면진장치를면진장치를 적용한적용한면진장치를면진장치를 적용한적용한국내국내 원전구조물의원전구조물의 예비지진해석예비지진해석(Preliminary Seismic Analysis of Korean Nuclear Power Plant Adapted Seismic Isolation System)
한국전력기술한국전력기술((주주))한국전력기술한국전력기술((주주))원원) ) 토목건축기술그룹토목건축기술그룹
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Contents
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2제17회 원자력안전기술정보회의 면진장치를 적용한 국내 원전구조물의 예비 지진해석
Introduction
1) Purpose of Study
2) Referencing Regulations and Guides
3제17회 원자력안전기술정보회의 면진장치를 적용한 국내 원전구조물의 예비 지진해석
1) Purpose of Study
• Export of Korean NPPs to high seismicity area– Increasing seismic demand because of world-wide big earthquake events– Target SSE of APR1400 is for third generation NPP
• Seismic Safety of NPP– After post-Fukushima event, various types of regulation and safety reviews
are being performed– One of the most effective tools to increase seismic safety margin
• Essential technical development scope of next generation NPP system• More enhanced standardization of NPP construction
4제17회 원자력안전기술정보회의 면진장치를 적용한 국내 원전구조물의 예비 지진해석
2) Referencing Regulations and Guides
• 10CFR– Part 50, App. S,
P t 52 S b t B– Part 52, Subpart B• US NRC, Regulatory Guides
– Reg. Guide 1.60 (Rev. 0), – Reg. Guide 1.61 (Rev. 1), – Reg. Guide 1.92 (Rev. 2), – Reg. Guide 1.208 (Rev. 0),
R G id 1 122 (R 1)– Reg. Guide 1.122 (Rev. 1)• SRP
– SRP 3.7.1 ~ 3.7.3• ISG: DC/COL-ISG-01, DC/COL-ISG-017• NUREG Report
– NUREG/CR-6728: Technical Basis for Revision of Regulatory Guidance on Design Ground Motions: Hazard- and Risk-consistent Ground Motion Spectra Guidelines
– Draft report , Technical Considerations for Seismic Isolation of Nuclear Facilities June 19 2012Facilities, June 19, 2012.
• European Utility Requirements for LWR Nuclear Power, 2.4.6
5제17회 원자력안전기술정보회의 면진장치를 적용한 국내 원전구조물의 예비 지진해석
Design Ground Motion
1) Design Ground Motion
2) Design Time Histories
6제17회 원자력안전기술정보회의 면진장치를 적용한 국내 원전구조물의 예비 지진해석
1) Design Ground Motion
• Two types of seismic input motion are considered.(1) US NRC requirements: high frequency reinforced RG 1 60 DRS(1) US NRC requirements: high frequency reinforced RG 1.60 DRS
(2) European Utility Requirements (EUR)
• HRHF for CEUS of US will be considered later• Reinforced RG1.60 DRS
– SSE value for the horizontal direction: 0.5g
– SSE DRS for vertical direction should be evaluated
– RG 1.60 spectra enhanced in high frequency from 9 Hz to 50 Hz
• Additional consideration on design ground motion for seismicAdditional consideration on design ground motion for seismic isolation is being studied
7제17회 원자력안전기술정보회의 면진장치를 적용한 국내 원전구조물의 예비 지진해석
1) Design Ground Motion (cont’d)
Horizontal Spectral Amplifications at high frequency range of RG 1.60 Spectrum (5% Damping)p p g q y g p ( p g)
8제17회 원자력안전기술정보회의 면진장치를 적용한 국내 원전구조물의 예비 지진해석
1) Design Ground Motion (cont’d)
• DRS for European sites European Utility Requirements for LWR Nuclear Power Plants 2 4 6– European Utility Requirements for LWR Nuclear Power Plants, 2.4.6
– SSE value for the horizontal direction: 0.5g
– SSE DRS for the vertical direction: 2/3 of SSE DRS for horizontal dir.
