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

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Figure A-15 Ratio of Top Half Significant Reaction Moments (Unbroadened Spectra) Figure A-16 Ratio of Top Half Significant Reaction Moments (Broadened Spectra) 153
NRC FORM 335 U.S. NUCLEAR REGULATORY COMMISSION (2-89) NRCM 1102, 3201, 3202 BIBLIOGRAPHIC DATA SHEET 2. TITLE AND SUBTITLE (See instructions on the reverse) Seismic Analysis of Large-Scale Piping Systems for the JNES/NUPEC Ultimate Strength Piping Test Program 5. AUTHOR(S) G. DeGrassi, J. Nie, C. Hofmayer 1. REPORT NUMBER (Assigned by NRC, Add Vol., Supp., Rev., and Addendum Numbers, if any.) NUREG/CR-6983 BNL-NUREG- 81548-2008 3. DATE REPORT PUBLISHED MONTH YEAR November 2008 4. FIN OR GRANT NUMBER JCN: N–6076 6. TYPE OF REPORT Technical 7. PERIOD COVERED (Inclusive Dates) 8. PERFORMING ORGANIZATION - NAME AND ADDRESS (if NRC, provide Division, Office or Region, U.S. Nuclear Regulatory Commission, and mailing address; if contractor, provide name and mailing address.) Energy Sciences & Technology Department Brookhaven National Laboratory Upton, NY 11973-5000 9. SPONSORING ORGANIZATION - NAME AND ADDRESS (if NRC, type “Same as above”; if contractor, provide NRC Division, Office or Region, U.S. Nuclear Regulatory Commission, and mailing address.) Division of Engineering Office of Nuclear Regulatory Research U.S. Nuclear Regulatory Research Washington DC 20555-0001 10. SUPPLEMENTARY NOTES S. Ali, NRC Project Manager. 11. ABSTRACT (200 words or less) The Japan Nuclear Energy Safety Organization/Nuclear Power Engineering Corporation (JNES/NUPEC) conducted a multi-year test program for the Ministry of Economy, Trade and Industry (METI) of Japan to investigate the behavior of typical Nuclear Power Plant (NPP) piping systems under large seismic loads. The objectives of this program were to develop a better understanding of the elasto-plastic response and ultimate strength of nuclear piping systems, to ascertain the seismic safety margins in current piping design codes, and to assess new code allowable stress rules. The test program consisted of a series of static and dynamic material tests, piping component tests, simplified piping system tests, and large-scale piping tests. As part of collaborative efforts between the United States and Japan on seismic issues, the U.S. Nuclear Regulatory Commission (NRC) and Brookhaven National Laboratory (BNL) participated in this program by performing both pre-test and post-test analysis for selected tests, and by evaluation of program results. A summary of the BNL analysis of the simplified piping system tests was documented in an earlier NUREG/CR report. This report describes the BNL post-test analyses of the large-scale piping system tests and discusses the insights gained from this program. 12 KEY WORDS/DESCRIPTORS (List words or phrases that will assist researchers in locating the report.) Seismic Analysis, seismic testing, piping design, ASME code evaluation, fatigue ratcheting, plasticity, kinematic hardening, fatigue failure. NRC FORM 335 (2-89) 13. AVAILABILITY STATEMENT unlimited 14. SECURITY CLASSIFICATION (This Page) unclassified (This Report) unclassified 15. NUMBER OF PAGES 16. PRICE
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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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Page 115 and 116: Figure 4-32 Displacement D4 Compari
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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
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Page 153 and 154: described in Sections 4 of this rep
Page 155 and 156: U.S. Nuclear Regulatory Commission,
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: Figure A-13 Ratio of Top Half Signi
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Seismic Analysis of Large-Scale Piping Systems for the JNES ... - NRC

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