Study on Relationship between Aging and Thermal-Hydraulic Behaviors of Nuclear Power Plants
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1 海上技術安全研究所報告第 5 巻第 2 号 ( 平成 17 年度 ) 総合報告 1 Study on Relationship between Aging and Thermal-Hydraulic Behaviors of Nuclear Power Plants by Hiroyuki MURATA, Fujio INASAKA, Masaki ADACHI, Ken-ichi SAWADA, Shigeru AKIYAMA, Masaaki SAKUMA, Ichihiko TAKAHASHI, and Michio USHIJIMA Abstract The number of aged nuclear power plants will increase in the future, because operation periods of the existing nuclear power plants are being extended from thirty years of initial supposition to sixty years at the longest. Therefore, it is important to establish the methodology to guarantee integrity of the aged nuclear power plants. Among the reported damages of nuclear power plant components due to the fatigue during long terms, many cases are considered to be related to their thermal-hydraulic behaviors during operation. Thus, quantitative understanding of thermal-hydraulic behaviors in the nuclear power plants is important to estimate many kinds of aging processes accurately. The research project, "study on relationship between nuclear power plant aging and its thermal-hydraulic behaviors", was conducted from 2001 to 2004 in order to clarify effects of thermalhydraulic behaviors in the nuclear power plants on structural materials during aging processes. In this project, flow induced vibration of an array of circular cylinders was investigated experimentally and numerically. Rotating bending fatigue tests were also performed for the austenitic stainless steel SUS316L (JIS G4304) and Ni-Cr-Fe alloy NCF690 (JIS G4904, INCONEL alloy 690 equivalent material) in order to examine the fatigue strength in the ultra high cycle fatigue region, namely cycles, and the notch effects (113)
2 2 It was found that the reduced flow velocity at which the flow induced vibration of a single rod occurs in transverse direction decreases with the increase of the blockage ratio. When plural rods are inserted in the channel, the pitch has an effect on the behavior of the vibrating rods and its influence becomes remarkable as the blockage ratio decreases. As for fatigue test results in the ultra high cycle fatigue region, it turned out that the fatigue limit of SUS316L is 279 MPa and that of NCF690 ranges from 320 to 400 MPa. () () SUS316L 13 NCF SUS316L 16 NCF Cnm [m] [mm] i [m] [Hz] s [Hz] [Hz] 0.20 [m] 0.19 [m] [kg/m] [cycles] [m] PD( PD( Re/ Sts/U [sec] [m/sec] Uc [m/sec] Vrc/ [m] w(l,t) [m] [m] m [m] [m] m [m 2 /sec] [mm] [kg/m ]. [MPa] [MPa] [MPa] [m] [m] nrw 25mm wd 50mm 1 2 (114)
3 海上技術安全研究所報告第 5 巻第 2 号 ( 平成 17 年度 ) 総合報告 ) SUS316LNCF690.. (115)
4 4 915mm 565mm. mm Flow mm mm m m m m 25mm 50mm200mm 13.7mmi9.22 mm 190mm mm / 25mm mm mm : Hz Cnm 7 Cn4.4 7) w(l,t) m 2 2 ml w ( L, t ) [cosh 2 1 cos 1 d i 1 K {sinh 1 sin 1 }] 1x {cosh L 1x K (sinh L x cos L m 1 m m 1x sin L m )} (1) K [cosh 1 cos1 ] [sinh 1 sin 1 ] mm (116)
