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TREE-NUREG-1136 for U.S. Nuclear Regulatory Commission
LOFT SYSTEM STRUCTURAL RESPONSE DURING SUBCOOLED BLOWDOWN
JOHN S. MARTINELL
January 1978
n ~~ EC311C3 Idaho, Inc.
!)S ,_I
q5o / IDAHO NATIONAL ENGINEERING LABORATORY
DEPARTMENT OF ENERGY 0
IDAHO OPERATIONS OFFICE UNDER CONTRACT EY-76-C-07-1570
DISTRIBUTION OE I.HtS O.OC.U.MEti"t IS UtiUMIIEO
DISCLAIMER
This report was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government nor any agency Thereof, nor any of their employees, makes any warranty, express or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or usefulness of any information, apparatus, product, or process disclosed, or represents that its use would not infringe privately owned rights. Reference herein to any specific commercial product, process, or service by trade name, trademark, manufacturer, or otherwise does not necessarily constitute or imply its endorsement, recommendation, or favoring by the United States Government or any agency thereof. The views and opinions of authors expressed herein do not necessarily state or reflect those of the United States Government or any agency thereof.
DISCLAIMER
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Pri nted in the United States of America Avai lahiP. from
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"The NRC will make available data tapes and operational computer codes on research programs deal ing with postulated loss-of-coolant accidents in light water reactors . Persons requesting this information must reimburse the NRC contractors for their expenses in preparing copies of the data tapes and the operational computer codes. Requests should be submitted to the Research Applications Branch , Office of Nuclear Regulatory Research, Nuclear Regulatory Commission , Washington , D.C. 20555."
NOTICE-------------,
This report was prepared as an account of work sponsored by the United States Government. Neither the the United States nor the Department of Energy, nor the Nuclear Regulatory Commission , nor any of their employees, nor any of their contractors, subcontractors, or their employees, makes any warranty, express or implied, or assumes any legal liability or responsibility for the accuracy, completeness or usefulness of any information , apparatus, product o r process disclosed, or represents that its use would not infringe privately owned rights.
LOFT SYSTEM STRUCTURAL RESPONSE
DURING SUBCOOLED SLOWDOWN
Approved:
L. P. Leach, Manager LOFT Experimental Program Division
N. C LOFT
,------NOTICE-------.
This report was prepared as an account of work sponsored by the United States Covemment. Neither the United States nor the United States Deputment of Energy, nor any of their employees, nor any of their contractors, subcontractors, or their employees, makes any warranty, express or impUed, or assumes any ltgaJ llabUJi>: or responstbll.tty lOr the accuracy, completeness or usefulness of any information, apparatus, product or process disclosed, or represents that its use would not infringe privately owned ri~Us.
DISTRIBUTION OE Il\IS Dl)CLIMENT 15 UNUMIT~
TREE-NUREG-1136
0
Distributed Under Category: NRC-2
Water Reactor Safety Research Systems Engineering
LOFT SYSTEM STRUCTURAL RESPONSE
DURING SUBCOOLED SLOWDOWN
By
John S. Martine11
EG&G Idaho, Inc.
January 1978
PREPARED FOR THE U.S. NUCLEAR REGULATORY COMMISSION
AND DEPARTMENT OF ENERGY
IDAHO OPERATIONS OFFICE UNDER CONTRACT NO. EY-76-C-07-1570
.ACKNOWLEDGMENTS
Appreciation is expressed to R. C. Guenzler, I. K. Hall, Jr.,
R. G. Rahl, V. T. Berta, L. D. Goodrich, and the personnel of the Loss
Of-Fluid Test .Oata Systems Branch·for their special help in. preparing
this document.
i i
ABSTRACT
The Loss-of-Fluid Test (LOFT) facility is a highly instrumented,
pressurized water reactor test system designed to be representative of
large pressurized water reactors (LPWRs) for the simulation of loss-of
coolant accidents (LOCAs). Detailed structural analysis and appropriate
instrumentation (accelerometers and strain gages) on the LOFT system
provided information for evaluation of the structural response of the
LOFT facility for loss-of-coolant experiment (LOCE) induced loads. In
general, the respbnse of the system during subcooled blowdown was small
with typical structural acceleratjons below 2.0 G's and dynamic strains
less than 150 x 10-6 m/m. The accelerations measured at the steam
generator and simulated steam generator flange exceeded LOCE design
values; however, integration of the accelerometer data at these
locations yielded displacements which were less than one half of the
design values associated with a safe shutdown earthquake (SSE), which
assures structural integrity for LOCE loads. ....
Use of the LOFT structural response data for reactor safety and
code qualification is not recommended due to the complexity. of the LOFT
system and to the problems associated with low amplitude data analysis.
The existing measurement system was adequate for evaluation of the LOFT
system response during the. LOCEs. The conditions affecting blowdown
loads during nuclear LOCEs will be nearly the same as those experienced
during the nonnuclear LOCEs, and the characteristics of the structural
response data in both types of experiments are expected· to be the same.
The LOFT system is concluded to be adequately designed and further
analysis of the LOFT system with structural codes is not required for
future LOCE experiments.
·I
iii
SUMMARY
The following subjects are addressed concerning the structural
response of the LOFT system during subcooled blowdown.
(1) The LOFT system ·structural response . relative to (a) the
experiment predictions and (b) the LOFT system design.
(2) The quality of the LOFT structural response data and applica
tions for reactor safety, code qualification, and LOFT
requal ification.
(3) The existing measurement system and recommendations for
repositioning and/or addition of new measurements.
(4) Projected changes in structural response data in nuclear LOCEs
relative to nonnuclear LOCEs.
(5) The need for additional analysis of the structural respon~~
data and/or LOFT system with structural codes.
The LOFT facility has been deiigned to r~prP.~sent: t,hP m~jnr
component and system thermal hydraulic responses of a LPWR during. a
LOCA. The test assembly includes five major subsystems which have been
extenstvely instrumented. so that ,desirable system parameters can be
measured and recorded during a LOCE. These subsystems were instrumented
for structural response. .measurements for purposes of assurance of the
adequacy of the LOFT structural design and requalification only. No
attempt was made to instrument for purposes of structunil t.:ullt:!
verification. The major subsystems include: (a) the reactor vessel,
(b) the primary coolant (intact) loop (c) the blowdown (broken) loop,
(d) the blowdown suppression system, and (e) the emergency core coolant
system.
iv
\
The Ll test series (nonnucl~ar blowdown tests) provided information
concerning equipment and system performance, structural adequacy, test
procedures, operator experience, and data for experimental verification
of thermal-hydraulic system behavior prior to nuclear blowdowns. In
particular, Experiments Ll-2, Ll-3, and Ll-3A were used.in this analysis
for addressing the subjects identified earlier. Structural response
data (accelerometer and strain gage data) in the intact and broken loops
and reactor vessel were reviewed and analyzed for comparison with
predicted and design values to evaluate the system response in these
areas. In general, the response of the system to LOCE loads· was small
rwith typical structural accelerations below 2.0 G and dynamic strains
less than 150 x 10-6 m/m. The measured accelerations from Experi
ment Ll-3A at the steam generator (AE-PC17-1 and AE-PC17-2) and the
simulated steam ~enerator flange (AE-BL2-l) exceeded the LOCE design
values. Quantification of the accelerometer data is highly subjective
since accuracy is poor due to the noise level in the measurements. A
more detailed analysis of the data at these locations (integration of
the acceleration plots) indicated that maximum deflections during sub
cooled blowdown were less than one half those associated with a safe
shutdown earthquake, assuring structural integrity for LOCE loads since
the system was designed for combined seismic and LOCA induced loads.
Due to the low magnitude of the LOFT structural response data, -quantification for direct comparison with predicted values is of
questionable value (strains only slightly larger than accuracy limits
and high noise level). Use of the data for reactor safety and code
qualification is not recommended due to the system complexity and the
problems involved in data reduction and evaluation. The LOFT data are
applicable for requalification purposes at LOFT but should not be relied
up~n solely, due to the problems associated with providing applicable
measurements at all points in the system (tees, welds, junctions, etc).
The requalification program will include a comprehensive inspection of
welds and components on intervals recommended by fatigue analysis. The
existing measurement system is deemed adequate for the purposes of
evaluating LOFT system structural response, and no recommendations for
repositioning or adding new measurements are ·made here. The data
v
associated with nuclear LOCEs should have the same characteristics as
the nonnuclear LOCE data since those conditions ~ffecting blowdown loads
are nearly the same in either case. Further analysis of the LOFT system
with structural codes for LOCE loads is deemed unnecessary.
The horizontal accelerations measured at the top of steam generator
(AE-PC17-l and -2) for ·nonnuclear LOCEs are two to three times the
values predicted by finite element analysis. This difference can, in
part, be explained by two techniques used in modeling the structure in
the area of the steam generator. First, the snubber supports as modeled
are loaded with any 1ncremental detlection, wh1le, 1n th~ phys1cal case,
a finite amount of displacement at the top o~ the steam generator 1s
required before the snubbers provide any restraint. Thus, low-amplitude
vibration can occur at· the top of the steam generator before lateral
restraint. occurs, for which the ·existing model can not account.
However, as the -amplitude of vibration increases, the modeled restraint
is a better representation of the physical restraint giving rise to
closer agreement between predicted and actual responses. Secondly, the
predicted accelerations are for the center of gravity of the steam
generator rather than at the top where the measurements were taken. Any
rotational motion about a horizontal axis would give rise to higher
acceleration at the top of the st~am g~nerator than pred1cted.
The acceleration measured in the east-west direction at the simu
lated steam generator flange (AE-BL2-l) exceeds the predicted LOCE value
by 17%. This difference is felt to .pe within· the allowable range of
accuracy associated with quantifying and comparing the measured data
with that predicted using finite element analysis.
Underprediction of the LOC~ accelerations at the steam generator
could give rise to questions concerning the predicted response for com
bined LOCA and seismic activity f.~r which the LOFT system is de~i_gned.
Review of the combined LOGA and seismic analysis of the mobile test
assembly reveals that response to those loads is two to three times as
severe as that measured during the nonnuclea~ L0C~s. Inspection of pre
d.icted load data for combined LOCA and seismic activity indi.cates the
vi
elastic factor of safety of the steam generator support beams is greater
than six. It is felt that this large factor of safety allows the
existing structure sufficient margin to accomodate any additional load
which may not have been predicted with the existing model.
. ... , ' .
vii
CONTENTS
ACKNOWLEDGMENTS
ABSTRACT
SUMMARY .
I. INTRODUCTION
II. SYSTEM CONFIGURATION
III. MEASUREMENTS AND INSTRUMENTATION
IV. EXPERIMENT CONDITIONS ..... .
V. DATA PRESENTATION AND DISCUSSION
VI. REFERENCES . . . . . . . . . . .
FIGURES
1. LOFT major components
2. Acceleration at simulated steam generator flange, East-West (AE-BL2-l) .............. .
3. Acceleration at simulated steam generator flange, North-South (AE-BL2-2) . . . . . . . . . . . .
4. Acceleration at simulated steam qenerator top, vertical (AE-BL3-l) ........ .
5. Acceleration at QOBV, cold leg, North-South (AE-BL4-1) . . .
6. Acceleration at QOBV, hot ieg, North-South (A[ DLS 1) . . . .
......
7. Acceleration at 90-degree-elbow downstream of primary coolant pumps, East-West (AE-PC3-l)
8. Acceleration at 90-degree-elbow downstream of primary coolant pumps, North-South (AE-PC3-2)
9. Acceleration at 90-degree-elbow downstream of primary coolant pumps, vertical (AE-PC3-3)
10. Acceleration at 45-degree-elbow in intact loop hot leg, East-West (AE-PCG-1) .
viii
i i
iii
iv
1
2
6
13
15
106
5
21
21
22
22
23
23
·24
24
25
11. Acceleration at 45~degree-elbow in intact loop hot leg, North-South (AE-PC6-2) .
12. Acceleration at 45-degree-elbow in intact loop hot ·leg, vertical (AE-PC6-3) . .
13. Acceleration at 90-degree-elbow in intact loop hot leg, East-West (AE-PC7-1) . .
14. Acceleration at 90-degree-elbow in intact loop'hot leg, North-South (AE-PC7-2)
15. Acceleration at primary coolant pump inlet, East-West (AE-PC16-l)
16. Acceleration at primary coolant pump inlet, North-South (AE-PC16-2) . . .
17. Acceleration at primary coolant pump inlet, vertical (AE-PC16-3) . .
18. Acceleration at steam generator north side, East-West (AE-PC17-l) . . .
19. Acceleration at steam generator north side, North-South (AE-PC17-2) . .
20. Acceleration at primary coolant pump 1 north side, East-West (AE-PC18-1)
21. Acceleration at primary coolant pump 1 north .side, North-South (AE-PC18-2) .
22. Acceleration at primary coolant pump 1 north side, vertical (AE-PC18-3) .
23. Acceleration at primary coohnt pump 2 north side, East-West (AE-PC19-l)
24. Acceleration at primary coolant pump 2 north side, North-South (AE-PC19-2)
25. Acceleration at primary coolant pump 2 north side, vertical (AE-PC19-3) .
26. Acceleration at bottom of reactor vessel, west side, East-West (AE-RVl-1)
27. Acceleration at bottom of reactor vessel,· west side, East-West (AE-RVl-2)
28. Acceleration at bottom of reactor vessel, west side, vertical (AE-RVl-3) . . . .
ix
.
.
. .
. .
. .
. .
25
26
26
27
27
28
28
29
. . . . . 29
30
. 30
31
31
. . 32
. . . 32
. 33
. . . 33
. . . 34
29. Acceleration at bottom of reacto~ vessel, north side, North-South (AE-RVl-4) . . . 34
30. Acceleration at bottom of reactor vessel, north side, North-South (AE-RVl-5) . . . . 35
31. Acceleration at bottom of reactor vessel, north side, vertical (AE-RVl-6) . 35
32. Strain at reactor vessel broken loop cold leg nozzle (SE-BL8-l) 36
33. Strain at reactor vessel broken loop cold leg nozzle (SE-BL8-2) . . 36
34. Strain at reactor vessel broken loop cold leg nozzle (SE-BL8-3) . . . 37
35. Strain at reactor vessel broken loop cold leg no:a.l e (SE-BL8-4) . . . 37
36. Strain at reactor vessel broken loop cold leg nozzle (SE-BL8-5) . . . . 38
37. Strain at reactor vessel broken loop cold leg nozzle (SE-BL8-6) . . . 38
38. Strain at reactor vessel broken loop colJ leg nozzle (SE-BL8-8)· . . 39
39. Strain at reactor vessel broken loop cold· lP!J nn771P. (SE-AL8-9) . . . 39
40. Strain at reactor vessel broken loop cold leg nozzle (SE-BL8-ll) . 40
41. Strain at reactor vessel broken loop cold leg nozzle (SE-BL8-12) 40
42. Strain at reactor vessel broken loop hot ,~
leg nozzle (SE-BL9-l) . 41
43. Strain at reactor vessel broken loop hot leg nozzle (SE-BL9-2) : 41
44. Strain at reactor vessel,broken loop hot leg nozzle (SE-BL9-4) . .• 42
45. Strain at reactor vessel broken loop hot leg nozzle (SE-BL9-4) . 42
46. Strain at reactor vessel broken loop hot leg nozzle (SE-BL9-5) . ''• 43
x.
47. Strain at reactor vessel broken loop hot leg nozzle (SE-BL9-6) . . 43
48. Strain between.pump and steam generator simulator (SE-BL27-2) . . . 44
49. Strain between pump and steam generator simulator (SE-BL27-4) . . . . . . . . . . 44
50. Strain between pump and. steam generator simulator (SE-BL27-5) . . . 45
51. Strain between pum~ and steam generator simulator (SE-BL27-6) . . . . . . . . . 45
52. Strain between pump and steam generator simulator (SE-BL27-8) . . . . 46
53. Strain at reactor vessel intact loop cold leg nozzle (SE-PC4-l) . 46
54. Strain at reactor vessel intact loop cold leg nozzle (SE-PC4-2) . . 47
55. Strain at reactor vessel intact loop cold leg nozzle (SE-PC4-4) . ... 47
56. Strain at reactor vessel intact loop cold leg nozzle (SE-PC4-5) . 48
57. Strain at reactor vessel intact loop cold leg nozzle (SE-PC4-7) . . . 48
58. Strain at reactor vessel intact loop cold leg nozzle (SE-PC4-8) . . . 49
59. Strain at reactor vessel intact loop hot leg nozzle (SE-PC5-l) . . 49
60. Strain at reactor vessel intact loop hot leg nozzle (SE-PC5-2). . . . 50
61. Strain at reactor vessel intact loop hot leg nozzle (SE-PCS-3) . . 50
62. Strain at reactor vessel intact loop hot leg nozzle (SE-PC5-4) . . 51
63. Strain at reactor vessel intact loop hot leg nozzle (SE-PC5-5) . . . . 51
64. Strain at reactor vessel intact loop hot. leg nozzle (SE-PC5-6) . . . 52
xi
65. Strain at reactpr vessel i~tact loop hot leg nozzle (SE-PC5-7) .
66. Strain at reactor vessel intact loop hot leg nozzle (SE-PC5-8) , . . .
67. Strain at reactor vessel intact loop hot leg nozzle (S.E-PC5-9)
68. Strain at reactor vessel intact loop hot leg nozzle (SE-PC5-10) .
69. Strain at reactor vessel intact loop hot leg nozzle (SE-PC5-ll) .
70. Strain at reactor vessel intact loop hot leg nozzle (SE-PC5-12) ..
71. Strain at steam generator inlet ~ozzle (SE~PC14-2) . , . . . . . . ..
72. Strain at steam gener~tor inlet nozzle (SE-PC14-3)
73. Strain at ste~m generator inlet nozzle (SE.;.PC14-4)
74. Strain at steam generator inlet nozzle (SE-PC14-5)
75. Strain at steam generator inlet nozzle (SE-PC14-6)
76. Strain at steam generator inlet noz~le (SE-PC14-7)
77. Strain at steam generator inlet nozzle (SE-PC14-8)
78. Strain at steam generator inlet nozzle (SE-PC14-9)
79. Strain at steam generator inlet nozzle (SE-PC14-l0)
80. Strain at steam generator inlet nozzle (SE~PC14-12)
81. Strain at steam generator outlet nozzle (SE~PC15~1.).
82. Strain at steam generator outlet nozzle (SE-PClS-2)
83. Strain at steam generator outlet nozzle (SE-PClS-3)
84. Strain at steam generator outlet nozzle (SE-PC15-4)
85. Strain at steam generator outlet nozzle (SE-PClS-5)
86. Strain at steam generator outlet nozzle (SE-PC15~6)
xi i
52
53
53
54
54
5.5
55
56.