EUR Design Basis Ground Motion Spectra (horizontal 5% anchored to 0 5g)EUR Design Basis Ground Motion Spectra (horizontal, 5%, anchored to 0.5g)
9제17회 원자력안전기술정보회의 면진장치를 적용한 국내 원전구조물의 예비 지진해석
2) Design Time Histories
• Reinforced RG 1.60 DRS- Modified THs are derived from real seed earthquake motionsq- THs are satisfied with the requirements of SRP 3.7.1, option 1,
approach 11
1.5
(g)
10
0 5 10 15 20 25
TIME (sec)
-1.5
-1
-0.5
0
0.5
ACCEL
ERATION (
1
cele
ratio
n (g
)
80
-40
0
40
80
VELO
CITY (in
ch/sec
)
Acc 0 5 10 15 20 25
TIME (sec)
-80
0
15
30
45
CEM
ENT (in
ch)
0.1 1 10 100
Frequency (Hz)
0.10 5 10 15 20 25
TIME (sec)
-45
-30
-15DISPL
ACE
Response Spectra of TH and Multi Acceleration Velocity and DisplacementResponse Spectra of TH and Multi-Damped DRS (Dir: NS, Damping: 2%, 3%, 4%, 5%, 7%, 10% anchored to 1.0g scale)
Acceleration, Velocity, and Displacement Plot of TH anchored to 1.0g scale)
10제17회 원자력안전기술정보회의 면진장치를 적용한 국내 원전구조물의 예비 지진해석
2) Design Time Histories (cont’d)
• DRS for European sites
(a) EUR-S1 (b) EUR-S3
Response spectra for 5% damping, and Synthetic Acceleration, Velocity, Displacement Time Historiesfor EUR Soft DGRS
11제17회 원자력안전기술정보회의 면진장치를 적용한 국내 원전구조물의 예비 지진해석
Generic Soil Profiles
1) Reinforced RG 1.60 DRS
2) EUR DRS
12제17회 원자력안전기술정보회의 면진장치를 적용한 국내 원전구조물의 예비 지진해석
1) Reinforced RG 1.60 DRS
• Generic soil profiles– Nine layered profiles and one fixed base condition– Nine layered profiles and one fixed base condition
• Site layer depth to bedrock– 55 ft (Embedment depth of NI) ~ 1,000 ft55 ft (Embedment depth of NI) 1,000 ft
Generic Soil Profiles for the APR1400 Standard Design
13제17회 원자력안전기술정보회의 면진장치를 적용한 국내 원전구조물의 예비 지진해석
1) Reinforced RG 1.60 DRS
• Horizontal Fundamental Site Frequencies for Generic Soil ProfilesProfiles
14
ProfileFreq.
8
10
12
y (Hz)
Profile
S1
S2
S3
(Hz)
1.22
1.61
2.25
4
6
8
Freq
uency S3
S4
S7
S8
S5
2.25
4.61
6.08
6.84
9 62
0
2
S1 S2 S3 S4 S7 S8 S5 S9 S6
S5
S9
S6
9.62
11.04
11.99
Profile Numbers
14제17회 원자력안전기술정보회의 면진장치를 적용한 국내 원전구조물의 예비 지진해석
1) Reinforced RG 1.60 DRS
• Layer Site Category– Categorized by layer thickness and depth range to bedrock– Categorized by layer thickness and depth range to bedrock
Layer Site Category Layer Thickness and Depth Range (ft)
A 0 ~ 55
B 55 ~ 100
C 100 ~ 200
D 200 ~ 500
E 500 1 000E 500 ~ 1,000
F Halfspace > 1,000
15제17회 원자력안전기술정보회의 면진장치를 적용한 국내 원전구조물의 예비 지진해석
2) EUR DRS
• Generic soil profiles– Nine typical sites are identified, three in each site categoryyp , g y
– Uniform half-space with single shear wave velocity value
16제17회 원자력안전기술정보회의 면진장치를 적용한 국내 원전구조물의 예비 지진해석
SSI Analysis
1) Modeling
2) Soil-Structure Interaction Analysis
3) Preliminary Seismic Analysis Results
17제17회 원자력안전기술정보회의 면진장치를 적용한 국내 원전구조물의 예비 지진해석
1) Modeling
• Characteristics of NI StructureCommon basemat is shared by RCB and AB– Common basemat is shared by RCB and AB.
– RCB and AB structures are separated above basemat.
– RCB consists of Prestressed Concrete Containment Vessel (PCCV)– RCB consists of Prestressed Concrete Containment Vessel (PCCV) and Containment Internal Structure (CIS).
– Reactor Coolant System (RCS) is incorporated into the CIS.
