUS316NGSTS410SFVQ1A (300) (UF)

42

43 (a) R.T. (b) (SUS316NG)

44 (a) R.T. (b) (SFVQ1A)

45 (a) R.T. (b) (STS410)

46 (SUS316NG) (SFVQ1A).

47 (STS410) a ε Taxis ( ) (a) Case (b) Case (c) Case (d) Case b ε Nf SUS316NGSFVQ1ASTS410 Case 60 Case Torii 13

48 UF UF UFeq,1 = Nf / Nf0 + Dd ( ) Dd = εf' / εf0 ( Nf Nf0 0 εf' εf0 UFeq, SUS316NG SFVQ1ASTS410 UFeq,1 UF 1 c SUS316NGSTS410SFVQ1A φ16 R40 φ10 M20 P1.0 (4.8) (4.8) (mm)

49 ε ε(=2ε a ) ε ε 1 (=2ε a,1 ) dε m /dn ε 2 (=2ε a,2 ) dε m /dn N f N N 0 N (a) Case(b) Case ε ε 1 (=2ε a,1 ) ε ε 2 (=2ε a,2 ) dε m /dn ε(=2ε a ) N 0 N N (c) Case(d) Case ε SUS316NG

50 ε SFVQ1A ε STS410

51 ε (UFeq,1=Nf/Nf0+Dd) (SUS316NG)(SFVQ1A) STS410 (a) (300) (300) 0.2 (b)

52 (1) BWR (2) (3) A Vol. 72No pp (4) SUS316 A Vol. 73No pp (5) GCF (6) (7) Ogawa, et. al. Investigation of effect of Pre-Strain on Very High-Cycle Fatigue Strength of Austenitic Stainless Steels, Proceedings of the 16th Int. Conf. on Nuclear Engineering ICONE (2008 May) (8) Vol pp (9) (10) (11) Namaizawa, J., Ueno, K., Ishikawa, A., Asada, Y., Life Prediction Technique for Ratcheting Fatigue, ASME PVP-Vol.266, (1993), 3. (12),,,,,, 316FR, 2004 (1), No.04-1, (2004). (13) Torii, H., Takagi, Y., Tanaka, Y., Ogawa, T. and Komotori, J., Effect of Cumulative Pre-Strain on Low Cycle Fatigue Life of Stainless Steel, 1st Japan-China Joint Symposium on Fatigue of Engineering Materials and Structures, (2008).

53

54

55

56 JEAC4601 発生応力 (MPa) 許容応力(MPa) 図 4.4-3a 63 設計内圧負荷時の Mises 応力 内面 100 図 4.4-3b 設計内圧負荷時の Mises 応力 外面 4-32

57

58 4.4-

59

60 GL RCCV RPV

61 % ,000 t 116,000 t 76,600 t 7,300 t 5,300 t 2,000 t

62

63

64

65

66

67

68

69

70

71

72

73

74 τ cr = 0.31 σb ( 0.31 σb σv ) +

75

76

77

78

79 F F F F K 1 A c F c K1 Ac Fc

80

81

82

83

84

85 σx σy σx σy τ

86 RPV RPV Ss5 RPV RPV RPV RPV RPV RPV RPV 0.57

87 (a) NS (b) EW

88 RPV RPV

89 RPV

90

91 σx σy σx σy τ

92 RPV RPV (a) (b) Ss-1 (c) Ss-2 (d) Ss-3 (e) Ss-4 (f) Ss NS 5-34

93 (a) (b) Ss-1 (c) Ss-2 (d) Ss-3 (e) Ss-4 (f) Ss EW 5-35

94 (a) (b) Ss-1 (c) Ss-2 (d) Ss-3 (e) Ss-4 (f) Ss NS 5-36

95 (a) (b) Ss-1 (c) Ss-2 (d) Ss-3 (e) Ss-4 (f) Ss EW 5-37

96 (1) 55 7 (2) JEAG (3)

97 19 10 (4) JNES/SSD (5) ANSI/ANS , Nuclear Plant Response to an Earthquake, May, 2002 (6) ANSI/ANS , Criteria for the Handling and Initial Evaluation of Records from Nuclear Power Plant Seismic Instrumentation, April 2003 (7) RG1.166, Pre-Earthquake Planning and Immediate Nuclear Power Plant Operator Post earthquake Actions, USNRC, Mar (8) RG1.167, Restart of a Nuclear Power Plant Shut Down by a Seismic Event, USNRC, Mar (9) EPRI NP-6695, Guidelines for Nuclear Plant Response to an Earthquake, EPRI, Dec (10) IAEA Safety Report, Pre-Earthquake Planning and Post-Earthquake Actions for Existing Nuclear Power PlantsDRAFT Rev (11) IAEA Safety Standards, Evaluation of Seismic Safety for Existing Nuclear Installations, Safety Guide No. NS-G-2.13, (1) (1) () 2.2 S S S JEAG (2) JEAC Leroy Perry EPRI (9) NRC

98 (7),(8) ANSI/ANS (5),(6) IAEA EBPExtra-Budgetary Project IAEA

99 % 24 1 Damage Indicating ParametersCumulative Absolute Velocity

100 ()

101 30km 10km NPS : 100km NPS Google ZENRIN : : 10km NPS 30km 1 ( 2005) (cm/s) (s) [] (2006) 2 6-6

102 12 [] (20083) km 30km Gal(cm/s 2 ), ( ) Google ZENRIN 4 6-7

103

104

105 ,

106 A B C D () 6-11

107 C ) D D 6-12

108 1 2 3 A B C D

109 4 5 A B C D A B C D A A

110 B B C C B D D B

111 3 Ss Sd 4 8 ~

112

113

114 () 6

115

116 8

117

118

119

120 Y

121 S 48 3a 6b6c7b 7c

122 C S S C

123 S S ()

124 76 C 9

125 C D 9

126 PSA SMA(Seismic Margin Assessment) ) S B C S

127 () D

128

129 . (1) (2) 300 (3)

130 (4).2

131

132

133 WG WG WG WG WG WG WG WG WG WG WG WG WG WG

134

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