56
57
57
58
58
59
59
60
60
61
61
62
62
63
87. Strain at steam generator outlet nozzle (SE-PC15-8)
88. Strain at steam generator outlet nozzle (SE-PC15-9).
89. Strain at steam generator outlet nozzle (SE-PC15-10)
90. Strain at steam generator outlet nozzle (SE-PC15-ll)
91. Strain at steam generator outlet nozzle (SE-PC15-12)
92. Strain at primary coolant pump outlet (SE-PC18-13)
93. Strain at primary coolant pump outlet (SE-PC18-14)
94. Str-ain at primary coolant pump outlet (SE-PC18-15)
95. Strain at primary coolant pump outlet (SE-PC18-16)
96. Strain at primary coolant pump outlet (SE-PC18-17)
97. Strain at primary coolant pump outlet (SE-PC18-18)
98. Strain at primary coolant pump outlet (SE-PC18-19)
99. Strain at primary coolant pump outlet (SE-PC18-21)
100. Strain at primary coolant pump outlet (SE-PC18-22)
101. Strain. at primary coolant pump outlet (SE-PC18-23)
102. Strain at primary coolant pump outlet (SE-PC18-24)
i03. Strain at reactor vessel broken loop cold leg nozzle (SE-BL8-l) . . . . . . . . .
104. Strain at reactor vessel broken loop cold leg nozzle (SE-BL8-2) • . .. . • • . . • • . • . .
105. Strain at reactor vessel broke~ loop cold leg nozzle (SE-BL8-3) . . . . . . . . . .
.106. Strain at reactor vessel broken loop cold leg nozzle (SE-BL8-4) . . .
107. Strain at reactor vessel broken loop cold leg nozzle (SE-81.8-5) . . . • . . • . . .
108. Strain at reactor· vessel broken loop cold leg nozzle (SE-BL8-6) . . . ; . . . . . ..
109. Strain at reactor vessel broken loop cold leg nozzle (SE-BL8-8) . . . . , , , . , . , , . . . . .
xiii
63
64
64
65
65
66
66
67
67
68
68
69
69
70
70
71
71
72
72
73
73
74
74
110, Strain at reactor vessel broken loop cold leg nozzle (SE-BL8-9)
' . . . . . . . . . . . 75
111. Strain at reactor vessel broken 1oop cold leg nozzle (SE-BL8-ll) . . . . . 75
112. Strain at reactor vessel broken loop cold leg nozzle (SE-BL8-12) . . . 76
113. Strain at reactor vessel broken loop hot leg nozzle (SE-BL9-l) . . . . . . . . . . . 76
114. Strain at reactor vessel broken loop hot leg nozzle (SE-BL9-2) . . . . . . . 77
115. Strain at reactor vessel broken loop hot leg nozzle (SE-BL9-3) . . . . . 77
116. Strain at reactor vessel broken loop hot leg nozzle (SE-BL9-4) . . . . . 78
117. Strain at reactor vessel broken loop hot leg nozzle (SE-BL9-5) .• . . . ' . . 78
118. Strain at reactor vessel broken loop hot leg nozzle (SE-BL9-6) .
' . . . . . 79
119. Strain between pump and steam generator simulator (SF~Rl27-?.) . . . . . . . ' . . . . 79
120. Strain between pump and steam generator simulator (SE-BL27-4) . . . . . . 80
1£1. Strain between pump and steam generator simulator (SE-BL27-5) . . . . 80
122. Strain between ..
pump and steam generator simulator (SE-BL27-6) . . . . . 81
123. Strain between pump and steam generator simulat·or .. (SE-BL27-8) . . . 81
124. Strain at reactor vessei intact 1oop cold leg nozzle (:>t-PC4- 'I) . . 82
125. Strain at reactor vessel intact loop cold leg nozzle (SE-PC4-2) . 82
126. Strain at reactor vessel intact ·loop co-ld leg nozzle (SE-PC4-4) . . . 83
127. Strain at reactor Vessel i'ntact loop cold leg nozzle (SE-PC4-5) . . . . . .83
xiv
128. Strain at reactor vessel intact loop cold leg nozzle (SE-PC4-7) . . . . . . . 84
129. Strain at reactor vess~l intact loop cold leg nozzle (SE-PC4-8)' . . . . . . 84
130. Strain at reactor vessel intact loop hot leg nozzle (SE-PC5-1) . 85
131. Strain at reactor vessel intact loop hot leg nozzle (SE-PC5-2) . . . . 85
132. Strain at reactor vessel intact loop hot leg nozzle (SE-PC5-3) .
" . 86
133. Strain at reactor vessel intact loop hot leg nozzle (SE-PC5-4) . . . . . . 86
134. Strain at reactor vessel intact loop hot leg· nozzle (SE-PC5-5) . . . . . 87
135. Strain at reactor vessel intact loop hot leg nozzle (SE-PCS-8) . 87
136. Strain at reactor vessel intact loop hot leg nozzle (SE-PC5-9) . . . . . 88
137. Strain at reactor vessel intact loop hot leg nozzle (SE-PC5-10) . . . . . 88
138. Strain at reactor vessel intact loop hot leg nozzle (SE-PC5-ll) . . . . 89
'
139. Strain at reactor vessel intact 1 oo"p hot leg nozzle (SE-PC5-12) . . 89
140. Strain at steam generator inlet nozzle (SE-PC14-2) 90
141. Strain at steam generator inlet nozzle (SE-PC14-3) 90
142. Strain at steam generator inlet nozzle (SE-PC14-4) 91
143. Strain at steam generator inlet nozzle (SE-PC14-5) 91
144. Strain at steam generator inlet nozzle (SE-PC14-6) 92
145. Strain at steam generator inlet nozzle (SE-PC14-7) 92
146. Strain at steam generator inlet nozzle (SE-PC14-8) 93
·147. Strain at steam generator inlet nozzle ($E-PC14-9) 93
XV
148. Strain at steam generator inlet nozzle (SE-PC14-10) 94
149. Strain at steam generator inlet nozzle (SE-PC14-12) 94
150. Strain at steam generator outlet nozzle (SE-PC15-l) 95
151. Strain at steam generator outlet nozzle (SE-PC15-2) 95
152·. Strain at steam generator outlet nozzle (SE~PC15-3) 96
153. Strain at steam generator outlet nozzle (SE-PC15-4) 96
154. Strain at steam generator outlet nozzle .. (SE-PC15-5) 97
155. Strain at steam generator outlet nozzle (SE-PC15-6) 97
156. Strain at steam generator· outlet nozzle (SE-PC15-8) . 98
157. Strain at steam generator outlet nozzle (SE-PC15-9) 98
158~ Strain at· steam generator outlet nozzle (SE-PC15.:.10) .. . 99
.159. Strain at steam generator ou·tle.t nozzle (SE-PC15:..1l} 99
160. Strain at steam generator outlet nozzle (SE-PC15-12) 100
161 . Strain at primary coolant pump out·l et· (SE-PC'JS-13) '100
162. Strain at primary coolant pump outlet (SE-P~18-14) 101
163. Strain at primary coolant pump outlet (SE-PC18-15) .1'01
164. Strain at primary coolant pump outlet (SE-PC18-16) 102
165. Strain at primary coolant pump outlet (SE-PC18-17) 102
1.66. Strain at primary coolant pump outlet (SE-PC18-l8) 103
167. Strain at primary coo·l ant· pump outlet (SE-PC18-19) l03
168. Strain at primary coo.l ant pump outlet. (SE-PC18-21) 104
169. Strain at primary ·coo 1 ant pump outlet (SE,..PC18-22) 104
170. Strain at primary coolant pump out·l et (SE-PC18-23) 105
171. Strain at primary coolant pump outlet (SE-PC18-24) 105
xvi
TABLES
I. Accelerometer Locations.
II. Strain Gage Locations ..
III. LOFT Ll-Series Experiment Conditions
IV. ·Summary of Accelerometer Data for Experiment Ll-3A
xvii
7
9
14
18
I. INTRODUCTION
The presentation of the loss-of-fluid test (LOFT) system structural
response during subcooled blowdown is addressed by the following:
(1) The response of the LOFT system relative to (a) experiment
predictions and (b) system design.
(2) The quality and magnitude of LOFT accelerometer and strain
gage data (structural response data).
(3) The applicability of LOFT structural response data for reactor
safety and/or structural
requalification.
code qualification and LOFT
(4) The quality, quantity, and position of existing and/or
proposed measurem~nts.
(5) The differences in structural response data from nonnuclear to
nuclear LOCEs.
(6) The need for further analysis of the existing structural
response data and/or the LOFT system with structural' codes.
This analysis concerns only the primary coolant system and blowdown
loop to the quick-opening blowdown valves (QOBVs) of the LOFT facility
as described in Section II of this
acquired with · the instruments
report.
described
. . Structural response
in Section III for and Ll-3A[ 1•2•3 •4 •5]
data
the
were nonnuclear series Experiments Ll-2, Ll-3,
reviewed. A brief descri~tion of the experiment
in Section IV. A complete set of accelerometer
conditions is included
and strain gage data
from the Ll-3A experiment is presented in Section V with an evaluation
and discussion.
. 1
II. SYSTEM CONFIGURATION
The LOFT facility has been designed to simulate the major
components and system thermal hydraulic responses of a large pressurized
water reactor (LPWR) during a loss-of-coolant accident (LOCA). The test
assembly is comprised of five major subsystems which have been
instrumented such that desirable system parameters can be measured and
recorded during a loss-of-coolant.experiment (LOCE). These subsystems
were instrumented for structural response me~surements for purposes of
assurance of the adequacy of the LOFT structural design and for
requalification only. No attempt was made to instrument fqr purposes of
structural code verification. The subsystems include: (a) the reactor
vessel, (b) the primary coolant (intact) loop, (c) the blowdown {broken) loop, (d) the blowdown suppression syst~m. and (e) ~he ~mergency core
cooling system (ECCS).
The LOFT reactor vessel simulates the reactor vessel of a LPWR. It
has an annular downcomer, a lower plenum, lower core suppbrt plates, a
core simulator, and an upper plenum. The downcomer connects with the
co 1 d ·1 eg_ of both the intact and broken 1 oops and contains two experi
mental instrument stalks; the upper plenum connects the hot leg of both
the intact and the broken loops. fhe core simulator conta1ns an exper1·
mental instrument stalk and hydraulic orifice plate assembly to simulate
the flow resistance of a nuclear core which will be installed for non
nuclear LOCE Ll-5.
The 1ntact luu!J ~ JmuldL~~ Lit~ uttut·ulo...t!tt loops of a LPWR. This loop
contains a steam generator, two circulating coolant pumps connected in
parallel, il prc~::;uriz.er, a venturi flowmeter, and connecting pipino.
For Experiment Ll-3A, the primary side steam generator inlet and outlet
plenums contained square-edged orifice plates sized for low resistance
or core flow area scaling. Thus these orifices provided a similar
pressure drop at scaled flow rates around the LOFT intact loop
(excluding the reactor vessel) as exists in a LPWR operating loop. The
secondary side of the steam generator was filled to a predetermined
2
level and isolated from the remainder of the secondary coolant system.
The intact loop circulating coolant pumps were used to bring the system
to the initial test temperature of 282°C.
The· broken loop simulates the broken loop of a LPWR. It consists
basically of hot and cold legs that are connected to the reactor vessel
and the blowdown suppression tank header. Each leg consists of a break
plane orifice which determines the break size to be simulated, a quick
opening blowdown valve (QOBV) which simulates a pipe break, a recircula
tion line, an isolation valve, a~d connecting piping. The recirculation
lines establish a small flow from the broken loop to the intact loop ·to
maintain these loop temperatures approximately equal prior to the blow
down. These recirculation paths are secured just prior to blowdown
initiation.
Experiments Ll-2, Ll-3, and Ll-3A simulated a 200% double-ended
shear break in a cold leg of a LPWR operating loop. In this configura
tion, the broken loop hot leg contained, in addition to the above
mentioned components, steam generator and pump simulators. These
simulators have hydraulic orifice plate assemblies installed which have
similar (passive) resistances to flow as a real pump and steam
generator. The break flow area (break plane orifice area) in this con
figuration is 0.0084 m2; this is 100% of the possible break flow area in
each line.
The blowdown suppression system simulates the containment back
pressure of a LPWR. This system is comprised of the blowdown
suppression· tank header, the blowdown suppression tank (BDST), the
nitrogen pressurization sy~tem, and the blowdown suppression tank spray
system (BDSTSS). The blowdown header is connected to the suppression
tank by four suppression tank downcomers that extend inside the tank and
discharge below the water level established as a test initial condition.
The nitrogen pressurization system is supplied by the LOFT inert gas
system and utlizies a remote controlled pressure regulator to establish
and maintain the specified BDST initial pressure. The spray system
consists of a centrifugal pump which discharges through a heatup heat
3
exchanger and either three spray headers or a pump recirculation line
that contains a cooldown heat exchanger. The spray pump suction can be
aligned to either the BDST or the borated water storage tank (BWST).
The three spray headers have 0.0013-, 0.0038-, and 0.0139 m3/s flow rate
capacities and are located in the BDST along the upper centerline; To
model the containment back pr~ssure of a LPWR, predetermined initial
conditions are established in the BDST.
The LOFT ECCS simulates the ECCS of a LPWR. The accumulator, the
high-pressure injection system (HPIS), and the low-pressure injection
system (LPIS) were used dur·ing the Ll-3A expet··iment. Each system was
configured to inject scaled volumetric flow rates of ECC directly into
the lower plenum of the re.;lctor vessel. To provide these scaled tlow
rates, accumulator ACC-A, HPIS pump A, and LPIS pump A were utilized.
Accumulator ACC-A was preset to inject ECC at a system pressure of
4.22 MPa. HPIS pump A was preset to inject at 0.001 m3/s and to
initiate by LOCE control at 22 s after the initiation of blowdown; LPIS
p~mp A was adjusted to in~tiate by LOCE control at 35.5 s after the
initiation of blowdown.
A detailed description of the LOFT facility can be found in
Reference 6. Only the first three subsystems mentioned above are
dis~ussed and a pictorial view is included in Figure 1.
4
Pressurizer
Steam Generator Outlet OTT Flange
Intact Locp Hot Le~; OTT
Vessel
Fig. l
Broken Loop Hot Leg OTT
Flange ·
ECC Lower Plenum lnje_ction Inlet
Intact Loop Cold Leg OTT Flange
LOFT major cq~ponents.
ANC-C-7002
Suppression Tank
III. MEASUREMENTS AND INSTRUMENTATION
The LOFT instrumentation system was designed to measure and record
the important parameters that occur during a LOCE. The .accelerometer
and str~in gage data from the locations summarized in Tables I and II
are. considered sufficient for use in the analysis presented herein.
Information on the calibration factors, accuracy, and response of
specific instruments is given in Reference 7. Reference 6 should be
consulted tor details of instrument design and locations.
