Seismic Analysis of Large-Scale Piping Systems for the JNES ... - NRC

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6 REFERENCES American Society of Mechanical Engineers (1986). “ASME boiler and pressure vessel code, code case N-411-1, alternative damping values for response spectra analysis of class 1, 2, and 3 piping,” Section III, Division 1, New York, NY. Approved February 20, 1986, Annulled May 5, 2000. American Society of Mechanical Engineers (2004). “Dynamic analysis methods,” Boiler and Pressure Vessel Code, 2004 Edition, Section III, Division 1, Non-Mandatory Appendix N, New York, NY. ANSYS (2007). “Release 11.0 documentation for ANSYS,” Online Manual, ANSYS, Inc. Armstrong, P.J. and Frederick, C.O. (1966). “A mathematical representation of the multiaxial bauschinger effect,” CEGB Report No. RD/B/N 731. Bari, S. and Hassan, T. (2000) “Anatomy of Coupled Constitutive Models for Ratcheting Simulations,” International Journal of Plasticity, Vol. 16, pp. 381-409. Besseling, J.F. (1958). “A theory of elastic, plastic and creep deformations of an initially isotropic material,” Journal of Applied Mechanics, Vol. 25, pp. 529-536. Borsoi, L. and Ricard, A. (1985). “A simple accelerogram correction method to prevent unrealistic displacement shift,” 8th SMIRT, Vol.K(a), Paper K2/7, Brussels. Chaboche, J.L. (1986). “Time independent constitutive theories for cyclic plasticity,” International Journal of Plasticity, Vol. 2, pp. 149-188. DeGrassi, G. and Hofmayer, C. (2005). “Seismic analysis of simplified piping systems for the NUPEC ultimate strength piping test program,” NUREG/CR-6889, by Brookhaven National Laboratory for the US Nuclear Regulatory Commission, December, 2005. Downing, S.D. and Socie, D.F. (1982). “Simplified rainflow counting algorithms,” International Journal of Fatigue, 4 (1), pp. 31-40. Hadjian, A.H. (1988). “Piping system damping evaluation,” EPRI NP-6035, Electric Power Research Institute, Palo Alto, California. JNES (2003). “Ultimate strength piping test program – large scale piping system tests and analysis”, Status Report, June, 2003. Matsuishi, M. and Endo, T. (1968). “Fatigue of metals subjected to varying stress,” paper presented to Japan Society of Mechanical Engineers, Fukuoka, Japan. Nie, J., Xu J., and Costantino, C. (2007). “P-CARES: probabilistic computer analysis for rapid evaluation of structures,” NUREG/CR-6922, by Brookhaven National Laboratory for the US Nuclear Regulatory Commission, January, 2007. Prager, W. (1956). “A new method of analyzing stresses and strains in work hardening plastic solids,” Journal of Applied Mechanics, Vol. 23, pp. 493-496. Suzuki, K., et al. (2001). “Seismic proving test of ultimate piping strength,” ICONE-9, Paper No. 155. Suzuki, K., et al. (2002). “Seismic proving test of ultimate piping strength,” ICONE-10, Paper No. 22225. U.S. Nuclear Regulatory Commission, Regulatory Guide 1.61 [1973]. “Damping values for seismic design of nuclear power plants,” Revision 0, NRC, Washington D.C., October, 1973. U.S. Nuclear Regulatory Commission, Regulatory Guide 1.61 [2007]. “Damping values for seismic design of nuclear power plants,” Revision 1, NRC, Washington D.C., March, 2007. 141
U.S. Nuclear Regulatory Commission, Regulatory Guide 1.92 [2006]. “Combining model responses and spatial components in seismic response analysis,” Revision 2, NRC, Washington D.C., July, 2006. U.S. Nuclear Regulatory Commission, Regulatory Guide 1.122 [2006]. “Development of floor design response spectra for seismic design of floor-supported equipment or components,” Revision 1, NRC, Washington D.C., February, 1978. Ware, A.G. (1991). “The history of allowable damping values for U.S. nuclear plant piping,” Transactions of the ASME, Vol 113, 284-290. 142
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NUREG/CR-6983 BNL-NUREG-81548-2008
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Seismic Analysis of Large-Scale Pip
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FOREWORD This report documents the
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Figure 2-7 Model B Simplified Pipin
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Figure 4-64 Acceleration A2 Compari
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In the final phase of the test prog
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Continued investigation of the subj
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1 INTRODUCTION Prior to the establi
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2 DESCRIPTION OF JNES/NUPEC TEST PR
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Photographs of the DM Test Piping a
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Design Method Confirmation Test Ult
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Stress (N/mm 2 ) Figure 2-1 Monoton
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Hoop Strain (%) 18 16 14 12 10 8 6
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φ76.3 7.8 1500 Variable Hanger Sma
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Figure 2-9 Overview of Design Metho
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Figure 2-11 DM Test Nozzle 17
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Figure 2-13 DM Test Spring Hanger 1
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Figure 2-15 DM Test Accelerometer L
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Figure 2-17 DM Test Strain Gage Loc
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Figure 2-19 US Test Piping System S
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Figure 2-21 US Test Elbow 2 and Add
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Figure 2-23 US Test Accelerometer L
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Figure 2-25 US Test Strain Gage Loc
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Displacem ent(m m ) S train(%) 100
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Figure 2-30 US Test Elbow 2 Fatigue
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3 BNL LINEAR ANALYSES AND CODE EVAL
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where: PD 2t D + 0S m (3-4) 2I 0 0
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limits and specified that stresses
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Regulatory Guide 1.61 Revision 0 da
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Code Edition 1993 1993 Table 3-3 DM
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Figure 3-1 Design Method Confirmati
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Acceleration (g) Acceleration (g) 1
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Acceleration (g) 16 14 12 10 8 6 4
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g, and 0.471 g respectively in the
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A simple approach has been taken in
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so as not to prevent ANSYS from fin
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are made with time histories and Fo
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DM4-2(2) (Restart): This analysis c
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The only responses obtained from th
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elements. The final hoop (plastic)
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are somewhat smaller than but in an
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difference in the residual displace
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esponse for the entire time histori
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Figure 4-1 Horizontal and Vertical
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Figure 4-7 Comparison of Baseline-c
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Stress(MPa) Stress (MPa) 600 500 40
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Hoop and Axial Strain (%) 17 16 15
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Figure 4-16 Displacement D2 Compari
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Figure 4-18 Acceleration A2 Compari
Page 103 and 104: Figure 4-20 Displacement D4 Compari
Page 107 and 108: Figure 4-24 Acceleration A2 Compari
Page 121 and 122: Figure 4-39 Relative Deformation Hi
Page 129 and 130: Figure 4-47 Strain Ratcheting Compa
Page 141 and 142: Figure 4-60 Horizontal Input Motion
Page 153: described in Sections 4 of this rep
Page 157 and 158: nominal dimensions for the straight
Page 159 and 160: Figure A-1 Original and Modified Re
Page 161 and 162: Figure A-5 Ratio of Reaction Forces
Page 163 and 164: Figure A-9 Ratio of Reaction Force
Page 165 and 166: Figure A-13 Ratio of Top Half Signi
Page 167: NRC FORM 335 U.S. NUCLEAR REGULATOR
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