18제17회 원자력안전기술정보회의 면진장치를 적용한 국내 원전구조물의 예비 지진해석
1) Modeling (cont’d)
• Development of Model(1) Lumped mass beam stick model(1) Lumped mass beam stick model
• Reference model: Shinkori units 3&4
• Rev. B: real numbers of bearing design is implemented to Rev. A modelRev. B: real numbers of bearing design is implemented to Rev. A model
NI MAT• Element : Soild• Material : Conc
Moat & SI Device• Element : Soild & beam• Material : Conc
RCBRCB• Element : Beam • Lumped mass
AUXAUX• Element : Beam • Lumped mass
19제17회 원자력안전기술정보회의 면진장치를 적용한 국내 원전구조물의 예비 지진해석
1) Modeling (cont’d)
• Development of Model(1) Three-dimensional finite element model(1) Three-dimensional finite element model
• Rev. A: it will be developed referencing up-to-date APR1400 model
Reactor Containment Shell
Containment Internal Structure
Auxiliary BuildingShell Structure
20제17회 원자력안전기술정보회의 면진장치를 적용한 국내 원전구조물의 예비 지진해석
2) Soil-Structure Interaction Analysis
Frequency Domain Analysis
Time Domain Analysis
Multi‐Step Analysis
SASSIKIESSI
SASSI + SAP2000SASSI + ANSYS
KIESSI + LS DYNA
PSD analysisSAP2000ESSI
:KIESSI + LS‐DYNA
:ANSYS, LS‐DYNA
:
21제17회 원자력안전기술정보회의 면진장치를 적용한 국내 원전구조물의 예비 지진해석
3) Preliminary Seismic Analysis Results (cont’d)
A. Seismic analysis using LRB SIs
Analysis program: SASSI– Analysis program: SASSI
– Device information:
• LRB type made by Unison Etech
• Diameter: 110cm
• Modeling: beam element using equivalent linear stiffness
– Natural frequency of SI device
Freq.(Hz) Period(sec) DOF
1 0 515 1 939 Horizontal EW1 0.515 1.939 Horizontal EW
2 0.515 1.940 Horizontal NS
3 0.555 1.802 Torsion
22제17회 원자력안전기술정보회의 면진장치를 적용한 국내 원전구조물의 예비 지진해석
3) Preliminary Seismic Analysis Results (cont’d)
A. Seismic analysis using LRB SIs (cont’d)
Model verification– Model verification
• Seismic Input motion: EUR (EW comp), 0.5g
• Assumed as rigid foundation and embedment effects are neglected
• Verification: FRS comparisons from SAP2000 and SASSIEL. 333 ft
EL. 55 ft
23제17회 원자력안전기술정보회의 면진장치를 적용한 국내 원전구조물의 예비 지진해석
3) Preliminary Seismic Analysis Results (cont’d)
A. Seismic analysis using LRB SIs (cont’d)
FRS for EUR DRS– FRS for EUR DRS
• Seismic input: 0.5g
• Location: ACB
< EW dir> < NS dir> < VT-dir>< EW-dir> < NS-dir> < VT-dir>
24제17회 원자력안전기술정보회의 면진장치를 적용한 국내 원전구조물의 예비 지진해석
3) Preliminary Seismic Analysis Results (cont’d)
A. Seismic analysis using LRB SIs (cont’d)
Relative displacement for EUR DRS– Relative displacement for EUR DRS
STR. EL. EW(in) NS(in) VT(in) EW(cm) NS(cm) VT(cm)
AUX 100' 5.22 4.01 0.08 13.25 10.18 0.21 120' 5.23 4.02 0.08 13.29 10.21 0.21
137'-6" 5.24 4.03 0.08 13.32 10.24 0.21 156" 5.24 4.03 0.08 13.32 10.24 0.21
RCB 78' 5.17 3.98 0.04 13.13 10.12 0.09 100' 5.18 4.01 0.04 13.16 10.18 0.09
136'-6" 5.21 4.03 0.05 13.22 10.24 0.12 156' 5.23 4.04 0.06 13.29 10.27 0.15 218' 5.28 4.10 0.10 13.41 10.42 0.24
333'-3' 5.35 4.18 0.16 13.59 10.60 0.40 PSW 78' 5.17 3.98 0.04 13.13 10.12 0.09