Device Number
AE-BL2-l
AE-BL2-2
AE-BL3-l
AE-BL4-l
AE-BL5-l
AE-PC3-l
AE-PC3-2
AE-PC3-3
AE-PCG-1
AE-PCG-2
AE-PCG-3
AE-PC7-l
AE-PC7-2
AE-PC7-3
TABLE I
ACCELEROMETER LOCATIONS
Direction
East-West
North-South
Vertical
North-South
North-South
East-West
North-South
Vertical
East-West
North-South
Vertical
East-West
North-South
Vertical
7
Location
SimUlated steam generator flange
Simulated steam generator flange
Simulated steam generator top
Quick-opening blowdown valve, cold leg
Quick-opening blowdown valve, hot leg
90-degree-elbow downstream of primary coolant pumps
90-degree-elbow downstream of primary coolant pumps
90-degree-elbow downstream of priamry coolant pumps
45-degree-elbow between reactor vessel and steam generator
45-degree-elbow between reactor vessel and steam generator
45-degree-elbow between reactor vessel and steam generator
90-degree-elbow betwe~n reactor vessel and steam generator
90-degree-elbow between reactor vessel arid steam generator
90-degree-elbow between reactor vessel steam generator
TABLE 1 (continued)
Device Number Direction Location
AE-PC16-l East-West Primary coolant pump jnlet
AE-PCl6-2 .North-South Primary coolant pump inlet
AE-PC16-3 Vertical Primary coolant pump inlet
AE-PCl7-l East-We.st Steam generator, north side
AE-PC17-2 North-South Steam generator, north side
At-PCl 8- l cast-West Pr1ma.ry co·olanL IJUIIIIJ 1 , north side
AE-PC18-2 North-.South Primary coolant pump 1 , .north s.i de
AE-PC18-3 Vertical .Pri ma:ry ooo'lant pump 1 , nor·th s·ide
AE-PC19-l East-West Pri.mary coolant pump 2, north .side
AE-PC19"'".2 ·North-South Primary coo·l ant pump 2, no·rth si.de
AE-PCl9-3 VeY't i ca 1 Primary coolant pump 2, north side
AE-RVl-1 East-West Reactor vessei bottom., west side
AE--RV1 -2 Ea~t-West Reactor vessel ·bottom, west side
AE-- RVl· 3 Ve.rtic.Jl . ~a actor VQ»iel b?ttom, we~.t. side
AE- RVl-4 North-South Reactor vessel bottom, north side
AE-RVl-5 North-South Reactor vessel bottom, north side
AE-RVl-6 Vert i'cal 'Reactor vessel bottom, north side
TABLE II
STRAIN GAGE LOCATIONS
Device Number Position Location
SE-BL8-l Top-longitudinal Broken loop, cold leg nozzle
SE-BL8-2 Top-45 degrees Broken loop, cold leg nozzle
SE-BL8-3 Top-circumferential Broken loop, cold leg nozzle
SE-BL8-4 Right-longitudinal Broken loop, cold leg nozzle
SE-BL8-5 Right-45 degrees Broken loop, cold leg nozzle
SE-BL8-6 Right-circumferential Broken loop, cold leg nozzle SE-BL8-7[a] Bottom-longitudinal Broken loop, cold leg nozzle
SE-BL8-8 Bottom-45 degrees Broken loop, cold leg nozzle
SE-BL8-9 Bottom-circumferential Broken loop, cold leg nozzle SE-BL8-10[a] Left-longitudinal Broken loop, cold leg nozzle
SE-BLS-11 Left-45 degrees Broken loop, cold leg nozzle
SE-BLB-12 Left-circumferential Broken loop, cold leg nozzle SE-BL9-l Top-longitudinal Broken loop, hot leg nozzle
SE-BL9-2 Right-longitudinal Broken loop, hot leg nozzle
SE-BL9-3 Right-45 degrees Broken loop, hot leg nozzle
SE-BL9-4 Right-circumferential Broken loop, hot leg nozzle
SE-BL9-5 Bottom-longitudinal Brol<en loop, hot leg nozzle
SE-BL9-6 Left-longitudinal. Broken loop, hot leg nozzle SE-BL9-7[a] Left-45 degrees Brok~n loop, hot leg nozzle SE-BL9-8[a] Left-circumferential Broken loop, hot leg nozzle SE-BL27-l [a] South-longitudinal Between pump and steam
generator simulator
SE-BL27-2 South-longitudinal Between pump and steam
generator simulator SE-BL27-3[a] South-circumferential Between pump and·steam
generator simulator
SE-BL27-4 East-longitudinal Between pump and steam
generator simulator
SE-BL27-5 North-longitudinal Between pump and steam
generator simulator
9
TABLE II (continued)
Device Number Position Location
SE-BL27-6 North-45 degrees Between pump and steam
generator simulator . SE-BL27-7[a] North-circumferential Between pump and ~team
generator simulator
SE-BL27-8 West-longitudinal Between pump and steam
generator simulator
SE-PC4-l Top-lonqitudinal Intact loop, cold leg nozzle
SE-PC4-2 Right-longitudinal Intact loop, cold leg nozzle SE-PC4-3[a] Right-45 degree~ Intact loop, cold leg nozzle
SE-PC4-4 Right-circumferential Intact loop, cold leg nozzle SE-PC4-5 Bottom-longitudinal Intact .1 oop, cold leg nozzle SE-PC4-6[a] left-longitudinal lntact loop, cold leg nozzle
SE-PC4-7 Left-45 degrees Intact loop, cold leg nozzle
SE-PC4-8 Left-circumferential Intact loop, cold leg nozzle
SE-PCS-1 Top-longitudinal Intact loop, cold leg nozzle
SE-PCS-2 Top-45 degrees Intact loop, hot leg nozzle
SE-PC5-3 Top-circumferential Intact loop, hot leg nozzle SE-PC5-4 Right-longitudinal Intact loop, hot leg nozzle SE-PCS-5 Ri ght.-4!:> degrees Intact loop, hot leg nozzl~
SE-PC5-6lbJ ' Right-circumferential Intact loop, hot leg nozzle
SE-PC5-7[b] Bottom-longitudinal Intact loop, hot leg nozzle
SE-PC5-8 .:Bottom-45 degrees In.tact loop, hot leg nozzle.
SE-PCS-9 Bottom-circumfe~ential Intact 'loop, hot leg nozzle SE-PCS-10 Left-longitudinal Intact loop, hot leg nozzle
SE-PC5-ll Left-45 degrees Intact loop, hot leg nozzle
SE-PC5-12 Left-circumferential Intact loop, hot leg nozzle SE-PC14-l[a] Right-longitudinal Steam generator inlet nozzle
SE-PC14-2 Right-45 degrees Steam generator inlet nozzle
SE-PC14-3 Right-circumferential Steam generator inlet nozzle
SE-PC14-4 Top-longitudinal Steam generator inlet nozzle
SE-PC14-5 Top-45 degrees Steam generator inlet nozzle
10
TABLE II (continued)
Device Number Position Location
SE-:PC14-6 Top-circumferential Steam generator inlet nozzle
SE-PC14-7 Left-longitudinal Steam gener~tor inlet nozzle
SE-PC14•8 Left-45 degrees Steam generator inlet nozzle
, SE-PC14-9 Left-circumferential Steam generator inlet nozzle
SE-PC14-10 Bottom-longitudinal Steam generator inlet nozzle
SE-PC14-ll[a?Bottom-45 degrees Steam generator inlet nozzle
SE-PC14-12 Bottom-circumferential Steam generator inlet nozzle
SE-PC15-l North-longitudinal Steam generator outlet nozzle
SE-PC15-2 North-45 degrees Steam generator outlet nozzle
SE-PClS-3 North-circumferential Steam generator outlet nozzle
SE-PClS-4 East-longitudinal 'Steam generator outlet nozzle
SE-PC15-5 East-45 degrees Steam generator outlet nozzle
SE-PC15-6 East-circumferential Steam generator outlet nozzle SE-PC15-7[a] South-longitudinal Steam generator outlet nozzle
SE-PC15-8 South-45 degrees Steam generator outlet nozzle
SE-PC15-9 South-circumferential Steam gen~rator outlet nozzle
SE-PC'l5-10 West-longitudinal Steam generator outlet nozzle
SE-PC15-ll West-45 degrees Steam generator outlet nozzle
SE-PC15-12 West-circumferential Steam generator outlet nozzle
SE-PC18-13 Bottom-longitudinal Primary coolant pump outlet
SE-PC18-14 Bottom-45 degrees Primary coolant pump outlet
SE-PC18-15 Bottom-circumferential Primary coolant pump outlet
SE-PC18-16 Left-longitudinal Primary coolant pump outlet
SE-PC18-17 Left-45 degrees Pri·mary coolant pump outlet
SE-PC18-18 Left-circumferential Primary coolant pump outlet
SE-PC18-19 Top-longitudinal Priamry coolant pump outlet
SE-PC18-20[c]Top-45 degrees Primary coolant pump outlet
SE-PC18-21 Top-circumferential Primary coolant pump outlet
SE-PC18-22 Right-longitudinal Primary ·coolant pump outlet
SE-PC18-23 Right-45 degrees Primary coolant pump outlet
11
TABtE II (continued):
Device Number Position Location
SE-PCl8-24· Right-circumferential Primary coolant pump. outlet
[a] Plots not includ~d due to signal failure.
[b] Plots to 1.0 second not included due to calibration problem.
[c} Pl~ts not i~cluded due to calibration problem .
. . : 1:2:
. ·.
IV. EXPERIMENT CONDITIONS
The parameters affecting blowdown loads for Experiments Ll-2, Ll-3,
and Ll-3A are summarized in Table III. For a detailed description of
the experiment configuration, operation, and conditions for each of the
above mentioned experiments, the reader is directed to References 1
and 2. The conditions affecting blowdown loads in the intact and broken
loops remain the same for the nuclear experiments as seen in the above
mentioned Ll series experiments .
13
~
TABLE III
LOFT Ll-SERIES EXPERIMENT CONDITIONS
Experiment Break Opening System ECC Pressurizer Designation Bre.=.k Size Break T~12e Time .!1P Injection Pressure
Ll-2 full[a] cold leg nonli na l high cold leg 15.6 break area (delayed)
Ll-3 full cold leg nominal low lower 15.6 bre:~k area plenum
Ll-.3A full cold leg nominal low lower 15.6 bre3k area. plenum
Primar:.' coolant temperature - 282°C
Primar:t coolant mass flow - 272 Kg/s
Nominal break opening time ~ 17.5 +2,5 ms[b] -
[a] Full break area corresponds to si~ulation of a non-communicative double-ended break of an LPWR main primary coclant pipe.
(MPa)
[b] Nominal break opening time 1s the e:<pected time interval for propagation of a full circumferential break in the main coolant pipe of an _PWR.
V. DATA PRESENTATION AND DISCUSSION
Accelerometer and strain gage data from Experiment Ll-3A are
included in Figures 2 through 172 which are included in total at the end
of this section. The characteristics of this set of data are similar to
those from Experiments Ll-2 and Ll-3,
accelerometer data from Experiment Ll-2
unusable due to nonzero average traces and
Ll-3 acceleration data to 0.2 s revealed
except in the case
which was considered to
spurious noise.· Review
ampl itu'de of acceleration
of
be
of
and
frequency content similar to the included Ll-3A acceleration data. The
strain gage data for all three experiments were reviewed to 0.2 s, and
it was concluded that the Ll-3A strain gage data were representative of
the strain gage data from all three experiments. Strain gage data to
1.0 s were reviewed since, in a few cases, the maximum dynamic strain
did not occur in the time during which ~ubcooled conditions existed.
Review and comparison of accelerometer data from Experiment Ll-3A
with predicted and design accelerat"ions, as summarized in Table IV,
indicates the following:
(1) In general the data are ~haracterized by a high degree of
noise in the form of preblowdown system vibration and/or high
frequency localized accelerations which are amplified due to
resonance in the accelerometers (Figures 5, 11, 15, 17, 20,
21, 22, 23, 24, and 25). These characteristics make quantifi
cation of the recorded accelerations difficult and highly
subjective.
(2) In many cases the low frequency (less than 110 Hz) amplitude '
of the recorded signal is estimated to be less than the
accuracy 1 imits of the accelerometer which is on the order of
,:!:0.20 G (Figures 7, 13, 17, 21, 23, 26, 27, 28, 29, 30,
. and 31).
15
(3) Some of the data are characterized by a shift in the average
value of the signal and/or are highly nonsymmetric which, upon
integration, would indicate unbounded displacements in the
system (Figures 6 and 14).
(4) With the problems in 1 through 3 above in mind, the data
review and comparison indicate'in most cases that accelera
tions in the frequency range less than 300 Hz are below the
predicted and design values. Accelerations at frequencies
greater than 300 Hz are believed to be local rather than gross
structural response and/or noise and give rise to deflections
less than 0.025 mm (Figures 2 .• 3, 10, ll, 12, 15, 16, 18, 19,
20, 21, 22, 23, 24, and 25).
(5) The measured accelerations at AE-PC17-l and AE-PC-17-2 (on. the
steam .generator, north s i·de) · exceed the LOCE design va 1 ues by
nearly a factor of twb. However, integration of the data
yielded deflections which were less than half those associated
with seismic_loads. Since the system is designed for combined
~eisMit and LOCA loads, tne LOCE loads will not pt~sent a
structural problem.
(6) The accelerometer data at AE-BL2-l (simulated steam generator
flange) indicate _that the measured .accelerations are slightly
higher than pre~icted and desig~ values. Integration of data
at this location yielded deflections le~s than half those for
seismic loads assuring structural adequacy for LOCE loads.
Review of the strain gage data indicates that the dynamic strains
at all ~easurement locations are Tess than 150 x 10-6 m/m~ The strain
data are characterized by a gradual: build up of. the signa 1 s corre
sponding to response to pressure relaxation during blowdown. Dynamic
fluctuations about the gradual build u~ correspond to response to
dynamic excitations, and the half range magnitudes a.re much lower than
those associated with pressure relaxation. The accuracy level of the
strain gage data is on the order of 10 x 10- 6 m/m which is 25 to 50% of
16
the half range magnitudes of the dynamic fluctuations. Since the
dynamic fluctuations are small (giving rise to stresses less than
1.12 X 107 N/m2) and not much larger than the accuracy level of the
signal, reduction of the strain gage data to component loads for
comparison with predicted data is deemed unnecessary.
In general, the magnitude and noise level of the structural
response data make quantification for direct comparison with predicted
·and de~ign values highly subjective. It is felt that the data are
applicable only to the LOFT facility oue to the complexity of the system
and are not applicable to LPWRs in general. Use of the data for
structural code qualification is not recommended due to the problems
involved in quantifying the recorded signals (low amplitudes, high noise
level). It is felt that the data can be used but should not be relied
upon solely for LOFT requaljfication due to the problems associated with
obtaining meaningful measurements at all critical structural points in.
the system (welds, joints, tees, etc.). A comprehensive inspection
program for welds and components at intervals based on fatigue analysis
will be included for requalification of the system. The present mea
surement system is deemed adequat~ for the purposes of LOFT structural
response determination and eval~ation, and additional insturments or
repositioning of measurements is felt to be unnecessary.
Hydraulic loads associated with nuclear LOCEs should be no more
severe than those arising from nonnuclear LOCEs since the system flow
rates for each case (assuming equal break areas) are the ·same. Decom
pression loads for nuclear LOCEs should be somewhat smaller than those
for nonnuclear ·LOCEs, because the saturation pressure in the upper
plenum is higher for nuclear experiments (11.44 MPa ·nuclear LOCE,
6.62 MPa nonnuclear LOCE). It is concluded that no major differences in
structural response data are expected in the data from nuclear tests.
Results of this analysis indicate the subject system is adequate
for LOCE loads and further analysis with structural codes is deemed
unnecessary.
17
TABLE IV
SUMMARY OF ACCELEROMETER DATA FOR EXPERIMENT L1-3A
Measured D~ta[aJ Predicted. Oe.vi ce ~q:e] era:t,i on., f.req_~.e .. ncy Acce 1 e.r.at.i on, Number. (-G). (Hz) (G)
AE-BL2-.1 0.7 30 0.6 AE-BL2-1[b] 1.6 500
AE-BL2-2 0.6 10 1.2 AE..:BL2-2[b] · 1.9 600 ,,
AE.- BL3-l[ c] data invalid 1.3 AE-B.L4-l[d] data invalid 2 .. 3 AE.-Bl,.5~ 1 [c] data invalid 2. 1
A~-PC3-1 0.2 20. 2. 1
AEi'H.C)::,J' 0.~ .12.5:' 2:,:1: A6-PC3.,.-l [b] 1.9 300
AE-PC3-2 ·0. 9 40 2. 1 AE-PC3-2[b] 2.3 300 AE~PC3,..3[e] 0.3 60· 2 .. 1 AE.,.PC3-3[b,e] 1.4 300> .
AE-PC6-1 ''l. 8 100 l.8
AE-PC6-1 [b] 3. 1 700 AE-PC6-2[e] 0.9 200 1. 6 " AE,.PC6-2[b,~] .· 4c. 2 '. 900 ·. ..
AE-PC6-3 0.8 40 1.8 AE~PC6-3[b] . 3. 2' 400
AE.,.,PC7-l· : 0.2 25 1; 4·
AE-PC7-2[c] '- '·data. inv·a1·id· 1.6 AE-PC7-'3[f]. '· .. data i nva·l id '1.6
AE-PC16-l[e,g] 0: 5· , .. ,. ·80. 2. 1 AE-PC16-1[b,e,g]· 1.9 1000
AEA·P(:1G~2 0.5 40 • • \I ... L2 AE-PC_l6-2[b] 0.9 300 AE-PC16-2[b] 1.2 s·oo
18 .
Desjgn Acce 1 e.ratj on
(G)
0.67
l. 63
·8. 60
4.86
5.55
10.8
1 o·.:a
13. 1
10:9
7.05
8. 54.
''. 2. 36
3. 00.
4.28
2.59
9:93
14.9 ·;.
TABLE IV (continued)
Measured Oata[a] Predicted Design Device Acceleratjon Frequency· Acceleration Acceleration .. Number CG2 (Hz) (G) (G)
AE-PC16-3[e,g] 0.3 30 1.0 11.3 AE-PC16-3[b,e,g] 2.0 400
AE-PC17-l 0. 3. 15 0. l 0.18
AE-PC17-l 0. l 100 0. l 0. 18 AE-PC17-l [b] 2.8 700
AE-PC17-2 0.6 25 0.3 0.34 AE-PC17-2[b] 7.8 1000 AE-PC18-l[g] 0.2 30 0.6 l. 79 AE"'-PC18-l[b,g] 1.6 800 AE-PC18-2[g] 0.4 60 0. 7 2.15 AE-PC18-2[b,g] 2.0 1000 AE-PC18-3[g] 0.3 25 0.4 3.57 AE-PC18-3[b,g] 1.2 600 AE-PC19-l[g] 0.2 100 0.6 2.08 AE-PC19-l[b,g] 0.6 400 AE-PC19-l[b,g] l . l 700 AE-PC19-2[g] 0.4 50 0.8 2.49 AE-PCl9-2[6,gJ 2.5 800 AE-PC19-3[g] 0.4 30 0.4 5. 77 AE-PCl9-3[h,gJ 1.3 4UO
AE-RVl-1 0.2 20 0. l 0.21 AE-RVl-1 [b] 1.6 - 350 AE-RVl-2[h] 0.3 13 0. 1 0.21 AE-RVl-2[b] 1.8 350
AE-RVl-3 0. l 15 0.3 0.42 AE-RV1-3[b] 2.0 350
AE-RVl-4 0. l 30 0.4 0.42 AE-RVl-4[b] 1.6 300
AE-RV1-5 0. l 13 0.4 0.42
19
/
'TABLE IV· (continued)
Measured nata[a]. Predicted Design Device Acceleration Frequency Acceleration Acceleratiop Number (G2 (Hz) (G2 (G) c
AE-RVl-5[b~. 1.5 300.
AE-RVl-6 0.3 100 0.3 0.42 AE-RVl-6[.b] 2. l 350
ral AccuracY of tabulated data is poor due to its low ma~nttude relative t.o no i s.e 1 eve.l .