5 海上技術安全研究所報告第 5 巻第 2 号 ( 平成 17 年度 ) 総合報告 khz. : c 0 rc/0 Cn4.4 / /. C n Vr x d/w=0.548 d/w=0.274 y x Vr / / y (117)
6 6 / / Hz 141.6Hz Hz X wd d/w =0.274, Vr=2.47 d/w =0.548, Vr=2.41 X nrw Hz P ( ) D y P ( ) D x Hz P ( ) D y P ( ) D x Hz f(hz) Y 1 f s V r (1 ) (2) dl WH S t f / St 0.44 /0.51 St /0.274 / St0.232 / mm/ mm/0.274 (118)
7 海上技術安全研究所報告第 5 巻第 2 号 ( 平成 17 年度 ) 総合報告 7. /./ / p=5.84 p=4.38 p=2.92 p=1.46 Single Rod Vr. / / / / y,1 y,2 /1.46 /2.92. /5.84 / /3.8 / 3.8 X 2 d/w=0.548, p=2.92, Vr=2.22 X 1 X 2 d/w=0.548, p=1.46, Vr=2.23 X 1 /2.92/1.46 Y Y (119)
8 8 /2.92. / / / / /0.548 /0.548 d/w=0.548, p=2.92 Y y y x x d/w =0.548, p=2.92, Vr=2.32 Vr X d/w =0.548, p=1.46 y y Y x x d/w=0.548, p=1.46, Vr=2.31 Vr X /2.92/ /2.92/1.46 (120)
9 海上技術安全研究所報告第 5 巻第 2 号 ( 平成 17 年度 ) 総合報告 9 / / / 1.46 / / p=5.84 p=4.38 p=2.92 p=1.46 Single Rod Vr y,1 y,2 / 4.38 / X 2 d/w =0.274, p=2.92, Vr=2.46 X 1 X 2 d/w =0.274, p=1.46, Vr=2.45 X 1 /2.92/1.46 Y Y (121)
10 10 /0.274 /1.46 /2.92 /.13 /1.46 d/w=0.274, p=1.46 y x Vr /1.46 d/w=0.274, p=1.46 y,2 x,2 Vr x x,2 y y,2 y d/w=0.274, p=2.92 x Vr / / / /2.92 x y (122)
11 海上技術安全研究所報告第 5 巻第 2 号 ( 平成 17 年度 ) 総合報告 11 25/0.548 / PHOENICS FINAS 10-4 sec PHOENICS Moving Navier-Stokes PHOENICS 2 d y dy m c ky F 2 dt dt (3) 16 (123)
12 12 17 : PHOENICS Moving BFC Y d/w=0.548, p=1.46, Vr=2.30 X PHOENICS / /0.274 : (124)
13 海上技術安全研究所報告第 5 巻第 2 号 ( 平成 17 年度 ) 総合報告 /0.548 /0.274 / /1.46 /2.92 PHOENICS FINAS SUS316L(JIS G4304) 690 NCF690(JIS G4904) SUS316 SUS316 (125)
14 14 (126)
15 海上技術安全研究所報告第 5 巻第 2 号 ( 平成 17 年度 ) 総合報告 NCF690 SUS316LJIS G NCF690JIS G4904 Kt Kt 10 SUS316L SEM Kt Kt Kt Kt SUS316L (127)
16 16. H7 279MPa Kt Kt Kt MPa Kt MPa 100Nm 3,400rpm 200V400W Kt SUS316L NCF690 3,400rpm 3,000rpm50Hz (cycles) SUS316L NCF690 MPa 398MPa 1.1x MPa 10 9 Kt NCF690 Kt MPa SUS316L NCF690 (128)
17 海上技術安全研究所報告第 5 巻第 2 号 ( 平成 17 年度 ) 総合報告 17 SUS316L SUS316L (129)
18 18 No.S-A-1 (a =318MPa, Nf =13,700cycles) No.S-A-2 (a =298MPa, Nf =35,700cycles) No.S-A-3 (a =279MPa, Nf =2,523,100cycles) No.S-B-1 (a =328MPa, Nf =32,900cycles) No.S-B-2 (a =308MPa, Nf =75,600cycles) No.S-B-3 (a =318MPa, Nf =127,700cycles) SUS316L (130)
19 海上技術安全研究所報告第 5 巻第 2 号 ( 平成 17 年度 ) 総合報告 19 No.S-B-4 (a =298MPa, Nf =150,900cycles) No.S-B-5 (a =279MPa, Nf =273,000cycles) No.S-C-1 (a =308MPa, Nf =13,100cycles) No.S-C-2 (a =279MPa, Nf =75,900cycles) No.S-C-3 No.S-C-4 (a =259MPa, Nf =144,900cycles) (a =219MPa, Nf =232,600cycles) SUS316L (131)
20 20 No.S-C-5 (a =239MPa, Nf =274,400cycles) No.S-C-6 (a =199MPa, Nf =963,500cycles) No.S-C-7 (a =179MPa, Nf =203,004,700cycles) SUS316L NCF690 (132)
21 海上技術安全研究所報告第 5 巻第 2 号 ( 平成 17 年度 ) 総合報告 21 NCF690 No.I-A-2 (a =477MPa, Nf =46,300cycles) No.I-A-3 (a =458MPa, Nf =92,900cycles) No.I-A-4 No.I-A-5 (a =418MPa, Nf =173,400cycles) (a =398MPa, Nf =1,119,100cycles) NCF690 (133)
22 22 JIS SUS316L Kt 690 JIS NCF690 SUS316L 279MPa NCF MPa subete.jp/book/5syou.pdf(2003) pp (19993) JSME S pp pp (1982) pp pp pp No pp p pp pp p.163 (134)
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