100' 5.17 4.00 0.04 13.13 10.15 0.09 156' 5.20 4.02 0.04 13.19 10.21 0.09 191' 5.22 4.04 0.04 13.25 10.27 0.09
SSW 78' 5.17 3.98 0.04 13.13 10.12 0.09 100' 5.17 4.00 0.04 13.13 10.15 0.09 156' 5.20 4.01 0.04 13.19 10.18 0.09 191' 21 02 0 0 13 22 10 21 0 09191' 5.21 4.02 0.04 13.22 10.21 0.09
25제17회 원자력안전기술정보회의 면진장치를 적용한 국내 원전구조물의 예비 지진해석
3) Preliminary Seismic Analysis Results (cont’d)
A. Seismic analysis using LRB SIs (cont’d)
FRS for Reinforced RG1 60 DRS– FRS for Reinforced RG1.60 DRS
• Seismic input: 0.5g
• Location: ACB
< EW-dir> < NS-dir> < VT-dir>< EW-dir> < NS dir> VT dir
26제17회 원자력안전기술정보회의 면진장치를 적용한 국내 원전구조물의 예비 지진해석
3) Preliminary Seismic Analysis Results (cont’d)
A. Seismic analysis using LRB SIs (cont’d)
Relative displacement for Reinforced RG1 60 DRS– Relative displacement for Reinforced RG1.60 DRS
STR. EL. EW(in) NS(in) VT(in) EW(cm) NS(cm) VT(cm)
AUX 100' 10.96 12.61 0.11 27.83 32.02 0.28 120' 10.97 12.62 0.11 27.86 32.06 0.29
137'-6" 10.98 12.65 0.11 27.90 32.11 0.29 156" 10.99 12.67 0.12 27.91 32.18 0.29
RCB 78' 10.87 12.52 0.06 27.62 31.80 0.14 100' 10.91 12.55 0.07 27.71 31.88 0.17
136'-6" 10.93 12.61 0.08 27.77 32.04 0.20 156' 10.98 12.66 0.10 27.89 32.15 0.25 218' 11.08 12.79 0.14 28.14 32.51 0.37
333'-3' 11.30 13.02 0.23 28.70 33.08 0.58 PSW 78' 10.87 12.52 0.06 27.62 31.80 0.14
100' 10.88 12.53 0.06 27.65 31.82 0.14 156' 10.92 12.61 0.06 27.74 32.02 0.16 191' 10.94 12.67 0.06 27.80 32.18 0.16
SSW 78' 10.87 12.52 0.06 27.62 31.80 0.14 100' 10.88 12.53 0.06 27.65 31.82 0.14 156' 10.92 12.56 0.06 27.72 31.92 0.14 191' 10.93 12.60 0.06 27.77 32.02 0.16
27제17회 원자력안전기술정보회의 면진장치를 적용한 국내 원전구조물의 예비 지진해석
3) Preliminary Seismic Analysis Results (cont’d)
B. Seismic analysis using Friction type SIs
Analysis program: SASSI– Analysis program: SASSI
– Device information:
• Friction type: EQS by Esco RTS
• Capacity: 10,000 kN
• Modeling: beam element using equivalent linear stiffness
– Natural frequency of SI device
Freq.(Hz) Period(sec) DOF
1 1 086 0 921 Horizontal NS1 1.086 0.921 Horizontal NS
2 1.087 0.920 Horizontal EW
3 1.172 0.854 Torsion
28제17회 원자력안전기술정보회의 면진장치를 적용한 국내 원전구조물의 예비 지진해석
3) Preliminary Seismic Analysis Results (cont’d)
B. Seismic analysis using Friction type SIs (cont’d)
Model verification– Model verification
• Seismic Input motion: Reinf. RG1.60 DRS (all comp), 0.5g
• Assumed as rigid foundation and embedment effects are neglected
• Verification: FRS comparisons from SAP2000 and SASSI
< EW-dir> < NS-dir>
29제17회 원자력안전기술정보회의 면진장치를 적용한 국내 원전구조물의 예비 지진해석
3) Preliminary Seismic Analysis Results (cont’d)
B. Seismic analysis using Friction type SIs (cont’d)
FRS for EUR DRS– FRS for EUR DRS
• Seismic input: 0.5g
• Location: ACB
< EW dir> < NS dir> < VT-dir>< EW-dir> < NS-dir> < VT-dir>
30제17회 원자력안전기술정보회의 면진장치를 적용한 국내 원전구조물의 예비 지진해석
3) Preliminary Seismic Analysis Results (cont’d)