[b] Acceleration believed· t.o be iocal and/or high level noise, not structural. as displacements are less than 0.25 ~m.
[c] Data have a bias zero shift and/6t the signal i~ highlY ·nonsymmetri c (.indicating unbounded displacements.).
[dJ Signal· appears to be 60-Hz noise. . .
[e] Data are high·ly questionable due to nonsymmetri·c characteris·t:ics.
[f] Signa]· failed.
[g] High degre~-of noise prior to tim~ zero has definite effeit ·on s-ignal· afte.r time zero, making resul.ts of data reduc.tfon. CJIIP.S t. i nnnh.l P.;
[h] Integration· of the data-yields de-flections whi.ch increase.- in magh-i-· tude throughout the: subcool ed b lowdown state i'ndi cat i ng -the data·; are invalid:
2.o.-:
.
2.0
0.0 ~
z: 0
I-«:
"' ...., -' ....,
-I. 0 '-' ~
-2.0 L-~~~~~~~~~~-d~~~--~_.~--~._~~~~--~~~
-0.05 0.00 0.05 0. I 0 0. 15 0.20
TIME AFTER RUPTURE !SECONDS>
Fig. 2 Acceleration at simulated steam generator flange, East-West (AE-BL2-l).
2.0
!::. 0.0
r5 ;::: «: "' ...., -' ...., u u «: -I. 0
-2.0 ~~~_.~~&-~~~--~~~_.~--._~~~--~._~_.~--._~_,
-0.05 0.00 0.05 0. I 0 0. 15 0.20
TIME AFTER RUPTURE !SECONDS>
Fig. 3 Acceleration at simulated steam generator flange, North-South (AE-BL2-2).
21
:z 0
s LLI _, LLI u u <(
:z ~
Oo <( 0:: LLI _, LLI ..., u <(
500
2o5
OoO
-205
-500
-0°05
Fig. 4
·!50 0
2o5
OoO ...,.,..
-205
-500
-0.0!3
Fig. 5
I I
I l I •I• •
~I
II~ ~ \
l rn I --r
1rr r• -,
0°00 0005 0 0 I 0 0 0 15 Oo20
TIME AFTER RUPTURE ISECONDSl
Acceleration at simulated steam generator top~ vertical (AE-BL3-l).
A
~
• ~ • l 'I
A ,,
I IWII ~ ~ I
v lUll I I
•• 1 II II Jll'
II rr
i
OoOO 0°0!3 0 o I 0 0 0 15 0.20
TIME AFTER RUPTURE ISECONOSl
Acceleration at QOBV, cold leg, North-South (AE-BL4-l).
22
..
2. z 0 ;:::: g; ...., ....J ...., u u <(
z 0
s ...., ....J ...., u u <(
5.0
2.5
0.0
-2.5
-5.0
-7.5
-0.05
Fig. 6
2.0
I . 0
n.o
-I. 0
-2.0
-0.05
l .. ,,u I II ... Ia
~Yf n~r 1 ~~ H1 "''U!rlllll lA. 'II Ill
·n~ P' ~ Jl' If IU 't: lrrl "' rJ ' I r--
ll!:. " ']
II
wn w I'
0.00 0.05 0. I 0 0. 15 0.20
TIME AFTER RUPTURE <SECONDS>
Acceleration at QOBV, hot 1 eg, North-South (AE-BL5-l). ~
I • II II Ill 1'1 r .l 14!J ~ 1. rt lA~ •t I• A -n:
.M -M ~ AI 1111 IV \IYV '\II ~ IUYI 1 ' l1 I' 1 .. ' H
r
0.00 0.05 0. I 0 0. 15 0.20
TIME AFTER RUPTURE <SECONDS>
Fig. 7 Acceleration at 90-degree-elbow downstream of primary coolant pumps, East-West (AE-PC3-l).
23
2.0 1--1·--
1-·
1-- ••• r- I ..
I .!\. •• Rill~ l
I. 0
0.0
2-
~~"'" I
" IL I. , f Rl\ • I J
I ,, 1'\ l D 1\J, j ,
111111 I I Ll J l II .. I-· J"' PI I• 1-
:z: 1-0 -I .0 ;::: ~ i-UJ ....J UJ
1-· : u u ~-· ex:
-2.0 :--1 .L~t~. -·
--.. :--+- -· --.. _; --~-- -- : - ---·
-3.0
-0.05 0.00 0.05 0. I 0 0. 15 0.20
TJHE AFTER RUPTURE !SECONDS)
Fig. 8 Acceleration at 90-degree-elbow downstream of primary coolant pumps, North-South (AE-PC3-2).
~
:z: 0 ;::: ~ UJ ....J
ti u ex:
Fig. 9
2.0 1·-
1--, __
I--
I . 0
-I • R~
IJ I Ill 11 0.0
11111111 ll '" ll I.Jh • .I.! IAI J ~ '"V ~ 1\M IIIlA J11 ·r N'-,M
IPI ' I 111 ' ., r I' lrl Ill r
1- - I I 1--
' -I . 0 e .. -- --.... -+---
·-·1--
-e.o i
-0.05 0.00 0.05 0. I 0 0. 15 0.20
TIME AFTER RUPTURE !SECONDS)
Acceleration at 90-degree-elbow downstream of primary coolant pumps, vertical (AE-PC3-3).
24
...
e z: 0.0 ::: 1-<2: 0:: u.J ...J u.J u u <2:
-2.5
5.0 L---~~_.~~~~~_.~~~~~~_.~--~._~~~~~6-~~
-0.05 0.00 0.05 0. I 0 0. 15 0.20
TIME AFTER RUPTURE ISECONOSI
Fig. 10 Acceleration at 45-degree-elbow in intact loop hot leg, East~ West (AE-PC6-l).
-5.0 ~._~--~~~._~~--~--~._._~_.~----._~~_.~----~~
Fig. 11
-0.05 0.00 0.05 0. I 0 0. 15 0.20
TIME AFTER RUPTURE ISECONDSI
Acceleration at 45-degree-elbow in intact loop hot leg, NorthSouth (AE-PC6-2).
25
:z 0
1-
~ LoJ ---' LoJ
i t--+---' ' ' I
~--+-~-+--~~~~~~~-+-4~~~~~~H-~-4.-+-~-+~
~ -2. 5 ._ ____ ..,....-+--+-+-+-
-5.0 ~-----~--_.~ __ ._ ______ ~----------~--~--._ __ _. __ ~------~
-o.o~ 0.00 0.05 0. I 0 0. I !:I 0.20
TIME AFTER RU~TURE ISECONOSl
Fi·g,. r2· Acc·eler.ati on. a-t: 4-5-dE:~ree.-el bow. in intact loop~ hot reg., vertical (AE-PC6-3) ..
!3.0
-5.0 L-----~----~----------~--._ ________ ._ ______ ~ __ _. ____ ._ ____ ~ -0.05 0.00 0.05 0. I 0 0. 15 0.20
Fig. 13
TIME AFTER RUPTURE ISECONOSl
Acceleration at 90-degree-elbow in intact loop hot leg, EastWest (AE-PC7-l).
26
-4.0 ~._~_. ____ ~._~_. ______ ._~~------~~~----._~_.----~
-0.05 0.00 0.05 0. I 0 0. I 5 0.20
TIME AFTER RUPTURE (SECONDSl
Fig .. 14 Acceleration at 90-degree-elbow in intact loop hot legs NorthSouth (AE-PC7-2) .
'(;' I . 0
z: 8 1-..: "" UJ _J 0.0 UJ u u ..:
-I .0
-2.0 ~._~~_.~--~._~_.~~--~._~_.--------~~_. ____ ~._~
-0.05 0.00 0.05 0. I 0 0. I 5 0.20
TIME AFTER RUPTURE (5ECON0Sl
Fiq. 15 Acceleration at primary coolant pump inlet, East-West (AE-PC16-l).
27
7.0
6.0
. 5.0
~ :z: 4.0 :::: 1-
"" "" ..... ....J
I&
J -- II ... I• A .. ... .. - 'I\ \. ...... ~ - .,. l lJ t _ .... _ •• T
-·- ·- IIIII I 'II ' I I
..... 3.0 u
u
"" - -t---1-· ---+-
I --+-2.0 . - -+-
---+-·-
··-t·-.... --I. 0
-0.05 0.00 0.05 0. I 0 0. 15 0.20
TIME AFTER RUPTURE <SECONDSI
Fig. 16 Acceleration at primary coolant pump inlet, North-South (AE-PC16-2).
<.!)
:z: :::: 1-<(
"" ..... ....J ..... u u
""
Fig. 17
~.0
0.0
- I .o
-2.0
&3.0
-0.05 0.00 0.05 0. I 0 0. 15 0.20
TIME AFTER RUPTURE <SECONOSI
Acceleration at primary coolant pump inlet, vertical (AE-PC16-3).
28
~ 0. 0
~ o< UJ --' UJ u u
""
-0.05
Fig. 18
:z: C)
1-
"" o< UJ --' UJ u ~
10.0
5.0
o·. oo 0.05 0. I 0 0. 15
. TIME AFTER RUPTURE ISECONOSl
Acceleration at s~eam generator north side, East-West (AE-PC17-l).
0.20
-10.0 ~~~~~~~~~~--~~~_.~--._~~~--~._~_.~--._~_,
. .-0.05
Fig. 19
0.00 0.05 0. I 0 0. 15
TIME AFTER RUPTURE !SECONDS!
Acceleration at steam generator north side, North-South (AE-PC17-2).
29
C..20
I. 0
~ :z: 0
I-<(
0.0 "" w ...J w u u <(
-I. 0
-2.0 L-~~~--~~~~--~--~_.~--~~~_.--~--~~~--~~~~
·-0. 05 0.00 0.05 0. I 0 0. 15
H ME AF"TER RUPTURE. I SECON.OS l
Fig. 20 Acceleration at primary cool9-nt pump l north side, East-West (AE-PC18-l).
I. 0
~
:z: 0 0.0 ~ <( IV
'" ...J w u u .:r I. 0
-3.0 L-~~~--~~~_.--~._.__.~--~~~_.--~--~~~--~~~~
-0.05 0.00 0.05 0. I 0 0. 15 0.20
TIME AF"TER RUPTURE ISECONOSl
Fig. 21 Acceleration at primary coolant pump l north side, North-South (AE-PC18-2).
30
~ OoO z 0 ;::: ..: "' UJ
ttl '-' '-' ..:
-I o.O
-200 ~~~_.~~~~~~_.~--~._~~~~--~~~-L~~~~~~
-0005 0°00 Oo05 0 o I 0 0 0 15 Oo20
TIHE AFTER RUPTURE !SECONDS>
Fig. 22 Acceleration at primary coolant pump 1 north side, vertical (AE-PC18-3).
~ z 0 s "' UJ -' UJ
'-' '-' ..:
0°0
-200 L-~~_.~~~._~~_.~--~._~~~~~~~~_.~--~~~~
-0°05
Fig .0 23
OoOO Oo05 0 o I 0 0 0 15 Oo20
TIHE AFTER RUPTURE !SECONDS>
Acceleration at primary coolant pump 2 north side, East-West (AE-PC19-l).
31
5 0.0
s .... -' ..... u u <C
-~.0 L-~~~_.~--~~~~~_.~----~._~~~--~--~._._~~
-0.05 o.oo 0.05 0. I 0 0. 15 0.20
TIME A~TER RUPTURE tSECONOSI
Fig. 24 Acceleration at primary coolant pump 2 north side, North-South (AE-PC19-2).
2.0
I•
I. 0
I
• 11 II ,
• l _.._1_1 _L
-~~~~1, 1, 11 • 11~ 0.0
I
-I. 0
I -2.0
-0.05 0.00 0.0~ 0. I 0 0. 15 0.20
TIME A~TER RUPTURE ISECONOSI
Fig. 25 Acceleration at primary coolant pump 2 north side, vertical (AE-PC19-3).
32.
-2.0 L-~~~~~~~-*~--~~~_.--~._~_.~--~~~_.~~._~~
-0.05 0.00 0.05 0. I 0 0. 15 0.20
Fig. 26
2.0
TIME AFTER RUPTURE ISECONOSJ
Acceleration at bottom of reactor vessel, west side, East-West (AE- RVl-1).
-2.0 ~~~_.~--6-~~~----~~--~--._~_.----~--~--~--._--~
-0.05 0.00 0.05 0. I 0 0. 15 0.20
Fig. 27
TIME AFTER RUPTURE ISECONOSJ
Acceleration at bottom of reactor vessel, west side, East-West (AE-RVl-2).
33
2.0
I. 0 J
J II II ·-
~ z 0
;: 0.0 "" 0:: LLI ...J LLI u u
"" • ~ I ~. v
"'' l'
~ llllr I I •
r-· I' P I 1
-I. 0
·---1'--
.-2.0
-0.05 o.oo 0.05 0. I 0 0. 15 0.20
TIME AF'TER RUPTURE ISECONDSI
Fig. 28 Acceleration at bottom of reactor vessel, west side, vertical (AE-RVl-3).
0.0
(;
"" 0
!;;: -I .u 0:: LLI ...J LLI u u
""
-2.0
-3.0 L-~~~~~~._~~_.~--~._~~_.~--~~~_.~--~._~~
-0.05
Fig. 29
0.00 0.05 0. I 0 0. 15 0.20
TIME AF'TER RUPTURE CSECONOSJ
Acceleration at bottom of reactor vessel, north side, NorthSouth (AE-RVl-4).
34
-2.0 ~~~~--~~----~--~._~~--~._----~--~~~~--~._--~
-0.05 0.00 0.05 0. I 0 0. 15 0.20
TIME AFTER RUPTURE !SECONDS>
Fig. 30 Acceleration at bottom of reactor vessel, north side, NorthSouth (AE-RVl-5).
.... 0
s ..... _, u.J u u ...:
I II I I
J ll-11 I I 1 t-o+-o+-+--+ .... tfl ~~ttlllllltHtnlttM kA lltl ~ ..a.1 ~ ..&.. ...r..... 0 .
0 J-+--+--+-t---iF-ifHflliiHfttlll H IWW ...._· r-+'-111.._.'__.+-'-1--+-___, .r--+·---i.., l--+--+---+--t---+--iH--1ffilltttt H r 1 r r II ..,
I
-2.0 L-~~~--~~~_.~--~~~~--~._ .. _.~--~~~~--~._--~
-0.05 0.00 0.05 0. I 0 0. 15 0.20
TIME AFTER RUPTURE !SECONDS!
Fig. 31 Acceleration at bottom of reactor vessel, north side, vertical (AE-RVl-6).
35
z -..... z -:J
z -< a: 1-Ul
100.
75.
50.
2S.
,, IIIII I .111
o. -0.05 0.00
I
II l
li'l~ lift
1nm II
I
0.05 0. I 0
TIME A~TER RUPTURE !SECONDS!
...J 1n1t
.I II IIJIIIU lftiiU. II 1'1 II
0. 15 0.20
Fig. 32 Strain at reactor vessel broken loop cold leg nozzle (SE-BLB-1).
75.
- -. 50.
z - 25 . ..... z -:J
- !1· y _j ... t1 J [l
I
~~ ll l1 1.11 II
r..l M I M I lllfll'l , ~ J'l I r II .. ~
" ~ I IIIII I [1 z o. - u I''J' < a: 1-Ul
I ltl~ ··--·· .. ···-··· ..... -······· --···. -·-··· ·-··--···-- -·-··---I \I'
-25. I
........ ··-····. ··-. ····-·- ·····-· --· -50.
-0.05 0.00 0.05 0. I 0 0. 15 0.20
TIME A~TER RUPTURE !SECONDS!
Fig. 33 Strain at reactor vessel broken loop cold leg nozzle (SE-BLB-2).
36
75.
-50.
rtj ft
z -..... z
lo VII !IJr Ml 1 nl Ill 1\11 JV \ I~ lA vv
' • In -::::> 25. . .. . . , I I ~
I l z I ~ \ ~IJ -< a: ..... (/)
0.
I
A~ ~ II II JJ v '
"
-25.
-0.05 0.00 0.05 0. I 0 0. 15 0.20
TIME AFTER RUPTURE !SECONOSl
Fig. 34 Strain at reactor vessel broken loop cold leg nozzle (SE-BLB-3).
50.
I
0. A ~~ tit _u,, JU 'V ~ v ' r\11
• z liJ ... ..... z A ' '" -::::>
-50. al l\ I f\} II II l U' ~ \J v V\ ,J, 'I " j
""' II'\ (\j
z \IY ~~ 1f \ fJ I \ll \l -< v ~JIV \ I ~
,, 1/
a: ..... tJI lil 'l (/)
-100. v
'
-150. . ..
-0.05 0.00 0.05 0. I 0 u 15 0.20
TIME A~TEA AUPTURE !S(CONOSl
Fig. 35 Strain at reactor vessel broken loop cold leg nozzle (SE-BLB-4).
37
75.
!
• J ft ( II~
50.
'" A .z
' 25.
1n MI. ~ I
z -::>
N Lll II .....
z 0. -<(
- u II 'I
' -- ·rn II
a: 1-Ul
I w VI I
-as.
-
-!:!0.
-:-0.05 0.00 Q.05 0. I 0 0. 15 0.20
TIME AFTER RUPTURE !SECONDS>
Fig. 36 Strain at re·actor vessel broken loop cold leg nozzle (SE-BL8-5).
z -., z -::>
z -<(
a: 1-Ul
150.
--1--
1 00.
50.
--
A.,
0.
··50.
-0.05
J .ru '
-·- .
l .l n tn 1\ v~ IJ1
~ UV' W\1 Y rr ' II' VI¥
I A
""' "' 1'1 ll "''I . I
I~
" J A 111n t\
u ~
. .
0.00 0.05 0. 10
TIME AFTER RUPTURE !SECONDS!
11 f~ r \/ I I' M If u ~ ' &J ' I
,, 1
0. 15 0.20
Fig. 37 Strain at reactor vessel broken loop cold leg nozzle (SE-BL8-6).
