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JANTI-SANE-03

1. 1.1 197166.817km 16km23km 743 1-1 A, As 1-11-2, 1-3 3760 2981 79.3 1.2 189 Ss Ss S 1-4,5 1-2 1-1

30km 10km Google ZENRIN 1-1 As 1 A 1 B C *1: 2006 1-2

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3.2.2 3.2.3 (JEAC4111) (JEAC4209) JIS JEC JEM JEAC JEAG4803 JEAG4601 3.2.4 3-2

3.2.5 3.2.6 (1) a. b. c. 3-3

(2) -3.2-1 -3.2-1 VT-3 JIS Z 3090 NDIS 3414 NDIS 3415 VT-2 JEAC4803 (3) -3.2-2 -3.2-2 NDIS 3413 JIS Z 2305 NDIS 06012 JIS Z2305 2 (4) 3-4

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(JEAG4601-1987) (1) (2) (3) (1) (2) (3) JEAC2008Draft, 2007ASME Sec. (,,)(H8H10

) NUPEC (H10H15 ) EPRI/NRC Piping and Fitting Dynamic Reliability Program(19851992 ) 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

1 39 pp. 99-1082001 5 2 p. 3.1-2215 1 3 15 16 6

4.3.2-1 (1) (SUS316NG) 1.3 0.85

(2) (SFVQ1A) (3) pre/f0.2 (4) (SUS316NG)(SFVQ1A) (5) SUS316L 10% 20% SUS304TPSTS480STPT410 SFVC2BSS400 UFpre0.2 SUS316NG STS410SFVQ1A(300) LCF a 4.3.4-1 4.3.4-2 100kN L/C ε Taxis

d ε = Taxis 2 ln (4.3.4-1) d 0 d 0 d ε Taxis b 4.3.4-3 4.3.4-5 (300) (DFC) UFpre 0.2 UF pre = N / N f0 UF post = Nf / Nf0 (4.3.4-2 N Nf Nf0 SUS316NGSFVQ1ASTS410 ( 300) UFpre0.2 DFC (UFpre)(UFUFpre UFpost) 4.3.4-6 4.3.4-8 SUS316NGSFVQ1A STS410 ( 300) UF 1 (300) UF c SUS316NGSTS410SFVQ1A (300) (UF)

4.3.4-1 4.3.4-2

(a) R.T. (b) 300 4.3.4-3 (SUS316NG)

(a) R.T. (b) 300 4.3.4-4 (SFVQ1A)

(a) R.T. (b) 300 4.3.4-5 (STS410)

4.3.4-6 (SUS316NG) 4.3.4-7 (SFVQ1A).

4.3.4-8 (STS410) a 4.3.4-9 ε Taxis (4.3.4-1) 4.3.4-10 (a) Case (b) Case (c) Case (d) Case b ε Nf 4.3.4-11 4.3.4-13 SUS316NGSFVQ1ASTS410 Case 60 Case Torii 13

UF UF UFeq,1 = Nf / Nf0 + Dd (4.3.4-3) Dd = εf' / εf0 (4.3.4-4 Nf Nf0 0 εf' εf0 UFeq,1 4.3.4-14 SUS316NG SFVQ1ASTS410 UFeq,1 UF 1 c SUS316NGSTS410SFVQ1A φ16 R40 φ10 M20 P1.0 (4.8) (4.8) 35 2 2 35 114 4.3.4-9 (mm)

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 4.3.4-10 ε 4.3.4-11 SUS316NG

ε 4.3.4-12 SFVQ1A ε 4.3.4-13 STS410

ε 4.3.4-14 (UFeq,1=Nf/Nf0+Dd) (SUS316NG)(SFVQ1A) STS410 (a) (300) (300) 0.2 (b)

(1) BWR 62 4 5 3 (2) 6 7 3 (3) A Vol. 72No. 7232006pp. 1731-1736 (4) SUS316 A Vol. 73No. 731 2007 pp. 796-802 (5) GCF2 17 18 3 (6) 19 2007.11 (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 ICONE16-48811 (2008 May) (8) Vol. 1561985pp. 485-492 (9) 11 3 12 3 (10) 11 3 12 3. (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).

4.4-1 4.4-

JEAC4601 発生応力 (MPa) 許容応力(MPa) 80 100 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

4.4-4 4.4-5

4.4-

5.1.2-1 5.1.2-1

GL RCCV RPV 1 5.1.2-1

5.1.3 5.1.3-1 5.1.3-2 5.1.3-1 5.1.3-1 4% 5.1.3-1 193,000 t 116,000 t 76,600 t 7,300 t 5,300 t 2,000 t

5.1.3-1 21 1

5.1.3-2 21 1

τ cr = 0.31 σb ( 0.31 σb σv ) +

F 1.5 1.5 F 1.5 1.5 3 F 1.5 1.3 F 1.5 1.5 1.5 0.31 K 1 A c F c K1 Ac Fc

σx 2 2 + σy σx σy 2 + 3 τ

RPV RPV 5.4.4-1 Ss5 RPV 5.4.4-2 5.4.4-3 RPV RPV 5.4.4-4 RPV RPV 5.4.4-7 RPV RPV 0.57

(a) NS (b) EW 5.4.4-1 5.4.3-1

5.4.4-2 RPV 5.4.4-3 RPV

0 5.4.4-4 RPV

5.4.4-5 5.4.4-6

σx 2 2 + σy σx σy 2 + 3 τ

RPV RPV (a) (b) Ss-1 (c) Ss-2 (d) Ss-3 (e) Ss-4 (f) Ss-5 5.4.4-8 NS 5-34

(a) (b) Ss-1 (c) Ss-2 (d) Ss-3 (e) Ss-4 (f) Ss-5 5.4.4-9 EW 5-35

(a) (b) Ss-1 (c) Ss-2 (d) Ss-3 (e) Ss-4 (f) Ss-5 5.4.4-10 NS 5-36

(a) (b) Ss-1 (c) Ss-2 (d) Ss-3 (e) Ss-4 (f) Ss-5 5.4.4-11 EW 5-37

(1) 55 7 (2) JEAG 4601-1987 (3) 07-0001 18

19 10 (4) 07-0001 JNES/SSD07-001 20 1 (5) ANSI/ANS-2.23-2002, Nuclear Plant Response to an Earthquake, May, 2002 (6) ANSI/ANS-2.10-2003, 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. 1997 (8) RG1.167, Restart of a Nuclear Power Plant Shut Down by a Seismic Event, USNRC, Mar. 1997 (9) EPRI NP-6695, Guidelines for Nuclear Plant Response to an Earthquake, EPRI, Dec. 1989 (10) IAEA Safety Report, Pre-Earthquake Planning and Post-Earthquake Actions for Existing Nuclear Power PlantsDRAFT Rev 12.002010 1 (11) IAEA Safety Standards, Evaluation of Seismic Safety for Existing Nuclear Installations, Safety Guide No. NS-G-2.13, 2009 1978 6 1980 (1) (1) () 2.2 S S S JEAG4601-1987 (2) JEAC4601-2008 1986 1 Leroy Perry EPRI (9) NRC

(7),(8) ANSI/ANS (5),(6) IAEA 2007 9 EBPExtra-Budgetary Project 2005 2007 2007 IAEA 21 21 22 22

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