B. Seismic analysis using Friction type SIs (cont’d)
Relative displacement for EUR DRS– Relative displacement for EUR DRS
STR. EL. EW(in) NS(in) VT(in) EW(cm) NS(cm) VT(cm)
AUX 100' 2.28 2.99 0.03 5.79 7.60 0.08 120' 2.31 3.03 0.04 5.85 7.70 0.09
137'-6" 2.32 3.06 0.04 5.90 7.77 0.10 156" 2.34 3.09 0.04 5.95 7.83 0.11
RCB 78' 2.23 2.93 0.01 5.66 7.45 0.01 100' 2.27 3.00 0.01 5.77 7.61 0.03
136'-6" 2.36 3.11 0.02 5.98 7.90 0.06 156' 2.41 3.17 0.03 6.11 8.06 0.07 218' 2.58 3.38 0.04 6.54 8.59 0.11
333'-3' 2.85 3.72 0.07 7.23 9.45 0.18 PSW 78' 2.23 2.93 0.01 5.66 7.45 0.01
100' 2.25 2.97 0.01 5.71 7.53 0.02 156' 2.32 3.08 0.01 5.90 7.82 0.03 191' 2.37 3.15 0.01 6.01 8.00 0.03
SSW 78' 2.23 2.93 0.01 5.66 7.45 0.01 100' 2.25 2.97 0.01 5.71 7.53 0.02 156' 2.31 3.03 0.01 5.86 7.70 0.02 191' 2 3 3 08 0 01 9 82 0 02191' 2.35 3.08 0.01 5.95 7.82 0.02
31제17회 원자력안전기술정보회의 면진장치를 적용한 국내 원전구조물의 예비 지진해석
3) Preliminary Seismic Analysis Results (cont’d)
B. Seismic analysis using Friction type SIs (cont’d)
FRS for Reinforced RG1 60 DRS– FRS for Reinforced RG1.60 DRS
• Seismic input: 0.5g
• Location: ACB
< EW-dir> < NS-dir> < VT-dir>< EW-dir> < NS dir> VT dir
32제17회 원자력안전기술정보회의 면진장치를 적용한 국내 원전구조물의 예비 지진해석
3) Preliminary Seismic Analysis Results (cont’d)
B. Seismic analysis using Friction type SIs (cont’d)
Relative displacement for Reinforced RG1 60 DRS– Relative displacement for Reinforced RG1.60 DRS
STR. EL. EW(in) NS(in) VT(in) EW(cm) NS(cm) VT(cm)
AUX 100' 4.67 4.51 0.04 11.85 11.46 0.11 120' 4.69 4.54 0.05 11.92 11.53 0.14
137'-6" 4.71 4.56 0.06 11.97 11.58 0.15 156" 4.73 4.58 0.07 12.01 11.62 0.17
RCB 78' 4.56 4.43 0.01 11.58 11.25 0.02 100' 4.61 4.48 0.03 11.70 11.38 0.09
136'-6" 4.70 4.58 0.07 11.94 11.63 0.18 156' 4.76 4.63 0.09 12.08 11.77 0.22 218' 4.92 4.81 0.14 12.50 12.21 0.34
333'-3' 5.18 5.08 0.22 13.14 12.91 0.55 PSW 78' 4.56 4.43 0.01 11.58 11.25 0.02
100' 4.58 4.44 0.01 11.62 11.29 0.03 156' 4.63 4.53 0.02 11.76 11.51 0.06 191' 4.66 4.59 0.02 11.84 11.66 0.06
SSW 78' 4.56 4.43 0.01 11.58 11.25 0.02 100' 4.58 4.44 0.01 11.62 11.29 0.03 156' 4.62 4.49 0.02 11.74 11.40 0.05 191' 4.65 4.51 0.02 11.80 11.45 0.05
33제17회 원자력안전기술정보회의 면진장치를 적용한 국내 원전구조물의 예비 지진해석
Summary and Future Plan
• Preliminary seismic analysis results are obtained through the
conventional FD seismic analysis methodconventional FD seismic analysis method
• Dominant seismic input motion set has been confirmed
R i d i i i t ti ill b d l d f th id ti f• Revised seismic input motion will be developed for the consideration of
seismic isolation system
S i i l i lt ill b ff t d b b i f i t• Seismic analysis results will be affected by bearing frequency, input
motions, seismic model, computer program, and analysis methods
S i i l i lt ill b d d ifi d th h l i• Seismic analysis results will be compared and verified through analysis
methods and research institutions