38
100.
7'5.
z '50 .
z - . 25. <(
lr 1---(Jl
o.
-25.
_J_l l ~
··- ---
-----
-..
lA.
-0.05 ·0.00
n11 ·- -.. iJ. LJ !\J II I'
,.,_
fl II I
1\ f1 I
IV
..
0.05 0 .. I 0 0. 15 0.20
TIME AFTER RUPTURE <SECONOSl
Fig. 38 Strain at reactor vessel broken loop cold leg nozzle (SE-BL8-8).
75. -~-----1 I
I -------- --.. ___ --.. t-
'50.
z ... ~51 z
-·-- --I- f -----r-- M
llr -- f-- , II I' -- -- II v r '\
::J
z o. <(
~
11 II lr I-(Jl
~ ' I u 1
-25.
-50.
-0.05 0.00 0.05 0. I 0 0. 15 0.20
TIME AFTER RUPTURE <SECONOSl
-Fig. 39 Strain at reactor vessel broken loop cold leg nozzle (SE-BL8-9).
39
!50. I I
100. r l. fi • It z t--
[I ilfl, ~- I!] ! l ru ......
z ::>
50.
,, v .n • ~ t--- rv ' ..
It z A <{ ~ Ia f\ a: 1- rr V' IJI
(Jl
0. ~ ~ . .. .
.. . ---50. I
-0.05 0 .. o 0 0 .. 05 0. I 0 0. 15 0.20
HHE AFTE"R RUPTURE <SECONDS l
Fig. 40 Strain at reactor vessel broken loop cold leg nozzle (SE-BLB-11).
!50. W--. .1
I
'· --
100. ... .. .. _j
,, z ll l~ li II I II
' r II u· I M v~ . z - 'l . . ' . ::>
50. ~ l
z -<{
a: 1-({)
0.
a I NOTE: Machine error in-Jl II ·n
processing data ~
Ill lA, ., plot.
' ,,
~ ·-·-
·~ ~- .. _
--··-
-50.
-0.05 0.00 0.05 0. I 0 0. 15 0.20
TIME AFTER RUPTURE <SECONDS>
Fig. 41 Strain at reactor vessel broken loop cold leg nozzle (SE-BLB-12).
40
z ..... z ::J
z <C(
a:: lUI
50.
25.
0.
-25.
i I,! ! -·- rt-+-+-1--+--+-l--+--+-+---+-+--1----J-....1..--t- +-'-+---..
1-j . -+-+--f-1---.J-+ --+---+--+-1---+---1--+--+--J.-·l--+--+--+-!---lll-4!1-lft
~--r·-r-+--+--+-+-+-+-+-4~~~~~~+--~·+-+-+-+--+-~IA~~ I"'
I A Ill~ 1 u 1 ., ~ rw
II j N
-0.05 0.00 0.05 0. I 0 0. 15 0.20
TIME AFTER RUPTURE CSECONDSl
Fig. 42 Strain at reactor vessel broken loop hot leg nozzle (SE-BL9-l).
25.
0.
z ..... -2~. z ::J
= -50. <C(
a:: l-UI
-75.
-100.
'' .r
-0.05
n. 11 Ul Ill
111 'I
. -
0.00
. ~. JIIM Tm'l I II
~
~ I ~. Ia ~~ .,
1.1 T •' '"' • I PI\ ~ II l~ ;Tj ll IRI l "l l
IV II' 1W Ill ~, 'T IT 'I rll/1' I lUI _I
-- ...... -- __ .'' . ....
0.05 0. I 0 0. 15 0.20
TIME AFTER RUPTURE CSECONDSl
Fig. 43 Strain at reactor vessel broken loop hot leg nozzle (SE-BL9-2).
41
75. I I
f- :=J: --
50. ~ . It L z -
] Jlir n lTf Jll!IJ "' ~
..... z j " -:J
25. .II rn- r II
z l ~l a. II i -<( r-v ~,, II a: 1-til
o. I .A li ' 1~/
r; lu /VI r AI YV
1J II' ' v
....
-25. i -0.05 0.00 0.05 0. I 0 0. 15 0.20
TIME AFTER RUPTURE CSECONOS>
Fig. 44 Strain at reactor vessel broken loop hot leg nozzle (SE-BL9-4).
150. i
+I i
.. • I J
I 00. I /lo AI .. 71 l~ r' ~ IV\. lafil ~ II\ 11 A n J\1 Ml rr 11 l v 11~ "J v 1
z -..... z
1 rr I v ~If I-
~ If -:J 50. A ~
n I lA
z l J IV 1
-<( {\ ~JV a: 1- A lA I II /It vI' Ill
0. I All Ul w.. lq " II --·
'\ ~ llf IU I'
-50.
-0.05 0.00 0.05 0. I 0 0. 15 0.20
TIME AFTER RUPTURE CSECONOS>
Fig. 45 Strain at reactor vessel broken loop hot leg nozzle (SE-BL9-4).
42
75.
-- ,_ ----
·-- ·-
-----·
·--
50. u ·-· •• '1.1
z
' z ::>
25.
M ~ f-- -
w Ia, II II" 111 n 1 f-- -·--
IV tAi 1' vv I I all' I ~
z - l ~
<(
a: .....
~ ~ IN p
lll I~ u.
-
-25.
-0.05 0.00 0.05 0. I 0 0. 15 0.20
TIME AFTER RUPTURE <SECONDSl
Fig. 46 Strain at reactor vessel broken loop hot leg nozzle (SE-BL9-5) ..
100. --1--J.-.
-~~~-+= .. 75.
r- .I IJ IIA llU 1 J
z -~. '10. z
1--· ~
~
" -::> J II \ J.n [
t\1 ~ I ~--,,
-z
25. <(
I~ ~ A ll I. 1\.
a: ..... lll
llJ rt 1\ n ~ II , IJ
v I V'
0. v II 1
---25.
-0.05 0.00 0.05 0. I 0 ·o. 15 0.20
TIME AFTER RUPTURE <SECONDSl
Fig. 47 Strain at reactor vessel broken loop hot leg nozzle (SE-BL9-6).
43
50. ! : ! ! ! I r-+-·· -+~ ---+-'· --·l ···-i ·- 1- -t- --r-- --·-c-~-
--+--j -·-+ --1- --r------ ·- ~-~-I-- ··- - --
--- ·-
o.
I 'V f-- -· -- --II .fl ' J
' I' ~l j ~ J
z
' z
\ 11 ~- \ j} /l ~ 1'1
·-~- - ~-ll. I~ 1\J U' ~INV
~ v J\, -, \1 'vJ ft A :::> -50.
z
- - -· lJ1
,.,, lW ~
--t 't I ~ v v
---r <t a: 1--~--1--lfl
-100.
--
-
-150. --
-0.05 0.00 0 .. 05 0. I 0 0. 15 0.20
Fig. 48
50.
25.
z o.
= -25. <t cc: >-1/J
-50.
-75.
TIME A~TER RUPTURE cSECONDSJ
Strain between pump and steam generator simulator (SE-HL27-2).
- ! .:-.1--~-:-~~~~= ~+=-- _-tt--~ --+--t--t-~f+--Jt-1- I-='=:= --+~--+---t---1 ---tl--- ~---t---t---- -+--- --, J " · ·- ·r--1·-- c-- 1 +-t-+--+--+--+-tt-t--ri'Mt-......,r-·-ftl-+---.--+-f----+--tt----1
I !
.J
1\
,
I - -t--1+-f-+--t---i--+--t---+--t-+-~~--+-+·-+--+-+--1--1--l---1
----1 I I I I I I
-0.05 0.00 0.05 0. I 0 0. 15 0.20
TIME AFTER RUPTURE CSECONOSJ
Fig. 49 Strain between pump and steam generator simulator (SE-BL27-4).
44
'T
100.
l-
50. 11.. {
f\1 ~ PJ ' z
..... 0 . z
11\. ~ r \ .Jv. M ~. .I lA "" N _i
' ""V "'" "\-' tJ ~ 'J' \ I 1ft. v
''" 1 t
:::) \ 1 \ - - -\. ' z
-50. < a:
.J l"t ~ / lA
1-Ul \L
"11 ,.. l l ~
-100. V"t .I rw ~
- . ..
-150. I
-0.05 0.00 0.05 0. I 0 0. 15 0.20
TIME AFTER RUPTURE CSECONDS>
Fig. 50 Strain between pump and steam generator simulator (SE-BL27-5).
25.
o.
z ..... -25. z
= -50. < a: 1-Ul
-75.
-100.
1\1 ID
11
-0.05
Fig. 51
~ I
!II
" L I
II II.. II .AI l , ftl ftftllrN
II J I . 'Ill ' II ' •• w J I .,
lll'lil I ••• I I PI rllll
Ji
Ill 'I L l
' II. Jll JW \a M
.I ll' I u ~ ~ I' I~ Ill
1'1
0.00 0.05 0. I 0 0. 15 0.20
TIME AFTER RUPTURE CSCCONOS>
Strain between pump and steam generator simulator (SE-BL27-6).
45
25. !
·- f---
1-
" ·-
.J.
0. 1\J 11 n ~ ,, ~\ ~ .~
z. -'
If' I ~, u 1\
·u '\' . .li. Ill ..... z ·fl ~ -:::l
-25. I .. IJ ' ~la
"' IJ. [~ IV1.. 1 z j ' lJ 111 -< 0! , .. 1n
-50.
WI ~ IT ~A ~ . ~H. 1 "I . Ill I
~ fi·
' -75.
-0.05 0.00 0.05 0·. I 0 0. 1'5 0.20
TIME AFTER RUPTURE !SECONDS>
Fig. 52 Strain between pump and steam generator simulator (SE-BL27-8).
--··- - -·~-... ·······. lJ II
0. ··-- - ....... ·-
Ill kl 1n l IW · ll 1~.
z I u ~
-. , z
... -·· - . ' ~-- .. .. . .
-~ ~' ~ -:::l -25. 'I I~ Ill !U
~ ft I,Aaj ~ .A ll ~ J z .A I~ " ~ ~I ~ I ru• l.!J. [11 -<(
0! ~
U)
-50.
'1'1 IUM \~ .
'Ill ·~ \II l
-
-75.
-0.05 0.00 0.05 0. I 0 0. 15 0.20
TIME AFTER RUPTURE !SECONDS>
Fig. 53 Strain at reactor vessel intact loop cold leg nozzle (SE-PC4-l).
46
40. I . I
: I 30.
I
20.
z -..... z I U. -:::>
~ T I ~ ~ '\I
1~11 :' . ..
~ II ~
..
~ z 0. -< ~ 0: 1-Ul -10.
-20 .
...,.30.
-0.05 0.00 0.05 0. I 0 0. 15 0.20
TIME AFTER RUPTURE !SECONOSl
Fig. 54 Strain at reactor vessel intact loop cold leg nozzle (SE-PC4-2).
150.
100. ~A \ .. ~ Ill ~~ IV LJ~ MY ,A . 'I A
"' A. '\I U\r ~ 'U j•l, r z - lNJ N . nJ Ill~ ~ .....
z -- -.
"' ~ ' -:::>
50. .Itt IM L ' z 1'1"\ -< a A I~
0: 1- JVl Ul
o. N A 11 . .. ll ~ ' ·~ _, r1 U\J ~
' l n
II
-!50. ..
-0.05 0.00 0.05 0. I 0 0. 15 0.20
TIME AFTER RUPTURE !SECONOSl
Fig. 55 Strain at reactor vessel intact loop cold leg nozzle (SE-PC4-4).
47
z
z -<(
a:
""" l/1
75.
50.
25.
0.
-25.
-50.
-- --~-- --1-- ---i---11--t- f--··--- - -1--·- -+--+---+-- --l---1-f--l---+----l--+--J--+----l--+-+---+---l-+-+--+--1 - --+--+--+-t-1·- ··-- ·--f--+--l--t---11---f--+--+--l'---+--4~-+--l--+---1--f---l
---------f-+-~-4·-~-+--4---l-r--+--+~-~-+--+-+---l-f-+-+~---+--l
-- -- --+·--t----tt----1--t--l--+-~l--+--t--t---i-f--t--+---t-tt---fi--t---i--t--t--f
- -- - r-- -:---- --+-+--4-~-+--+--+--f--H--t--+-ttt-ft--t--+~-r----f -+-t---+--
1 II 11111 11 ll n 1\ II ~ U1 1.1
IIIlA v '" II' ,, ~ 1ft I ,. 1\
II II. lA
••
I
-0.05 0.00 0. 05· 0-. I 0 0~. 15 0.20
TIME AFTER RUPTURE (SECONDS!
Fig. 56 Strain at reactor vessel intact loop cold leg nozzle (SE-PC4-5).
I 00. --+- r· t- r---- ----'=+ --(-·~-- --·- 1----
---- r-- -- -75.
-- -II -
I j J'l --- --
50.
, .. 1'1 I \I' I I I --- II Ill
z -N JIJ A l\11 'II
' z ·~"~ Ill' r11 'II I
--,,
II lUI j :::> 25. llllUU
" lA iM" -Ill lA. z <(
a: 0. I-
" ~
en --' ---
-25. r-- ··--.
--·-·· ... ... . . -·.
-50.
-0.05 0.00 0.05 0. I 0 0. 15 0.20
TIME AFTER RUPTURE (SECONDS!
Fig. 57 Strain at reactor vessel intact loop cold leg nozzle (SE-PC4-7).
48
~ tOO.
z -' z -::>
50.
150.
. ···-..+ ·--- --+ I ! --+--~-------~--- :---
~ I--+ 1 -! ll 1---1- - --1--- --
I (\ ~ n II II - --
1--~---- l I' II ¥1. II'' -r ,., \ft ll I ~ ~-+-- -!- "-ll \ I~ I
----~-i 1\ lA a 1 1----!--t--
M V UIIVI I
' I z IJ -<{
a: I-
I -,I 1.1 11'1 II
(/1
0. ~ IJI ~
f I
-50.
-0.05 0.00 0.05 0. I 0 0. 15 0.20
TIME AFTER RUPTURE (SECONDS>
Fig. 58 Strain at reactor vessel intact loop cold leg nozzle (SE-PC4-8).
30.
f--
20.
I f-
~ l I. It l'
z
' z -::>
I 0.
z -<{
II J l'l ~ IU
~ ' 11M ~ IJf f--• ~ I
IMI I •• _,., , ._ I 'I
a: I-(/1
0. ~ I Ill
., . I"' I
-I 0.
-0.05 0.00 0.05 0. I 0 0. 15 0.20
TIME AFlER HUPlUR£ !SECONDS>
Fig. 59 Strain at reactor vessel intact loop hot leg nozzle (SE-PC5-l).
49
30.
rl\ ~ .I
20.
Ml ... J ,~I ..... ILfll .J.J I(_ A. AJ ' 'IV y \8
.. .. Jl \1 !\... ,. w
~ z
~ M ..... z J 'l.t, I.M :::> I 0. tlJ ..
~ ' ~ I'
z I' -<{ r a: 1- ..., M (Jl
o. l wA .N I 'tf' l1' 'V "
II' . ·~ . ~
-10. . .
-0.05 0.00 0.05 0. I 0 0. 15 0.20
TIME AFTER RUPTURE <SECONDS>
Fig. 60 Strain at reactor vessel intact loop hot leg no-zzle (SE-PC5-2).
z ..... z :i
z -<{
a: 1-(Jl
50.
40.
30.
20.
I 0.
0.
··I 0.
-0.05
L
liMI
. .
r .. R. J JW '\W ..,..
r r'I'\.J .l"'l A.. .If , l .l. J(
#I ....,
I J ,... lt"
~ II
... I
I l J ,,
'\.\.
"'
0.00 0.05 0. I 0
TIME AFTER RUPTURE <SECONDS>
I ...a r l!..
.f' rr'. \ i.J . ""' .... II'
0. 15 0.20
Fig. 61 Strain at reactor vessel intact loop hot leg nozzle (SE-PC5-3).
50
I 0.
0.
z , -I 0. z ::>
~ -20. < a: .... (f)
-30.
-'+0.
~-1--'--·· I---
lA.&J ~-
-0.05
.tt ~-- .., ~
.. Y\
1
.L J.. f"
IJ 1 J L / ... \1 L v IJ I\ fl
II\ -~ " I f\J 1\ .!"\ I, II 1r J J. 1
"' '11
----- -
0.00 0.05 0. I 0
TIME AFTER RUPTURE CSECONDSl
-
,._ A I~ \ af \[
. ... J rv
' IJV v \1" 1\ •
\ J v
0 .'15 0.20
Fig. 62 Strain at reactor vessel intact loop hot leg nozzle (SE-PC5-4).
50.
_jj~ .. A J -.~. ... IN 1/W V\ ~ ~ t.t -··
·r. fi ~ 1ft' ~~ I" ,,. '+0.
, 30. z
·- , I
I ..... z ::> 20.
z < n: I 0. .... (f)
II -
l rv\ r-~~ {
1/
0. .tl . doth .l.. .J .. .... . ... "~V ~r·
-I 0. i -
-0.05 0.00 0.05 0. I 0 0. 15 0.20
TIME AFTER RUPTURE rSECONDSl
Fig. 63 Strain at reactor vessel intact loop hot leg nozzle (SE-PC5-5).
51
125.
100.
75.
50.
25.
...... : 0.
I
! ·:
t ~ -v-;; -~. -· ... - - -
; -)!: ... ~: ... : ..... . ;;.;~· ..
-- ·t . - ~ -
-v~---:_·-· : .. ; . ~ ..
... . . -~- - .
• ,.-- . • + •• ··!· .... . -- ----·· ..... ····r -- . ···I-· . • .... .j.. -- •
-25. I
-0.05
Fig. 64
20.
I 0.
0.
I 0.
-0.05
Fig. 65
. ! . ~ .. ! --···:·- ··i·· ... -··- t.
' ~ - - ...•.. t
0.00 0.05
. -· ..... - ·- .... ···- .... I I
0. I 0
TIME AFTER RUPTURE rSECONOSl
0. 15 0.20
Strain at reactor vessel intact loop hot leg nozzle (SE-PC5-6).
__.
-~ -- ··-. ----~----- _ _;_ ___ --- ...... - ..
-r- •.• ..; . --r --~-- ................... ·- ...
0.00 0.05 0. I 0 0. 15 0.20
TIME AFTER RUPTURE (SECONDS>
Strain at reactor vessel intact loop hot leg nozzle (SE-PC5-7).
52
'JO.
-- ~- --1---1-- ~- .. 1·- llr.AI La. 1111 ,.JlJftl'&
~- H~11lLJ ~M.. 1111. r ·, ,
'+0.
30. z
' z
.... • 1- L'llll ·' ·-f-• 1M. ...,,
• 1\_ .. T
:::> 20. .I •
• IL •• z ,,.... < a: I 0. 1- .. lll Ill'
..allr
o. I
'I" l,Jit" ~ .. ............. .,
-10.
-0.05 0.00 0.05 0. I 0 0. 15 0.20
TIME AFTER RUPTURE CSECONDSJ
Fig. 66 Strain at reactor vessel intact loop hot leg nozzle (SE-PC5-8).
'+0.
30.
z
'· ?0. z :::>
z I 0.
< a: 1-lll
0.
-10.
-0.05 0.00 0.05 0. I 0 0. 15 0.20
TIME AFTER RUPTURE CSECONDSJ
Fig. 67 Strain at reactor vessel intact loop hot leg nozzle (SE-PC5-9).
53•
25.
0.
~
" z
~ .. .tr~
-:::> -25.
z -< a: ... '/'!
-50. ·~ I""' I ' 'I
-75.
-0 .. 05 0.00 0.05 .0. I 0 0. 15 0.20
TIME AFTER RUPTURE ISECONOS>
Fig. 68 Strain at reactor vessel intact loop hot leg nozzle (SE-PC5-10).
50.
u 40.
30. z
' 7, -:::> 20.
z < 0: I 0. 1-(f)
o. ""'" '"'T"
-10.
-0.05 0.00 0.05 0. I 0 0. 15 0.20
TIME AFTER RUPTURE ISECONOSl
Fig. 69 Strain at reactor vessel intact loop hot leg nozzle (SE-PC5-ll).
54
150.0
100.0 / ~ -r..-"
v z / .....
z -:::> 50.0 v
/ ~
z v <( I a: 1- / (/)
o.n v
-50.0
-0.05 0.00 0.05 0. I 0 0. 15 0.20
TIME AFTER RUPTURE <SECONDS!
Fig. 70 Strain at reactor vessel intact loop hot leg nozzle (SE-PC5-l2).
100.
-,~ \. It! ~ I 75. J - ,_
~ ,. \. ,}<.. /4r ....
1,1
z '· 50.
I 1/ ..
z :::> I
I v
z 25. <( I a: 1-(/)
J 'I If -·· -·"· .... ,~ ·-·· -·--
Q. r\ j
I'"\ J
·--- ~
-25.
-0.05 0.00 0.05 0. I 0 0. 15 0.20
TIME AFTER RUPTURE <SECONDS!
Fig. 71 Strain at steam generator inlet nozzle (SE-PC14-2).
55
150. fWo A v !\.,
' 1/ " J i ,. \~ ~ ~
I 00. v ' .A. La
/ .., ~ -z - j
' z I -::::> 50.
j
I z 1/ -~ a: ~ I Ill
0. l.f
- .. .. . .. . -·-·· -~·· - - 1-
-50.
-0.05 0.00 0.05 0. I 0 0. 15 0.20
TIME AFTER RUPTURE <SECONDSl
Fig. 72 Strain at steam generator inlet nozzle (SE-PC14-3)~
20.
-
10. j 1·-- -
z ,,
-' z l -::::> 0.
z ,...., ~ a: ~ r.n
- I 0 .
M L. M I~ IIIII ,l W· l. I .jP' . ' ~ ,, 11 ., , fffLyJJ ., '
' I m I
-20.
-0.05 0.00 0.05 0. I 0 0. 15 0.20
TIME AFTER RUPTURE <SECONDSl
Fig. 73 Strain at steam generator inlet nozzle (SE-PC14-4).
56
100.
75. r"r11L Jf \. ....... ,,...
WI .. ,.. Ia ..III 1_., , .. ~ n! "- ... .. ,,I"'
z
' 50.
I.a. rr 1' 1 .. 11 i"-" .. rrn z :::>
!If
• , z
25. r• <(
a: 1-(/)
I
' .. o. I. ... .. ,11-~
•p , •. IP'
-25.
-0.05 0.00 0.05 0. I 0 0. 15 0.20
TIME AFTER RUPTURE !SECONDSl
Fig. 74 Strain at steam generator inlet nozzle (SE-PC14-5).
150.
tl' w ...,.. 'W T Tr Tr-""' ... """'
.,.
-" A
100. " If''"' IJ'
z -j
I ' z IJ :::>
50. 1
z 1/ <(
a: 1- J (/)
0. .... ,.
-50.
-0.05 0.00 0.05 0. I 0 0. 15 0.20
TIME AFTER RUPTUR~ ~~~CONOSI
Fig. 75 Strain at steam generator inlet nozzle (SE-PC14-6).
57
20. 1:·- " -J.
tA I 0.
., J I' I
~-· ..... z • li
1 '• ···~. -::::>
0. JIL
z -~ a: f-Ul
-I 0.
f'll ~ _. " " ~· ~~ lJ J..
A~ I II II ~ -I•' Ill I'"_L H ll • , ,. "' • •• u
U_J'I'" ' ,. l
'
-20. . -o,. o~. 0.00 0.. I 0,, 0 0 1,5 0-.20
TIME AFTER RUPTURE (5ECONOSJ
Fig. 76 Strain at steam generator inlet nozzle (SE-PC14-7).
100. '
I '::J • .A
I/ ["\.,. ~ -- ---_L
--~
"""" 1/ v ~ ~ r-~
z :.r - 50. •.
I -z . ~
::::> .I ,. 1'
z 25. -~ a:
/ f·
f-Ul
l o. / -
.:'5.
-0.,. 05 0.00 0.05 0. I 0. 0 0 15 0.20
TIME AFTER RUPTURE (5£CONOSJ
Fig. 77 Strain at steam generator inlet nozzle (SE-PC14-8).
58
200.
-
150. .,..~ _,... ~
~ v /
z -' 100. z ,I
:::> / /
z 50.
<(
I 1
a: 1-lll
I 1/
0. /
-50·- -. ~ -0.05 0.00 0.05 0. I 0 0. 15 . 0.20
·TIME AFTER RUPTURE lSECONDSJ
Fig. 78 Strain at steam generator inlet nozzle (SE-PC14-9).
30.
'" AJI'I ..A J,j 11 \ Ia
20.
f4 \ " ' ,.,
I J \ r .,. z
·- I 0. z
• ,. ( 1\ 1 I L I \ I t"
A. , J " J '" :::> " I. I I""
.,. I - ·-
II ,.\ 11 I 1f 11 1,., ..
z ·o. <(
.J.. ·"'-ll' 'Wll "\
a: \ 1-lll "'I\. 1
\ r -10.
II I
-20. . -0.05 0.00 0.05 0. I 0 0. 15 0.20
TIME AFTER RUPTURE lSECONOSJ
F·iy. 79 Strain at steam generator 1nlet nozzle (SE-PC14-10).
59
z
z < a: 1-Ul
z ..... z ::>
z < a: 1-Ul
150.
_,j. -r--
L.t. v 100.
I
50. J J
I
o.
1----l--+--+---4--lf----+--+--+--+--+----4-+--+-+--+-+-·· ·---- -·-+--+---i-t-+--1
' -50. ~._~~--~------._._._~--_.--~--~._~~~_.--~--~
-a·. 05 0.00 0. 05 0. I 0 0.15 0.20
TIME AFTER RUPTURE !SECONDS>
Fig. 80 Strain at steam generator inlet nozzle (SE-PC14-12)~
50.
·'
40.
30.
20.
-·
~~ n ~
I .. J. _, ,·. ' '
" I~~ ~'-· f lJ· 'I "l ~ IV w I' :~. ~I~ fA
A~ ..
~ '1'~
I 0.
o.
~- '" ~ ~ ~ll I ~
:
J "V ·v ., . hi'NM 1'~1\11-
.
II
-I 0.
-0.05 0.00 0.05 0. I 0 0. 15 0.20
TIME kFTER RUPTURE !SECONDS>
Fig. 81 Strain at steam generator outlet nozzle (SE~PC15-l).
75. '
•• 0 II ~~ ~ I m1 lA I. I '11
Ill "WI ~· '\ 'IJL.J 1 J. J' 1 lll"'f
50.
"' ~ M I
z M \ -·- 25. z
II laJI -:> rv
IJ
z o . ... <{ II .It • a: 1-lll
-25.
.... , Ill m M iii p• n n II rf
II r r1 I'H fl I
-50.
-0.05 0.00 0.05 0. I 0 0. 15 0.20
TIME AFTER RUPTURE <SECONDS>
Fig. 82 Strain at steam generator outlet nozzle (SE-PC15-2).
150.
1--A
~ J.j f\ I ~~ lA1 1'1..& ll l
~ IN. ll ~ ., W'l 11 I .. Y I'V' r(Jf
100. L /Y II .N~"
z - " u~ h. 1 r T ' N 1
' z ' -:> 50. AN'
l/ z -<{
a: 1- J ,}J lll
0. Ia A lAfi ~~ u I I V 'j r vv ' rv 'V' ~· .
-50.
-0.05 0.00 0.05 0. I 0 0. 15 0.20
TIME AFTER RUPTURE !SECONDS>
F1g. 83 Strain at steam generator outlet nozzle (SE-PC15-3).
61
60.0 . .. - .. '
f--
50.0
40.0
z ..... z 30.0
::::>
l ~
,M .. ·. ~ A J
~ ' - .
z 20.0 -<{
II IJ IM~ ~ 11 r• ~ a: r-\1) I 0. 0 _, ....... ... '··"'
0.0 .. ·-··· -- .... -
-10.0 - -:-9-Q!:? 0.00 .9·9? . 9. 1.9 0.20
TIME AFTER RUPTURE !SECONOSJ
Fig. 84 Strain at steam generator outlet nozzle (SE-PC15-4).
100. .
·- ----
7!'1.
. I II AI
z ..... 50. z ::::>
lA 1\ It II ~
"" I' I I IJ I Ll Ul " I I I Ill U' l.n Ill I "'I t ~ V¥1 , \J v l
r II 2 25. -<{
.J v IL ···•···
" ' a: t-Ul
a1 II II " IJ If U1J I' 11. L!.llll r
0.
... -··- -·-··. "I IJ 'r ·--- ... . .
-- ... .. ·-.. -· ..
-25. f---
I
I .
-0.05 0.00 0.05 0. I 0 0. 15 0.20
TIME AFTER RUPTURE !SECONOSJ
Fig. 85 Strain at steam generator outlet nozzle (SE-PC15-5).
-: ...
z
z < a: 1-(j)
z -' z -::>
z -< a: 1-(j)
150.
- - ·-- --
---f-·
t\ A ill ~ u,.. n 100.
J, f.tl 1 I If iJI. I '\II ~ lM l'U Mf ~ 1\ ~ft u ' v
"V\1 .I I ' p IV 1\4 VI v
- 'I v t\IJ II -- -
50. A I' n rv - -¥
- .. - .. ·-I ,I AI
o. .A Jl riA , l 1 lV" VI If I ~ VII' ll' .. '
-50.
-0.05 0.00 0.05 0. I 0 0. 15 0.20
TIME AFTER RUPTURE CSECONOSJ
Fi~. 86 Strain at steam generator outlet nozzle (SE-PC15-6).
150.
100.
50.
~-l-+- -- --c--f---t-t--tf----1-t- -t---+-t--t-t--1--f---t- - --1---t--t---i --1-- --·- :._ --t--+----+--t--f--l--11---f--i-tt--1--f--·-t-- -t---t--t--t-t---t
f-f-- -- 1-+--t-+-+-+--t--t---+--t---+-+-+-+-+- +--+--t--+-+--t--t--1
I
-1--~-~-+~-+-+~~~~~~'H'~''ILb-~~f--i-t-t~-t-t--t--t~ -~---~-~~~ll~l~~~v~~~~--~-~~-~;--+--t-~-+ ~~~~ ·~~~._~N~~~V~I'-t--+--+---+---+--1--+--+--+-+-~r-r-r-~ 1l I / I
J\11 I 1\.A. 11 0
. II rl . ~
-50.
-0.05 0.00 0.05 0. I 0 0. 15 0.20
TIME AFTER RUPTURE CSECONOSJ
Fig. 87 Strain at steam generator outlet nozzle (SE-PC15-8).
63
z
' z ::::>
z <(
a: .... Ill
z
' z -::::>
z <(
a: .... ln
200. - .. ~ ~-. - -.
-- --j-- --. -· --- -- --·--- -- 1----- ---
-···-·-I __ ·-
,. II t! I 150.
lJ lt .Ill!_ ~)j r1 -~ It\ II\ ~\ VI 'V V\1 --
I 00.
A I ~ v ' f-· Jll 1.111'
II V ),. 'V l-1 I~ IV I I r'V ~
A N 50. A
Ill
' I ,; a
o. lA II riA I Ill I. IJIUliiA lA 1 rv
IU II n 'I ~~ I' tf I'
f---50.
-0.05 0.00 0.05 0. I 0 0. 15
TIME AFTER RUPTURE <SECONDS>
Fig. 88 Strain at steam generator outlet nozzle (SE-PC15~9).
ISO.
I 00.
J .. -~----1~+-- I I __ ,_ I -- L~--~-+-- ·-f--+
i : l_j -- -t -·t -··r--i ,---t··t·-r- -- t-·
~ ! !
-+t·-f-- v ~ ·---i-- ~ I~ ····-f-- I
ill
~ 50 .
IJ IJ
~ ~
-0.
-0.05 0.00 0.05 0. I 0
TIME AFTER RUPTURE <SECONDS>
I J I
~ r
.l I~ M ll '~ w ' l\
0. 15 .
u '
Fig. 89 Strain at steam generator outlet nozzle (SE-PC15-10).
64
fl\1 y
0.20
l ~~
0.20
..
150.
'·"" 100.
z - J ~ ' z r\ ,
' -::'1 5U. II t'l M_ II II 111 ITR
V I~ I VI \\ v ~\j y \ z ~ ~
.. -< a: 1- I N (/)
0. J 11\ lA IW
f f
-50.
-0.05 0.00 0.05 0. I 0 0. 15 0.20
TIME AFTER RUPTURE !SECONDS>
Fig. 90 Strain at steam generator outlet nozzle (SE-PC15-ll).
150.
100. 11 j Ill I N
"' z - IV I r \a Aa "' ' z
........ ·--· ........
'I I~ l -::> 50.
Ill z ll -< II n a: 1-(/)
u. rJ lA [1
II ~
-50. ..
-0.05 0.00 0.05 0. I 0 0. 15 0.20
TIME AFTER RUPTURE !SECONDSl
Fig. 91 Strain at steam generator outlet nozzle (SE-PC15-12).
65
I 0.
z - -·I 0. ' z
I
I I
I II IU II' 1n
I I
:MA.~ f.' I .. I II 1 .I.
... 0.
-::>
z -eo. -<(
v ~
I _l
IIIII lUI
-I 1111
~~~ ~,~ 1'11111 ,11 'II ,.,, II IUW
IIIU II 11'1 II; 1-
II' I f 'I r ' (fl
·30.
-'+0.
-0_. ('!:5. ('). 00> Q. 1u; Q.20
TIME AFTER RUPTURE !SECONDS!
Fig. 92 Stra.in at primary. coolant pump outlet (SE-PCl8-l3).
5-0.
0.
z -a.l.u IJ
~ .I -~
\ ~~ fl'l IV .I • u·v.. ' z ' ,, rl -::.
-tiO. I
~ 1 f\J
z ~' -~ -<( I ·'I: VI ' I 0:: 1- ~ l'j ~- J ' ~ ....
·" Jl, •. 1/l
··I 00. ' 'IJj ~~ ~ ~ Vl ·n ~\ mn ~
" I' '
-150.
-0. 05· 0.00 0.05 0. I (J 0. 15 0.20
TIME AFTER RUPTURE !SECONDS!
Fig. 93 Strain at primary coolant pump outlet (SE-PC18-14).
66·
50.
---f-~-+-1-- --+ i
--~---1--
-- --·t- I - ·-,_
- -i .. ·-
M 1\J. A 1.\ II\ A 0.
, l v '
'~ " "Vl z
' -50. z
Ll\a Y' V'\
I --;:\ \
"\I\ --'lA
z -100. -< \..
'" U\ a: 1-Ul ' W\!A.
' ., 1M. \ ... hAf .r IJfl.l I'\ ~ J\. ~ l1\
-150. ' I'V 1 I •• r IV' v ~
I
-200. -
-0.05 0.00 0.05 0. I 0 0. 15 0.20
TIME AFTER RUPTURE (SECONDS>
Fig. 94 Strain at primary coolant pump outlet (SE-PC18-15).
25.
1--~ I
0. ! 'I n 1 I z - ,,~ \.U ltV M ....
z I PJ' ~ - ., ;:\
-25. llry
z . -~ LA -< , ~ a: 1- IY l Ul
-50. , ~~~~ I I v ll " ·~ ll'~ IM. ..... 1.\ II'
II ~ ~ \II tr'~ ~-'II/'
-75.
-0.05 0.00 0.05 0. I 0 0. 15 0.20
TIME AFTER RUPTURE (SECONDS>
Fig. 95 Strain at primary coolant pump outlet (SE-PC18-16).
67
z -..... z -:>
z -<(
a: 1-(j)
z -..... z -:>
z -<(
a: 1-(j)
25. - - b--t-
0. l 1
ll t ~ lA II -· II I'M IV\jj rltl.l 1 f11t ll
-25 . L 111 1.1 I .u :
v .
I L
-50. \II \1 It I
ru aft I • ~IL ~- N Ia.. l, 1\t. lLMI
lftll \1 \ ,, lJ l.nt f\ , .. !
-75. n r I n· _! 1'-'i II' : \A t-- .......
lJ
~- ·~·--- .... .. ··-~- -·~-·· ---....... _ u •• "' -~ -· ·····--1-
-100.
-0.05 0 .. 00. 0 .. 05 0 .. I 0 0. 1.5
TIME AFTER RUPTURE (SECONDS!
Fig. 96 Strain at primary coolant pump outlet (SE-PC18-17).
50.
0. j
:1\l
-50.
-100.
. 150.
-0.05
na ·" ~I U\ ~,
I
.A rv~ 'VII I A
V\1 WI v A :Ju '1"1
~an \~ !\.. Ill
" v u .& 1n ... r W' ~\ r\ MJ liVIJ
y VI
0.00 0.05 0. I 0
TIME AFTER RUPTURE (SECONDS!
LtJ l AI\ I
II' J Ju 1 '¥ n ' ·v u v . ' IVY
0. 15
1\ v
Fig. 97 Strain at primary coolant pump outlet (SE-PC18-l8).
68
0.20
.. l
lf1 I .
~ 1/.
' 0.20
50. · I 1 -·-·:-----r--r-r
---:-·- i ·-·- ·--·-•u-•t•·-i- ··--1-+
25. .. f ~; II. I UY I II II
0. z Ill lllf
"\\I lVI II
' z :::)
-25.
I Ill Ill
rC .II
z 'I II~ ll .A
UJII II IJI II A..l la lA. <(
a: -50. .... lll
" ,, ll_ II"U li'j _._. l_"' !LV
IU 'V U'~ Ill. I I ' ·u lJ
' II 1-
-75. --··
-100.
-0.05 0.00 0:05 0. I 0 0. 15
TIME AFTER RUPTURE lSECONDSJ
Fig. 98 Strain at primary coolant pump outlet (SE-PC18-19).
50.
0.
z ..... -'50 z :::)
~ -I 00. <(
a: .... lll
-150.
-200.
! ' -··-·r--- --· ··-·~·--·
I
-··-i·-H
l,J l n. I l~ lrl v•r
--
---t -
I
--I _:
-0.05
.A lVI a.
• ~. II -'' v 1JI t--,. '1 ll
'\J II..,
lall "" ---'ti1A
v [1. II 'I\. II n
v hi' J\ .A. _h \.l IJ.. r ., _V ~· \ 11\r\t Ml.l \ II '\I I ll\IV ~
' ~ Vl 'I 'V w '
\A. ,/ ll[
,.
0.00 0.05 0. I 0 0. 15
TIME AFTER RUPTURE lSECONDSJ
--
Ia. llf
II
0.20
_,.,_, .....
fi II I
II IJI T i
0.20
Fig. 99 Strain at primary coolant pump outlet (SE-PC18-21).
69
25. 1 " I I I I
I
I J. 1ru I~
0.
II II' Ill I I
z v u ~· !J 1\.ft._ -' .... -25 . z
> ~ i~ 1 'L ft n I A 'I /\~
::) u II " ' N I )j iiJ ]j
I ' z -50. - t II
< 0: 1-(/)
. '---r-· -75.
-100.
-0 .. 0,~· 0. 00. Q. 0.~ Q,. 10.:: 0. 1·5, Q·. 2.0
TIME AFTER RUPTURE <SECONDSl
Fig. 100 Strain at_ primary coolant pump outlet (SE-PC18.,.22).
50 .. ---
o, I -- -
II\ I 'I I r 11
z -IVLWVH
IV ~ ..... z .~, -::::>
50.
z
II U1 l
·- ~ .' -~ V1 ~ A. . ~~-\ ~I IJdi·- . . ~j . Wv ft ·~ .I -< ·. lA/ '\1 ' I ~~-A, ' ~ lA
0: 1- tV 11\J w w (/)
-100. ' ' II u
-150.
-0.05 0.00 0.05 0. I 0 0. 15 0.20
TIME AFTER RUPTURE <SECONOSl
Fig. 101 Strain at primary coolant pump outlet (SE-PC18-23).
50.
0.
z
' -50. z ::>
~ -I 00. <(
a: ~
lll
-150.
-200.
: : I I -f-L - t--··r- -r---~ -- ··i=- ~r-~- ·- ·--+--c-
wv ft/ II I IV lit IV\ I I
v ~IN 'I'
LA V' -
~-tl ~: ,- -
±-· -
' .I -·
'
r.
J '\ v 'II Vll. II I
•IJJ' ll tll ll lA [\A I! A
IV \I~ /'U J!W MJ IUV ., y ' l u ~ ' '\
-0.05 0.00 0.05 0. I 0 0. 15
z
' z =>
z <(
a: ~
lll
TIME AFTER RUPTURE !SECONDS>
Fig. 102 Strain at primary coolant pump outlet (SE-PC18-24).
100.
7'3.
50.
25.
o.
-0. I 0.0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9
TIME AFTER RUPTURE !SECONDS>
,,.. u
0.20
I. 0
Fig. 103 Strain at reactor vessel broken loop cold leg nozzle (SE-BL8-l).
71
75.
50.
z .... 25 . z :::>
z 0 . .....
< a: 1-Ill
-25.
-50.
-0. I 0.0 0.1: 0.2 0.3• 0.4 0.5 0.6 0.7· 0.8 0.9 I. 0
TIME AFTER RUPTURE <SECONOSl
Fig. 104 Strain at reactor vessel broken loop cold leg nozzle (SE-BLB-2).
75.
50.
z .... z :::>
25 .
• < a: 1-Ill
n.
-25.
-0. I 0.0 0. I 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 I. 0
TIME AFTER RUPTURE <SECONOSl
Fig. 105 Strain at reactor vessel broken loop co.ld leg nozzle (SE-BL8-3).
72
z ..... z ::J
z <{
a: ~
Ul
50.
0.
-50.
-100.
-150.
-0. I 0. 0 0. I 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9
TIME AFTER RUPTURE !SECONDSJ
I. 0
Fig. 106 Strain at reactor vessel broken loop cold leg nozfle (SE-BLB-4).
z ..... z ::J
z <{
a: ~
Ul
75.
50.
25 .
o.
-25.
-50.
-0. I 0. 0 0. I 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9
TIME AFTER RUPTURE !SECONOSJ
I. 0
Fig. 107 Strain at reactor vessel broken loop cold leg nozzle (SE-BLB-5).
73
150·.
I 00.
z ..... z ::>
50.
z <{
a:: ~ lJ)
o.
-50.
-0. I 0.0 0. I 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 I. 0
TIME AFTER RUPTURE !SECONDS>
Fig. 108 Strain at reactor vessel broken loop cold leg nozz,le (SE-BL8-6).
1 00.
75.
z ..... 50 . z :J
z 25.
<{
a:: ~ lJ)
0.
-·25.
-o. 1 0. 0 0. I 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1 . 0
TIME AFTER RUPTURE !SECONDS>
Fig. 109 Strain at reactor vessel broken loop cold leg nozzle (SE-BL8-8).
74
z
' z :::>
z <(
a: 1-Ul
75.
50.
25.
0.
-25.
-50.
-0. I 0. 0 0. I 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9
TIME AFTER RUPTURE lSECONOSJ
I. 0
Fig. 110 Strain at reactor vessel broken loop cold leg nozzle (SE-BLB-9).
z
' z :::>
z <(
a: ..... Ul
150.
100.
50.
0.
-50.
-0. I 0. 0 0. I 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9
TIME AFTER RUPTURE !SECONDS!
I. 0
Fig. 111 Strain at reactor vessel broken loop cold leg nozzle (SE-BL8-ll).
75
z ..... z ~
z 1(
a: I-1/l
150.
100.
50.
0.
-50.
-0. 1 0. 0 0. 1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1.0
TIME AFTER RUPTURE CSECONOSl
Fig. 112 Strain at reactor vessel broken loop cold leg nozzle (SE-BLS-12).
50.
25. z ..... z
,J,. J
" ,.,, ~
j; Ht II
-<{
a: 0. f-Ul
1-·
-25.
-0. 1 0. 0 0. 1
M .. j,, , I • lj
I ''II L.
r• II rr·, 'WI
---~- .. -·· ...... .. ··----- I····-.-· .. ·-···
II'
_,. ;
'
0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9
TIME AFTER RUPTURE CSECONOSl
h~ ~ rr .. - ······-
1. 0
Fig. 113 Strain at reactor vessel broken loop hot leg nozzle (SE-BL9-l).
76
25.
0.
z ..... -2~. z :::>
= -50. <t ._.
-75.
-100.
-0. I 0. 0 0. I 0.2 0.3 0.'+ 0.5 0.6 0.7 0.8 0.9
TIME AFTER RUPTURE <SECONDS>
I . 0
Fig. 114 Stratn at reactor vessel broken loop hot leg nozzle (SE-BL9-2).
75.
50.
z ..... z :::> 25.
z <t 0::: ..... l/)
o.
-25.
-0. I 0. 0 0. I 0.2 0.3 0.'+ 0.5 0.6 0.7 0.8 0.9
TIME AFTER RUPTURE <SECONDS>
I. 0
Fig. 115 Strain at reactor vessel broken loop hot leg nozzle (SE-BL9-3).
77
z ..... z :>
z <(
a: 1-(/1
150.
100. ''·~ IJ Allft. 1m''' I I I ,. I IIJ 'II II '. Ill I I II ,. l
' 'II I' r-
Ul
50.
II ' ..
0. D.ll "fHJ ..
I
- .
-50.
-0.1 0.0 0.1 0.2 0.3 0.~ 0.5 0.6 0.7 0.8 0.9 I .0
TIME AFTER RUPTURE !SECONDS>
Fig. 116 Strain at reactor vessel broken loop hot leg nozzle (SE-BL9-4).
75.
50.
z -..... z -::>
2!J.
z <{
a: 1-(/1
0.
-25.
-0.1 0.0 0.1 0.2 0.3 0.~ 0.5 0.6 0.7 0.8 0.9 1.0
TIME AFTER RUPTURE !SECONDS>
Fig. 117 Strain at reactor vessel broken loop hot leg nozzle (SE-BL9-5).
78
100.
75.
z ..... 50 . z :::)
z 25. -<
a: 1-lll
0.
-25.
-0.1 0.0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1.0
TIME AFTER RUPTURE <SECONDS>
Fig. 118 Strain at reactor vessel broken loop hot leg nozzle (SE-BL9-6).
50.
II.~
0.
z ..... z ::>
-50.
z
I 'Iii Ill •• J I I I IJ .1 I '• 1 I I I
• II
~
I ,.1 I .......
'R II ' I I Ill II
< a: 1-
II I'
lll
-100. -·
-150.
-0.1 0.0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1.0
TIME AFTER RUPTURE <SECONDS>
Fig. 119 Strain between pump and steam generator simulator (SE-BL27-2).
79
z ..... z ::::>
z -Cl a: I-Ul
50.
25.
o .
-25.
-50.
-75.
-0. I 0. 0 0. I 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9
TIME AFTER RUPTURE <SECONDS>
I . 0
Fig. 120 Strain between pump and steam generator simulator (SE-BL27-4).
100.
z -..... 0 . z ~
::::>
:z= -50. < a: f··· ...
Ul -
-100.
-150.
-0. I
II
-I A
.u I I " ,,
LAo!. lJ\ I.J r ..L 'I'
'M ' II\( r .1 ... ~ I
' 1 , .L _p !L\ .... !1"11'1 J ltru ,. w J t 1'1"
jJ '" "l.. II( "ln' I' 11 •c,_.,.f.,,. .. "" .~
II A. v tl • 7" ~ •
l1 r " l IU
\ .1. .. ..... Y.. 11 \1'1
-....... ~-...... --- ···-·--······ ·-·-··· . ··- ···--- ··---~
. -·· ··----~--- ·---
... --
.. ..
0. 0 0- I 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9
TIME AFTER RUPTURE <SECONDS>
I. 0
Fig. 121 Strain between pump and steam generator simulator (SE-BL27-5).
80
25.
FW L: -r
" ~· 0.
z I I -- f- ---..... -25 . z IUt J J I -::::> I fl
It I u J •• J..l I I II z
-50. -< a: 1-Ul
IJPI ~ I
I fl ---, I
" I r 1 I p
I J I
-75. II ' II
-100.
-0.1 0.0 0.1 0.2 0.·3 0.4 0.5 0.6 0.7 0.8 0.9 1.0
TIME AFTER RUPTURE <SECONDSl
Fig. 122 Strain between pump and steam generator simulator (SE-BL27-6).
25.
0. l.t
HI .I
I I z -..... z -::::> -25.
z -< a: 1-Ul
-50.
''II I. I "T JUT J li =II ~lit t
'1 l
r il I -.1 II
lfllh liU Ul r.l IWII illftl r1 '"''
'( If I • • ~ lfll' I
I
I' 'I Jl T
-75.
- 0 . I 0 . 0 0 . 1 0 . 2 0 . 3 0 . 4 0 . 5 0 . 6 o·. 7 0 . 8 0 . 9 I . 0
TIME AFTER RUPTURE CSECONOSl
Fig. 123 SLr·din between pump and steam generator simulator (SE-BL27-8).
81
z
' z ::>
z < a:: 1-Ul
25.
0.
-25.
-50.
-75.
-0. I 0. 0 0. I 6.2 0.3 0.~ 0.5 0.6 0.7 0.8 0.9
TIME AFTER RUPTURE !SECONDS!
I. 0
Fig. 124 Strain at reactor vessel intact loop cold leg nozzle (SE-PC4-l).
z
' z ::>
z < a:: 1-Ul
~0.
30.
20.
I 0.
0.
-10.
-20.
-30.
-0. I 0. 0 0. I 0.2 0.3 0.~ 0.5 0.6 0.7 0.8 0.9
TIME AFTER RUPTURE !SECONDS!
I. 0
Fig. 125 Strain at reactor vessel intact loop cold leg nozzle (SE-PC4-2).
82
150.
I I I
100.
z ..... z
~~ .1 ,~ 1 Ill II
~I I I JJ I I I ' ::::>
50. II IP
z <
"" a: 1- II (/)
0. ~~ Ll
-50.
-0.1 0.0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1.0
TIME AFTER RUPTURE !SECONDS!
Fig. 126 Strain at reactor vessel intact loop cold leg nozzle (SE-PC4-4).
75.
50.
z ..... 25 . z ::::>
z 0.
< a: 1-(/)
-25.
-50.
-0.1 0.0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1.0
TIME AFTER RUPTURE !SECONDS!
Fig. 127 Strain at reactor vessel intact loop cold leg nozzle (SE-PC4-5).
83
100.
75.
I
50. z I.
• ..... z ~111 1 :::)
25. 1.1
• • II
z < 0:: 0. ~
lll Ml I
-25.
-50.
-o. 1 0.0 0. I
1 I
1 I I I 1 .. I. w Ll. _l
L lh _l ,u Ill lit .. 1
• IW L II I I LU
111 I III I 'I' , I
111 n ''1 I J _r: Ill I t II I I I
I I
.. -
0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9
TIME AFTER RUPTURE <SECONDS!
II I'
~
--
I. 0
Fig. 128 Strain at reactor vessel intact loop cold leg nozzle (SE-PC4~7).
z ..... z :::)
z < 0:: ~
en
I "in
100.
50.
o.
-50.
-0. I 0. 0. 0. I 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9
TIME AFTER RUPTURE <SECONDS!
I. 0
Fig. 129 Strain at reactor vessel intact loop cold leg nozzle (SE-PC4-8).
84
30.
20.
z -' z -::>
I 0.
1 ~ 1 I llll
~ All II ,,
z -c{
a: 1-lfl
o. =i1 I ,
-10.
-0.1 0.0 0.1 0.2 0.3 0.'+ 0.5 0.6 0.7 0.8 0.9 1.0
liME AFTER RUPTURE !SECONDS>
Fig. 130 Strain at reactor vessel intact loop hot leg nozzle (SE-PC5-l).
30. -.
20. ' Nloll.l .at • ~ .J I .•• J. J ... ..,j ~II J Y'l'll1V1 ~ IT .,., .. . NPwn1lf ~M
" ~ . ~' . , r " J • 1 J r J .. ~
r I ' z - ' ' z -::>
I 0.
z -c{
a: 1-lfl
0. .J.J 'll'l
'
-I 0.
-0.1 0.0 0.1 0.2 0.3 0.'+ 0.5 0.6 0.7 0.8 0.9 1.0
TIME AFTER RUPTURE !SECONDS>
Fig. 131 Strain at reactor vessel intact loop hot leg nozzle (SE-PC5-2).
85
50.
..a Ill ... 1t.U1 .. J.At ....
~ -~ 1'1J,.. ..o& • • .II. Jll,. ..
,flll"' l.f ll/~..11 ..llll 1111n J ~ lr I .1"\Jf\1 ~ liU ll''Y .. Ill • ' 1.1 ' lll I .... (_l_
' 1__)1 !I_ ll ' _I_ v ' '
40.
..... ' • r I I' 30.
z nr _I
• ' z :::>
20. II f
J z " <(
a: I 0. 1-Ul
·- ..
•• 0. .. " J. ..... ... --- ...... . . , .... -
_ ..
·-. .. .. ..
-I 0.
I ·-·
I .. ·- . --
-0. I 0. 0 0. I 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 I. 0
TIME AFTER RUPTURE <SECONDS!
Fig. 132 Strain at reactor vessel intact loop hot leg nozzle (SE-PC5-3).
1 n.
0.
z , -I 0. z :::>
~ -20. <(
II. II/)
-30.
-40.
-
-0. I
.M
·-
I Ill If
0. 0 0. I
--
..
-
• .. . .L •"' l.ll.L ..... ..... ..... ......_~ ........ r'V'P- IIYaaJl '-' 1"' I r .:"'"' rtl..,.....
-·J~~n u-.... ~ '" T .., 11'1 ~ " . . .1' II'
I ' . -- .
. . ·····
0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 I. 0
TIME AFTER RUPTURE <SECONDS!
Fig. 133 Strain at reactor vessel intact loop hut leg nozzle (SE-PC5-4).
86
50.
' .. • .. ... • .. I • 1 J ....
j~F·.,."'" 1 .. ..,....,,.... ,, ....... "'""'"'· t ,..,.,, " .. '
I~ r • 40.
30. z ...... z :::>
20.
z N < a: I 0. 1-Ill
0. .......a.! "T'l
-10.
-Q, I 0. 0 0. I 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 I. 0
TIME AFTER RUPTURE <SECONDS>
Fig. 134 Strain at reactor vessel intact loop hot leg nozzle (SE-PCS-5).
50.
40. 1
30. I z ...... z ul ,.. :J 20.
z I < a: I 0. 1-Ill
1
0. ...... T'T
-1 ·a.
-0. I 0. 0 0. I 0.2 0.3 0.4 0.~ 0.6 0.7 0.8 0.9 I. 0
TIME AFTER RUPTURE <SECONDS>
Fig. 135 Strain at reactor vessel intact loop hot leg nozzle (SE-PC5-8).
87
z
' z ::>
z c{
cr >-IJ)
40.
30.
20.
I 0.
0.
-I 0.
-0. I 0. 0 0. I 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9
TIM~ AFTER RUPTUnE !SECONOSI
I . 0
Fig. 136 Strain· at reactor vessel intact loop hot leg nozzle (SE-PC5-9).
25.
f--
u.
z
' z ::>
-25.
z -c{
cr >-1.0
-50.
f--
-75.
-0. I
.Ill .oil
n I • I J
0. 0 0. I
--
--
0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9
TIME AFTER RUPTURE !SECONOSl
I. 0
Fig. 137 Strain at reactor vessel intact loop hot leg nozzle (SE-PC5-10).
88
50.
' 40.
30. z ..... z :::>
20.
z <(
0:: I 0. 1-Ul
0.
-I 0.
-0. I 0. 0 0. I 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 I . 0
TIME AFTER RUPTURE (SECONDS>
Fig. 138 Strain at reactor ~essel intact loop hot leg nozzle (SE-PC5-ll).
150.0
··-··--- ··-------f----f- ---1-----+---+----f----~'-----f -·--.f-----1
----··-··· ··--·--t-·-----1~----t---+---+----+---·-f-·--+---+-----1
-----····· r------- ------t----t----ff----+---+----.f-------1r-----t----t
r .,
100.0 .,...,..
z I I .....
z I :::>
50.0 1 I
z <(
0:: 1-Ul
1 ---~~---- ---+-----r--~r--~--~---~--~--+--~
I
0.0
--·-- --·--~--1---+---r--~t----~-==-+----
--~------+--- ~--~--r--~r---~---+-- ---1--~
-50.0 ~--~~--_. ____ _. ____ ~----~----4----~~--~----~----~----~
-0. I 0. 0 0. I 0.2 0.3 0.4 O.!:i 0.6 0.7 0.8 0.9 I. 0
TIME AFTER RUPTURE (SECONDS>
Fig. 139 Strain at reactor vessel intact loop hot leg nozzle (SE-PC5-12).
89
\ .
z ..... z :::>
z ...,. 4: a: 1-(JI
z ..... z :::>
z 4: a: 1-•n
100.
75.
50 .
J I'
25 .
...
:J.
~·-· ....
-25.
-0. 1 0.0
~ A. ... _.... 1 !A ..._ .. , "' /Ylll ll~ ... .....,.... -v -. I"" """
Jll\ , ' I .....
j f
; 1
0. I
I IMJ
'.J
. ., .. .. . .. . ... -- ....... _ ···- .. -- --
..... ··- .
-
0.2 0.3 0.~ 0.5 0.6 0.7 0.8 0.9
TIME AFTER RUPTURE <SECONDS!
.._
I . 0
Fig. 140 Strain at steam generator inlet nozzle (SE-PC14-2).
150.
1 uo.
50.
0.
-50.
-o. 1 0.0
I
I 'l -
I
' 1 I -~A -I
(
..
0. I
"\. IJ.J - """""' ...... ~
.,~
·-·
--- .. -
0.2 0.3 0.~ 0.5 0.6 0.7 0.8 0.9
TIME AFTER RUPTURE <SECONDS!
.,
·---- .....
-·-
I . 0
Fig. 141 Strain at steam generator inlet nozzle (SE-PC14-3).
90
20.
I 0.
z .... z :::>
0.
z < a:: ~
Ul
-10.
-20.
-0. I 0. 0 0. I 0.2 0.3 0.'+ 0.5 0.6 0.7 0.8 0.9 I. 0
TIME AFTER RUPTURE !SECONDS>
Fig. 142 Strain at steam generator inlet nozzle (SE-PC14-4).
I 00.
~ _...
·~5~ .... ..,., ............ I'll j ... r.,... ... 1 ~
75.
z .... 50 . L
~ ... ~ ,
:::>
z 25.
< a:: ~
Ul
o. ....... ,. ......
-25.
-0. I 0. 0 0. I 0.2 0.3 0.'+ 0.5 0.6 0.7 0.8 0.9 I . 0
TIME AFTER RUPTURE !SECONDS>
Fig. 143 Strain at steam generat~r inlet nozzle (SE-PC14-5).
91
z
' z ::>
z ~
<(
a:: I-(/)
z
' z ::>
;z
<(
a:: !-(/)
!50. I.... . ...
liW" ........ ....... ..... .... ...- .. ....,.. ----
' ,
I 100.
, I
50.
I I
0. -~~
.... ...... .. - .. ·- ...
-50.
-o. 1 0. 0 0. I
- .. ~-- ... --- -·
.. - ~-
·- --
0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9
TIME AFTER RUPTURE !SECONDS>
Fig. 144 Strain at steam generator inlet nozzle (SE-PC14-6).
20.
·-
1 a.
.1
0. ~ J
I. 0
-I 0. ' I .. ] ~ ~ • lliR ~_..... rr .l lf ' '
" _, ' ill
-20.
-0. I 0. 0 0. I
1 ..... I r ._ ,
. . ·1---
0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9
TIME AFTER RUPTURE ISECONDSl
Fig. 145 Strain at steam gener'ator inlet nozzle (SE-PC14-7).
. 92
"
I . 0
z .... z :::>
z <(
a: 1-Ul
z
' z :::>
z <(
a: 1-Ul
I 00. --·
··- ---- f-·
I"" ... .-r J '
,...,..... ~ ,J I'... F .. ._. ~ .-..... 75.
I I' I _,
~ ...,.,., ~
I \IV" I
50. 1 I --1 r I
-
25. (
I ...__
o. .-..... .l
-25.
-0. I 0. 0 0. I 0.2 0.3 0.'+ 0.5 0.6 0:7 0.8 0.9 1-. 0
TIME AFTER RUPTURE' <SECONDS!
Fig. 146 Strain at steam generator inlet nozzle (SE-PC14-8).
200. ------ -----~----4-----~---4~----t----~----4r----~----~--~
---- f--·----+------t----------1----l-----+---+----+-----t----Jf----t
150.
I ... !
I 00 . I l I
r----~~---4----~----~----~----+---~r--~----+------t---~
.50. ~-----~~--~---------1-----+----~---~---+-----t-----Jr---~-----1
. 0. I
~--~-----+----~----~----~---~----+-----~---4~--~----~
-§0.
-0. I 0. 0 0. I 0.2 0.3 0.4 o·.5 o.6 o.7 o.8 0.9 I. 0
TIME AFTER RUPTURE <SECONDS!
Ftg. 147 Strain at steam generator inlet nozzle (SE-PC14-9).
93
30. ,-----·- --·-- ----·. ·--- ---·-· f------ 1----- ..
al 111 ILl ft. .,'L .J..JLII .. ~ ........... •IJA IU J r~ \1 l.t ,.J wn. 11.,. 'V ,.,.. ... .. , .... II ..... ..., 20. , l -J ll"J v ........ ' fT "1
-- •fll' .LII '1 z "r r ..... I 0 . z ·' ·'
IIIIJ ' ::l
l'l 1111 v
z 0.
<t
........ 1--
., " --a:
..... f--lll
-I 0.
-20.
-0. I 0. 0 0. I 0.2 0.3 0.'+ 0.5 0.6 0.7 0.8 0.9 I . 0
TIME AFTER RUPTURE ISECONDSl
Fig. 148 Strain at steam generator inlet nozzle (SE-PC14-10).
150. 1'\. "'- - --... --, .. - "V" -
I
I 00. ·r ..
z ..... z ::> 50.
z <t ' a: 1- 11 lll
o. ....--
f---· ...
--. ..
-· ..
-50.
-0. I 0. 0 0. I 0.2 0.3 0.'+ 0.5 0.6 0.7 0.8 0.9 1.0
TIME AFTER RUPTURE ISECONDSl
Fig. 149 Strain at steam generator inlet nozzle (SE-PC14-l2).
50.
40.
30. z ..... z ::::>
20.
z oC(
a: I 0. 1-lll
0.
-10.
-0. I 0. 0 0. I 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 I. 0
TIME AFTER RUPTURE (SECONDS!
Fig. 150 Strain at steam generator outlet nozzle (SE-PC15-l).
7'5.
50.
z
' 25. z ::::>
z 0.
oC(
a: 1-lll
-25.
-50.
-0. I 0. 0 0. I 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 I. 0
TIME AFTER RUPTURE (5ECONOSl
Fig. 151 Strain at steam generator outlet nozzle (SE-PClS-2).
95
15.0.
I' ~ 111 ~M11 .d .. Jl-U.l&J I.IIA.tl.1 fl1 11 r IVIJIII'Ir- .,,fl -100. 1 r" r
.tA z
,MJ' l"l .....
z ::J
50.
z < 0:: f.-u·•
o.
~ _____ ... ...... ·····-· .. .... ···- ......
--tM' -····
.. -50.
-0. 1 0. 0 0. 1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1 . 0
TIME AFTER RUPTURE CSECONOSl
Fig. 152 Stratn at steam generator outlet nozzle (SE-PC15-3).
60.0
50.0
40.0
z ..... z 30.0
z < 0:: 1-
(/l 10.0
-10.0 ~--~----~----~----._--~----~----~----~--~~---L--~
-0. 1 0. 0 0. I 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1. 0
TIME AFTER RUPTURE CSECONOSl
Fig. 153 Strain at steam generator outlet nozzle (SE-PC15-4) ..
96
z
' z :>
z c{
a: 1-Ul
z
' z
:>
z c{
a: 1-Ul
100.
75.
50.
25.
0.
-25.
-0. I 0. 0 0. I 0.2 0.3 0.4 ·0.5 0.6 0.7 0.8 0.9 -
TIME AFTER RUPTURE (5ECON0Sl
Fig. 154 Strain at steam generator outlet nozzle (SE-PC15-5).
150.
100.
50.
o.
-50.
-0. I o". 0 0. I 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9
TIME AFTER RUPTURE (5ECONOSl
Fig~ 155 Strain at steam generator outlet nozzle (SE-PC15-6).
97
I. 0
I. 0
150.
100.
z
' z :::>
50.
z oc{
a: 1-Ill
0.
-50.
-o. 1 0 0 0 0 0 1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 )•. 0
TIME AFTER RUPTURE (SECONOSJ
Fig. 156 Strain at steam generator outlet n0zzle (SE-PC15-8).
200.
I~U.
z 100.
z :::>
z 50.
oc{
a: I-rJ)
0.
-50.
-o. 1 0 0 0 0 0 1 0 0 2 0 0 3 0 0 4 0 0 5. 0 0 6 0 0 7 0 0 8 0 0 9 1 0 0
TIME AFTER RUPTURE (SECONOSJ
Fig. 157 Strain at steam qenerator outlet nozzle (SE-PC15-9).
98:
z
' z ::::>
z <(
a: 1-Ul
'"·
z
' z ::::>
z <(
a: 1-Ul
150.
100.
50.
0.
-o. 1 0. 0 0. I 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9
TIME AFTER RUPTURE CSECONOSJ
Fig. 158 Strain at steam generator outlet nozzle (SE-PC15-10).
150.
100.
50.
0.
-50.
-0. I 0. 0 0. I 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9
TIME AFTER RUPTURE CSECONDSl
Fig. 159 Strain at st~am generator outlet nozzle (SE-PC15-ll).
~99
I. 0
I. 0
z
' z :::)
z < a: 1-(/)
150.
100.
50.
0.
-50.
-0. I 0. 0 0. I 0 .. 2 0.3 0.4 0.5 0.6 0.7 0.8 0.9
TIME AFTER RUPTURE !SECONDS!
Fig. 160 Strain at steam generator outlet nozzle (SE-PC15-l2).
I 0.
0.
z ., ·-I 0. z
= -·20. < a: 1-(/1
-3C.
-40.
-o. 1 0. 0 0. I 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9
TIME AFTER RUPTURE !SECONDS!
Fig. 161 Strain at primary coolant pump. outlet (SE-PC18-l3).
)00
I. 0
I. 0
'-
50.
0.
z ..... z ~
-50.
z < a: ~
lll
-100.
-150.
-0. I 0. 0 0. I 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 I. 0
TIME AFTER RUPTURE !SECONDS!
Fig. 162 Strain·at primary coolant pump outlet (SE-PC18-14).
50.
0.
z ..... -50 . z
~ -I 00. < a: ~
lll
-150.
-200.
-0. I
..... ITJ"'M
" ' , ~ "\
• Pt.. .,. I I I
.r. & t; ''IT l .. $d w_. ,.,.. -·~ ,.,. ~ai•L~ '"'PVWV
0. 0 0. I
I,.,.,.. JT I
0.2 0.3 U.4 0.5 0.6 0.7 0.8 0.9
TIME AFTER RUPTURE !SECONOSl
I. 0
Fig. 163 Strain at primary coolant pump outlet (SE-PC18-l5).
101
25.
0.
z ..... z ::> -25.
z < a: I-(/)
-50.
-75.
-0. I 0. 0 0. f 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9
TIME AFTER RUPTURE (SECONDS>
Fig. 164 Strain at primary coolant_pump outlet (SE-PC18-16).
25.
n.
z ..... -25. z ::>
= -50. < a: 1-lll
-75.
-100.
-o. 1 0.0 0. I 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9
TIME AFTER RUPTURE (SECONDS>
Fig. 165 Stra1n at primary coolant pump outlet (SE-PC18-l7).
102
I. 0
..)
I. 0
z ..... z -:::>
z < a: ..... (/)
z ..... z -:::>
:;;;: -< a: ..... (/)
50.
0.
~ -50.
f--· N
~· . "'' ~ 1---· -· I "J ~T . , ~ I I J -~
-100.
-150.
-0. I 0. 0 0. I 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 I .0
TIME AFTER RUPTURE (SECONDS>
Fig. 166 Strain at primary coolant pump outlet (SE-PC18-18).
50.
25.
0.
~25.
-50 .
-75.
-100.
-0. I 0. 0 0. I 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1.0
TIME AFTER RUPTURE (SECONDS>
Fig. 167 Strain at primary coolant pump outlet (SE-PC18-19).
103
z
' z :::>
7:
< a:: 1-(/)
50.
0.
l=W I
-50.
l -tOO. ''H
-150.
-200.
-0. I 0. 0 0. I 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9
TIME AFTER RUPTURt !SECONOSl
Fig. 168 Strain at primary coolant pump outlet (SE-PC18-21).
25.
o.
z ' -25. z :::>
= -50. < a:: 1-(/l
-75.
-100.
-0. I 0. 0 0. I 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9
TIME AFTER RUPTURE <SECONDS!
Fig. 169 Strain at primary coolant pump outlet (SE-PC18-22).
104
I . 0
I. 0
z
' z ::)
z -t lr ..... (/)
z
50.
0.
-50.
-100.
-150.
-0. I 0. 0 0. I 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9
TIME AFTER RUPTURE <SECONDS!
Fig. 170 Strain at primary coolant pump outlet (SE-PC18-23).
50.
0.
-50.
= -I 00. -t a: ..... f/l
-150.
-200.
-0. I 0. 0 0. I 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9
TIME AFTER RUPTURE <SECONOSl
Fig. 171 Strain at primary coolant pump outlet. (SE-PC18-2'1).
105
I. 0
I. 0
1.
VI. REFERENC.ES
T. K. Samuels, Conformed Copy of LOFT Experiment Operating Specifi
cation, Volume 2, Nonnuclear Test Series Ll Experiment 2, NNE Ll-2,
Revision l (June 1976)_
2. T. K. Samuels, Conformed Copy of LOFT Experiment Operating Specifi
cation, Volume 2, Nonnuclear Test Seri~s Ll Experiment 3 and 3A,
Aerojet Nuclear Cumpany, EOS. Volume 2, NNE U-3 and -3A, Revision 2
(September 1976).
3. H. C. Robinson, Exper·iml:!nt Datu Report for LOFT Nonnuclear
Test Ll-2, TREE-NUREG-1026 (January 1977).
4. G. M. Millar, Experiment Data R!port for LOFT Nonnuclear Test LT-3,
TREE-NUREG-1065 (April 1977).
5. G. M. Millar, Experiment Data Report for LOFT Nonnuclear
Test Ll-3A, TREE-NUREG-1027 (December 1976).
6. H. C. Robinson, LOFT ~ysf.em C:llltl Test DescY'iption (Lns~-of-Cool.af!~·
txper1menLs Using a C:ore Simul_~~o.r), fREE-NURE.G-1019
(November 1976).
7. G. L. Biladeau et al, LOFT Experimental Measurements Unt.:t:!r·tainty
,~.na,ly~is, Aerojet Nuclear Company,
(September 1975).
LTR 141-39,. REG-76-560
II
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